WorldWideScience

Sample records for safe operating limits

  1. Safe operating envelope

    Energy Technology Data Exchange (ETDEWEB)

    Oliva, N [Ontario Hydro, Toronto, ON (Canada)

    1997-12-01

    Safe Operating Envelope is described representing: The outer bound of plant conditions within which day-to-day plant operation must be maintained in order to comply with regulatory requirements, associated safety design criteria and corporate nuclear safety goals. Figs.

  2. Safe operating envelope

    International Nuclear Information System (INIS)

    Oliva, N.

    1997-01-01

    Safe Operating Envelope is described representing: The outer bound of plant conditions within which day-to-day plant operation must be maintained in order to comply with regulatory requirements, associated safety design criteria and corporate nuclear safety goals. Figs

  3. Blue limits of the Blue Planet : An exploratory analysis of safe operating spaces for human water use under deep uncertainty

    NARCIS (Netherlands)

    Kwakkel, J.H.; Timmermans, J.S.

    2012-01-01

    In the Nature article ‘A safe operating space for humanity’, Rockström et al. (2009) introduce the concept of a safe operating space for humanity. A safe operating space is the space for human activities that will not push the planet out of the ‘Holocene state’ that has seen human civilizations

  4. ITER operating limit definition criteria

    International Nuclear Information System (INIS)

    Ciattaglia, S.; Barabaschi, P.; Carretero, J.A.; Chiocchio, S.; Hureau, D.; Girard, J.Ph.; Gordon, C.; Portone, A.; Rodrigo, L. Rodriguez; Roldan, C.; Saibene, G.; Uzan-Elbez, J.

    2009-01-01

    The operating limits and conditions (OLCs) are operating parameters and conditions, chosen among all system/components, which, together, define the domain of the safe operation of ITER in all foreseen ITER states (operation, maintenance, commissioning). At the same time they are selected to guarantee the required operation flexibility which is a critical factor for the success of an experimental machine such as ITER. System and components that are important for personnel or public safety (safety important class, SIC) are identified considering their functional importance in the overall plant safety analysis. SIC classification has to be presented already in the preliminary safety analysis report and approved by the licensing authority before manufacturing and construction. OLCs comprise the safety limits that, if exceeded, could result in a potential safety hazard, the relevant settings that determine the intervention of SIC systems, and the operational limits on equipment which warn against or stop a functional deviation from a planned operational status that could challenge equipment and functions. Some operational conditions, e.g. in-Vacuum Vessel (VV) radioactive inventories, will be controlled through procedures. Operating experience from present tokamaks, in particular JET, and from nuclear plants, is considered to the maximum possible extent. This paper presents the guidelines for the development of the ITER OLCs with particular reference to safety limits.

  5. Implementation of an Improved Safe Operating Envelope

    International Nuclear Information System (INIS)

    Prime, Robyn; McIntyre, Mark; Reeves, David

    2008-01-01

    This paper is a continuation of the paper presented at IYNC 2004 on 'The Definition of a Safe Operating Envelope'. The current paper concentrates on the implementation process of the Safe Operating Envelope employed at the Point Lepreau Generating Station. (authors)

  6. Implementation of an Improved Safe Operating Envelope

    Energy Technology Data Exchange (ETDEWEB)

    Prime, Robyn; McIntyre, Mark [NB Power Nuclear, P.O. Box 600, Lepreau, NB (Canada); Reeves, David [Atlantic Nuclear Services Ltd., PO Box 1268 Fredericton, NB (Canada)

    2008-07-01

    This paper is a continuation of the paper presented at IYNC 2004 on 'The Definition of a Safe Operating Envelope'. The current paper concentrates on the implementation process of the Safe Operating Envelope employed at the Point Lepreau Generating Station. (authors)

  7. Systems for the safe operation of the JET tokamak with tritium

    International Nuclear Information System (INIS)

    Stork, D.; Ageladarakis, P.; Bell, A.C.

    1999-01-01

    In 1997, the JET device was operated for an extensive campaign with deuterium-tritium (D-T) plasmas (the DTE1 campaign). A comprehensive network of machine protection systems was necessary so that this experimental campaign could be executed safely without damage to the machine or release of activated material. This network had been developed over many years of JET deuterium plasma operation and therefore the modifications for D-T operation was not a significant problem. The DTE1 campaign was executed successfully and safely and the machine protection systems proved reliable and robust and, in the limited cases where they were required to act, functioned correctly. The machine protection systems at JET are described and their categorisation and development over time are summarised. The management, commissioning and operational experience during DTE1 are discussed and some examples of fault scenarios are described. The experience with protection systems at JET highlights the importance of correct design and philosophy decisions being taken at an early stage. It is shown that this experience will be invaluable data input to the safe operation of future large fusion machines. (orig.)

  8. Prepare to protect: Operating and maintaining a tornado safe room.

    Science.gov (United States)

    Herseth, Andrew; Goldsmith-Grinspoon, Jennifer; Scott, Pataya

    2017-06-01

    Operating and maintaining a tornado safe room can be critical to the effective continuity of business operations because a firm's most valuable asset is its people. This paper describes aspects of operations and maintenance (O&M) for existing tornado safe rooms as well as a few planning and design aspects that affect the ultimate operation of a safe room for situations where a safe room is planned, but not yet constructed. The information is based on several Federal Emergency Management Agency safe room publications that provide guidance on emergency management and operations, as well as the design and construction of tornado safe rooms.

  9. Safe operation of critical assemblies and research reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1960-09-15

    Some countries have accumulated considerable experience in the operation of these reactors and have in the process developed safe practices. On the other hand, other countries which have recently acquired, or will soon acquire, such reactors do not have sufficient background of experience with them to have developed full knowledge regarding their safe operation. In this situation, the International Atomic Energy Agency has considered that it would be useful to make available to all its Member States a set of recommendations on the safe operation of these reactors, based on the accumulated experience and best practices. The Director General accordingly nominated a Pane Ion Safe Operation of Critical Assemblies and Research Reactors to assist the Agency's Secretariat in drafting such recommendations

  10. Standards for safe operation of research reactors

    International Nuclear Information System (INIS)

    1996-01-01

    The safety of research reactors is based on many factors such as suitable choice of location, design and construction according to the international standards, it also depends on well trained and qualified operational staff. These standards determine the responsibilities of all who are concerned with the research reactors safe operation, and who are responsible of all related activities in all the administrative and technical stages in a way that insures the safe operation of the reactor

  11. ITER Operating Limits and Conditions

    International Nuclear Information System (INIS)

    Ciattaglia, S.; Barabaschi, P.; Carretero, J.A.

    2006-01-01

    The Operating Limits and Conditions (OLCs) are operating parameters and conditions, chosen among all system/components, which together define the domain of the safe operation of ITER in all foreseen ITER status (operation, maintenance, commissioning). At the same time they are selected to guarantee the required operation flexibility which is a critical factor for the success of an experimental machine such as ITER. System and components important for personnel or public safety (Safety Important Class, SIC) are identified from the overall plant safety analysis on functional importance to safety of the components. SIC classification has to be presented already inside the preliminary safety analysis report and approved by the licensing safety authority before the relevant construction. OLCs comprise the safety limits, i.e. that if exceeded could result in a potential safety hazard, the relevant settings that determine the intervention of SIC systems and the operational limits on equipment which warn from or stop a functional departure from a planned operational status that could challenge equipment and functions. The safety limits have to indicate clearly states that leave the nominal safety state of ITER; they are derived from the safety analysis of ITER. OLCs can represent in some cases few parameters grouping together. Some operational conditions, e.g. inventories, will be controlled through no real time measurements and procedures. Operating experience from present tokamaks, in particular JET, and from nuclear plants is considered at the maximum possible extent. This paper presents the guidelines to develop the ITER OLCs with particular reference to safety limits. A few examples are reported as well as open issues on some OLCs control and measurement and the relevant R-and-D planned to solve the issues. (author)

  12. Safe Operation of Nuclear Power Plants. Code of Practice and Technical Appendices

    International Nuclear Information System (INIS)

    1969-01-01

    This book is in two parts. The first is a Code of Practice for the Safe Operation of Nuclear Power Plants and the second part is a compilation of technical appendices. Its object is to give information and illustrative examples that would be helpful in implementing the Code of Practice. This second part, although published under the same cover, is not part of the Code. Safe operation of a nuclear power plant postulates suitable siting and proper design, construction and management of the plant. Under the present Code of Practice for the Safe Operation of Nuclear Power Plants, those intending to operate the plant are recommended to prepare documentation which would deal with its operation and include safety analyses. The documentation in question would be reviewed by a regulatory body independent of the operating organization; operation would be authorized on the understanding that it would comply with limits and conditions designed to ensure safety. The Code may be subject to revision in the light of experience. The Appendices provide additional information together with some examples relating to certain topics dealt with in the Code; it must be emphasized that they are included as examples for information only and are not part of any recommendation. Purpose and scope: The recommendations in the Code are designed to protect the general public and the operating personnel from radiation hazards, and the Code forms part of the Agency's Safety Standards. The Code, which should be used in conjunction with the Agency's other Safety Standards, provides guidance and information to persons and authorities responsible for the operation of stationary nuclear power plants whose main function is the generation of thermal, mechanical or electrical power; it is not intended to apply to reactors used solely for experimental or research purposes. It sets forth minimum requirements which, it is believed, in the light of experience, must be met in order to achieve safe operation of a

  13. Operationalizing safe operating space for regional social-ecological systems.

    Science.gov (United States)

    Hossain, Md Sarwar; Dearing, John A; Eigenbrod, Felix; Johnson, Fiifi Amoako

    2017-04-15

    This study makes a first attempt to operationalize the safe operating space concept at a regional scale by considering the complex dynamics (e.g. non-linearity, feedbacks, and interactions) within a systems dynamic model (SD). We employ the model to explore eight 'what if' scenarios based on well-known challenges (e.g. climate change) and current policy debates (e.g. subsidy withdrawal). The findings show that the social-ecological system in the Bangladesh delta may move beyond a safe operating space when a withdrawal of a 50% subsidy for agriculture is combined with the effects of a 2°C temperature increase and sea level rise. Further reductions in upstream river discharge in the Ganges would push the system towards a dangerous zone once a 3.5°C temperature increase was reached. The social-ecological system in Bangladesh delta may be operated within a safe space by: 1) managing feedback (e.g. by reducing production costs) and the slow biophysical variables (e.g. temperature, rainfall) to increase the long-term resilience, 2) negotiating for transboundary water resources, and 3) revising global policies (e.g. withdrawal of subsidy) that negatively impact at regional scales. This study demonstrates how the concepts of tipping points, limits to adaptations, and boundaries for sustainable development may be defined in real world social-ecological systems. Copyright © 2017 The Authors. Published by Elsevier B.V. All rights reserved.

  14. Beyond Safe Operating Space: Finding Chemical Footprinting Feasible

    DEFF Research Database (Denmark)

    Posthuma, Leo; Bjørn, Anders; Zijp, Michiel C.

    2014-01-01

    undefined boundary in their selection of planetary boundaries delineating the “safe operating space for humanity”. Can we use the well-known concept of “ecological footprints” to express a chemical pollution boundary aimed at preventing the overshoot of the Earth’s capacity to assimilate environmental...... scenarios that allow us to avoid “chemical overshoot” beyond the Earth’s safe operating space....

  15. LHC collimator controls for a safe LHC operation

    International Nuclear Information System (INIS)

    Redaelli, S.; Assmann, R.; Losito, R.; Donze, M.; Masi, A.

    2012-01-01

    The Large Hadron Collider (LHC) collimation system is designed to protect the machine against beam losses and consists of 108 collimators, 100 of which are movable, located along the 27 km long ring and in the transfer lines. The cleaning performance and machine protection role of the system depend critically on accurate jaw positioning. A fully redundant control system has been developed to ensure that the collimators dynamically follow optimum settings in all phases of the LHC operational cycle. Jaw positions and collimator gaps are interlocked against dump limits defined redundantly as functions of time, beam energy and the β functions, which describe the focusing property of the beams. In this paper, the architectural choices that guarantee a safe LHC operation are presented. Hardware and software implementations that ensure the required performance are described. (authors)

  16. Gas Bearing Control for Safe Operation in Critical Speed Regions - Experimental Verification

    DEFF Research Database (Denmark)

    Theisen, Lukas R. S.; Niemann, Hans H.; Galeazzi, Roberto

    2015-01-01

    supported by gas bearings to extend their operating range. Using H∞-design methods, active lubrication techniques are proposed to enhance the damping, which in turn reduces the vibrations to a desired safe level. The control design is validated experimentally on a laboratory test rig, and shown to allow...... and deceleration patterns and avoidance of operation near the critical speeds, which is a limiting factor during operation, specially during run-downs. An approach for reducing the vibrations is by feedback controlled lubrication. This paper addresses the challenge of reducing vibrations in rotating machines...

  17. Integral Battery Power Limiting Circuit for Intrinsically Safe Applications

    Science.gov (United States)

    Burns, Bradley M.; Blalock, Norman N.

    2010-01-01

    A circuit topology has been designed to guarantee the output of intrinsically safe power for the operation of electrical devices in a hazardous environment. This design uses a MOSFET (metal oxide semiconductor field-effect transistor) as a switch to connect and disconnect power to a load. A test current is provided through a separate path to the load for monitoring by a comparator against a preset threshold level. The circuit is configured so that the test current will detect a fault in the load and open the switch before the main current can respond. The main current passes through the switch and then an inductor. When a fault occurs in the load, the current through the inductor cannot change immediately, but the voltage drops immediately to safe levels. The comparator detects this drop and opens the switch before the current in the inductor has a chance to respond. This circuit protects both the current and voltage from exceeding safe levels. Typically, this type of protection is accomplished by a fuse or a circuit breaker, but in order for a fuse or a circuit breaker to blow or trip, the current must exceed the safe levels momentarily, which may be just enough time to ignite anything in a hazardous environment. To prevent this from happening, a fuse is typically current-limited by the addition of the resistor to keep the current within safe levels while the fuse reacts. The use of a resistor is acceptable for non-battery applications where the wasted energy and voltage drop across the resistor can be tolerated. The use of the switch and inductor minimizes the wasted energy. For example, a circuit runs from a 3.6-V battery that must be current-limited to 200 mA. If the circuit normally draws 10 mA, then an 18-ohm resistor would drop 180 mV during normal operation, while a typical switch (0.02 ohm) and inductor (0.97 ohm) would only drop 9.9 mV. From a power standpoint, the current-limiting resistor protection circuit wastes about 18 times more power than the

  18. Hanford high level waste (HLW) tank mixer pump safe operating envelope reliability assessment

    International Nuclear Information System (INIS)

    Fischer, S.R.; Clark, J.

    1993-01-01

    The US Department of Energy and its contractor, Westinghouse Corp., are responsible for the management and safe storage of waste accumulated from processing defense reactor irradiated fuels for plutonium recovery at the Hanford Site. These wastes, which consist of liquids and precipitated solids, are stored in underground storage tanks pending final disposition. Currently, 23 waste tanks have been placed on a safety watch list because of their potential for generating, storing, and periodically releasing various quantities of hydrogen and other gases. Tank 101-SY in the Hanford SY Tank Farm has been found to release hydrogen concentrations greater than the lower flammable limit (LFL) during periodic gas release events. In the unlikely event that an ignition source is present during a hydrogen release, a hydrogen burn could occur with a potential to release nuclear waste materials. To mitigate the periodic gas releases occurring from Tank 101-SY, a large mixer pump currently is being installed in the tank to promote a sustained release of hydrogen gas to the tank dome space. An extensive safety analysis (SA) effort was undertaken and documented to ensure the safe operation of the mixer pump after it is installed in Tank 101-SY.1 The SA identified a need for detailed operating, alarm, and abort limits to ensure that analyzed safety limits were not exceeded during pump operations

  19. Operational limits and conditions and operating procedures for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    This Safety Guide was prepared as part of the Agency's programme for establishing safety standards relating to nuclear power plants. The present Safety Guide supersedes the IAEA Safety Guide on Operational Limits and Conditions for Nuclear Power Plants which was issued in 1979 as Safety Series No. 50-SG-O3. For a nuclear power plant to be operated in a safe manner, the provisions made in the final design and subsequent modifications shall be reflected in limitations on plant operating parameters and in the requirements on plant equipment and personnel. Under the responsibility of the operating organization, these shall be developed during the design safety evaluation as a set of operational limits and conditions (OLCs). A major contribution to compliance with the OLCs is made by the development and utilization of operating procedures (OPs) that are consistent with and fully implement the OLCs. The requirements for the OLCs and OPs are established in Section 5 of the IAEA Safety Requirements publication Safety of Nuclear Power Plants: Operation, which this Safety Guide supplements. The purpose of this Safety Guide is to provide guidance on the development, content and implementation of OLCs and OPs. The Safety Guide is directed at both regulators and owners/operators. This Safety Guide covers the concept of OLCs, their content as applicable to land based stationary power plants with thermal neutron reactors, and the responsibilities of the operating organization regarding their establishment, modification, compliance and documentation. The OPs to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide. The particular aspects of the procedures for maintenance, surveillance, in-service inspection and other safety related activities in connection with the safe operation of nuclear power plants are outside the scope of this Safety Guide but can be found in other IAEA Safety Guides. Section 2 indicates the

  20. Operational limits and conditions and operating procedures for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2000-01-01

    This Safety Guide was prepared as part of the Agency's programme for establishing safety standards relating to nuclear power plants. The present Safety Guide supersedes the IAEA Safety Guide on Operational Limits and Conditions for Nuclear Power Plants which was issued in 1979 as Safety Series No. 50-SG-O3. For a nuclear power plant to be operated in a safe manner, the provisions made in the final design and subsequent modifications shall be reflected in limitations on plant operating parameters and in the requirements on plant equipment and personnel. Under the responsibility of the operating organization, these shall be developed during the design safety evaluation as a set of operational limits and conditions (OLCs). A major contribution to compliance with the OLCs is made by the development and utilization of operating procedures (OPs) that are consistent with and fully implement the OLCs. The requirements for the OLCs and OPs are established in Section 5 of the IAEA Safety Requirements publication Safety of Nuclear Power Plants: Operation, which this Safety Guide supplements. The purpose of this Safety Guide is to provide guidance on the development, content and implementation of OLCs and OPs. The Safety Guide is directed at both regulators and owners/operators. This Safety Guide covers the concept of OLCs, their content as applicable to land based stationary power plants with thermal neutron reactors, and the responsibilities of the operating organization regarding their establishment, modification, compliance and documentation. The OPs to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide. The particular aspects of the procedures for maintenance, surveillance, in-service inspection and other safety related activities in connection with the safe operation of nuclear power plants are outside the scope of this Safety Guide but can be found in other IAEA Safety Guides. Section 2 indicates the

  1. Guideline for the preparation of safe operating procedures

    International Nuclear Information System (INIS)

    Stinnett, L.; Carroll, M.M.; Crooks, D.L.; Doyle, J.R.; Jeblick, H.G.; Kessel, D.S.; Tippy, M.W.; Stuckey, J.M.

    1981-03-01

    These procedures are written for activities that involve the use of explosives, dangerous chemicals, radioactive materials, hazardous sytems, and for certain types of operational facilities which present hazards. This guideline presents a suggested Safe Operating Procedures format

  2. Method of safely operating nuclear reactor

    International Nuclear Information System (INIS)

    Ochiai, Kanehiro.

    1976-01-01

    Purpose: To provide a method of safely operating an nuclear reactor, comprising supporting a load applied to a reactor container partly with secondary container facilities thereby reducing the load borne by the reactor container when water is injected into the core to submerge the core in an emergency. Method: In a reactor emergency, water is injected into the reactor core thereby to submerge the core. Further, water is injected into a gap between the reactor container and the secondary container facilities. By the injection of water into the gap between the reactor container and the secondary container facilities a large apparent mass is applied to the reactor container, as a result of which the reactor container undergoes the same vibration as that of the secondary container facilities. Therefore, the load borne by the reactor container itself is reduced and stress at the bottom part of the reactor container is released. This permits the reactor to be operated more safely. (Moriyama, K.)

  3. Guideline for the preparation of safe operating procedures

    International Nuclear Information System (INIS)

    Stinnett, L.; Armbrust, E.F.; Christy, V.W.; Doyle, J.R.; Kesinger, J.H.

    1977-03-01

    Sandia Laboratories Safe Operating Procedures (SOP) are written for activities which involve the use of explosives, dangerous chemicals, radioactive materials, hazardous systems, and certain types of operational facilities which present hazards. This guideline presents a suggested SOP format

  4. Embracing Safe Ground Test Facility Operations and Maintenance

    Science.gov (United States)

    Dunn, Steven C.; Green, Donald R.

    2010-01-01

    Conducting integrated operations and maintenance in wind tunnel ground test facilities requires a balance of meeting due dates, efficient operation, responsiveness to the test customer, data quality, effective maintenance (relating to readiness and reliability), and personnel and facility safety. Safety is non-negotiable, so the balance must be an "and" with other requirements and needs. Pressure to deliver services faster at increasing levels of quality in under-maintained facilities is typical. A challenge for management is to balance the "need for speed" with safety and quality. It s especially important to communicate this balance across the organization - workers, with a desire to perform, can be tempted to cut corners on defined processes to increase speed. Having a lean staff can extend the time required for pre-test preparations, so providing a safe work environment for facility personnel and providing good stewardship for expensive National capabilities can be put at risk by one well-intending person using at-risk behavior. This paper documents a specific, though typical, operational environment and cites management and worker safety initiatives and tools used to provide a safe work environment. Results are presented and clearly show that the work environment is a relatively safe one, though still not good enough to keep from preventing injury. So, the journey to a zero injury work environment - both in measured reality and in the minds of each employee - continues. The intent of this paper is to provide a benchmark for others with operational environments and stimulate additional sharing and discussion on having and keeping a safe work environment.

  5. 76 FR 29992 - Loan Policies and Operations; Lending and Leasing Limits and Risk Management

    Science.gov (United States)

    2011-05-24

    ... FARM CREDIT ADMINISTRATION 12 CFR Part 614 RIN 3052-AC60 Loan Policies and Operations; Lending and Leasing Limits and Risk Management AGENCY: Farm Credit Administration. ACTION: Final rule. SUMMARY: The... (collectively loan) concentration risks. We expect this final rule will increase the safe and sound operation of...

  6. Importance of safety review to the safe operation of a nuclear plant

    International Nuclear Information System (INIS)

    Brinkerhoff, L.C.

    1978-01-01

    Widely differing standards of construction of nuclear reactors are employed in different countries. Although the reactor vendors, including designers and construction contractors, have a vested interest in safety, the ultimate responsibility for safety rests with the reactor facility operator. Even though governmental agencies, either directly or indirectly, must take a strong lead in developing policies and practices of safe operation, the reactor facility operator must recognize and accept the full responsibility for safe operation of the facility. The policies and practices of safe operation imposed by governmental agencies must help assure the prudent operation and the adequate maintenance of those structures, systems, and components of importance to safety. Since each country has a slightly different philosophy for achieving safety and each vendor utilizes different structures, systems, and components to fulfil this philosophy, it is imperative that the facility operator adequately maintain those engineered safety features and those plant protective systems which have been engineered into achieving the desired levels of safety. An additional method of helping to assure that those structures, systems, and components of importance to safety are prudently operated and adequately maintained is to assign the full safety responsibility for the overall operations of the reactor facility to the operating organization, i.e. assigning a 'line of responsibility' within the reactor facility operator. This assurance can be further strengthened by requiring that the facility operator establish a safety review body that overviews the operation and assures that the operating organization complies with those policies and practices of safe operation which have been imposed on the reactor facility. (author)

  7. Digital image monitoring to optimise safe port operation

    CSIR Research Space (South Africa)

    Phelp, D

    2008-11-01

    Full Text Available This paper describes a low cost video system ‘Harbour Watch’, which can be used to support safe port operations, especially in developing countries. Preset digital images are geo-referenced and then archived for later analysis to improve...

  8. Investigation on the Short Circuit Safe Operation Area of SiC MOSFET Power Modules

    DEFF Research Database (Denmark)

    Reigosa, Paula Diaz; Luo, Haoze; Iannuzzo, Francesco

    2016-01-01

    This paper gives a better insight of the short circuit capability of state-of-the-art SiC MOSFET power modules rated at 1.2 kV by highlighting the physical limits under different operating conditions. Two different failure mechanisms have been identified, both reducing the short-circuit capability...... of SiC power modules in respect to discrete SiC devices. Based on such failure mechanisms, two short circuit criteria (i.e., short circuit current-based criterion and gate voltage-based criterion) are proposed in order to ensure their robustness under short-circuit conditions. A Safe Operation Area (SOA...

  9. Safety analysis to support a safe operating envelope for fuel

    International Nuclear Information System (INIS)

    Gibb, R.A.; Reid, P.J.

    1998-01-01

    This paper presents an approach for defining a safe operating envelope for fuel. 'Safe operating envelope' is defined as an envelope of fuel parameters defined for application in safety analysis that can be related to, or used to define, the acceptable range of fuel conditions due to operational transients or deviations in fuel manufacturing processes. The paper describes the motivation for developing such a methodology. The methodology involved four steps: the update of fission product inventories, the review of sheath failure criteria, a review of input parameters to be used in fuel modelling codes, and the development of an improved fission product release code. This paper discusses the aspects of fuel sheath failure criteria that pertain to operating or manufacturing conditions and to the evaluation and selection of modelling input data. The other steps are not addressed in this paper since they have been presented elsewhere. (author)

  10. Safe Operation of Critical Assemblies and Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1961-05-15

    This Manual is provided as a guide to the safe operation of critical assemblies and small research reactors. It is intended that it should be used by all authorities and persons concerned with, or responsible for, the use of such equipment, in addition to the scientists and technologists who are actually working with, or operating it. It is suggested that it will be of use to those wishing to design and manufacture, or purchase, critical assemblies or research reactors, as well as those already in possession of them, and that it will prove particularly helpful to those users who have no direct access to other collected sources of information. This Manual is not a set of rules or a code of practice, but a series of recommendations which must be interpreted with scientific judgement in their application to any particular problem. The guiding principles are given from which good operational procedures may be established and improved. The promulgation of rigid standards is both impossible and undesirable at the present time, since the topics discussed form part of a rapidly growing science and technology. Therefore, any recommendations made should not be used to restrict or inhibit future developments. The Manual is intended mainly for use in those Member States where there has been little experience in the operation of critical assemblies and research reactors. It has been compounded from the best practices which exist in Member States having a large amount of such experience, so that nothing in it should conflict with the best practices to be encountered in the field of safe operation.

  11. Safe Operation of Critical Assemblies and Research Reactors

    International Nuclear Information System (INIS)

    1961-01-01

    This Manual is provided as a guide to the safe operation of critical assemblies and small research reactors. It is intended that it should be used by all authorities and persons concerned with, or responsible for, the use of such equipment, in addition to the scientists and technologists who are actually working with, or operating it. It is suggested that it will be of use to those wishing to design and manufacture, or purchase, critical assemblies or research reactors, as well as those already in possession of them, and that it will prove particularly helpful to those users who have no direct access to other collected sources of information. This Manual is not a set of rules or a code of practice, but a series of recommendations which must be interpreted with scientific judgement in their application to any particular problem. The guiding principles are given from which good operational procedures may be established and improved. The promulgation of rigid standards is both impossible and undesirable at the present time, since the topics discussed form part of a rapidly growing science and technology. Therefore, any recommendations made should not be used to restrict or inhibit future developments. The Manual is intended mainly for use in those Member States where there has been little experience in the operation of critical assemblies and research reactors. It has been compounded from the best practices which exist in Member States having a large amount of such experience, so that nothing in it should conflict with the best practices to be encountered in the field of safe operation.

  12. From Planetary Boundaries to national fair shares of the global safe operating space — How can the scales be bridged?

    NARCIS (Netherlands)

    Häyhä, Tiina; Lucas, Paul L.|info:eu-repo/dai/nl/272607444; van Vuuren, Detlef P.|info:eu-repo/dai/nl/11522016X; Cornell, Sarah E.; Hoff, Holger

    2016-01-01

    The planetary boundaries framework proposes quantitative global limits to the anthropogenic perturbation of crucial Earth system processes, and thus marks out a planetary safe operating space for human activities. Yet, decisions regarding resource use and emissions are mostly made at less aggregated

  13. Making operations on standard-library containers strongly exception safe

    DEFF Research Database (Denmark)

    Katajainen, Jyrki

    2007-01-01

    -library containers to provide the strong guarantee of exception safety, instead of the default guarantee, without violating the stringent performance requirements specified in the C++ standard. In particular, we show that every strongly exception-safe operation on dynamic arrays and ordered dictionaries is only...... a constant factor slower than the corresponding default-guarantee operation. In terms of the amount of space, the overhead introduced is linear in the number of elements stored....

  14. Management for nuclear power plants for safe operation

    International Nuclear Information System (INIS)

    Kueffer, K.

    1981-01-01

    This lecture covers management aspects which have an immediate bearing on safety and identifies the objectives and tasks of management which are required for safe operation of a nuclear power plant and is based on the Codes of Practice and Safety Guides of the IAEA as well as arrangements in use at the Swiss Nuclear Power Station Beznau. (orig./RW)

  15. System Safety Program Plan for Project W-314, tank farm restoration and safe operations

    International Nuclear Information System (INIS)

    Boos, K.A.

    1996-01-01

    This System Safety Program Plan (SSPP) outlines the safety analysis strategy for project W-314, ''Tank Farm Restoration and Safe Operations.'' Project W-314 will provide capital improvements to Hanford's existing Tank Farm facilities, with particular emphasis on infrastructure systems supporting safe operation of the double-shell activities related to the project's conceptual Design Phase, but is planned to be updated and maintained as a ''living document'' throughout the life of the project to reflect the current safety analysis planning for the Tank Farm Restoration and Safe Operations upgrades. This approved W-314 SSPP provides the basis for preparation/approval of all safety analysis documentation needed to support the project

  16. Contextual Challenges to Safe Surgery in a Resource-limited Setting: A Multicenter, Multiprofessional Qualitative Study.

    Science.gov (United States)

    Scott, John W; Lin, Yihan; Ntakiyiruta, Georges; Mutabazi, Zeta A; Davis, William Austin; Morris, Megan A; Smink, Douglas S; Riviello, Robert; Yule, Steven

    2018-03-01

    Safe surgery should be available to all patients, no matter the setting. The purpose of this study was to explore the contextual-specific challenges to safe surgical care encountered by surgeons and surgical teams in many in low- and middle-income countries (LMICs), and to understand the ways in which surgical teams overcome them. Optimal surgical performance is highly complex and requires providers to integrate and communicate information regarding the patient, task, team, and environment to coordinate team-based care that is timely, effective, and safe. Resource limitations common to many LMICs present unique challenges to surgeons operating in these environments, but have never been formally described. Using a grounded theory approach, we interviewed 34 experienced providers (surgeons, anesthetists, and nurses) at the 4 tertiary referral centers in Rwanda, to understand the challenges to safe surgical care and strategies to overcome them. Interview transcripts were coded line-by-line and iteratively analyzed for emerging themes until thematic saturation was reached. Rwandan-described challenges related to 4 domains: physical resources, human resources, overall systems support, and communication/language. The majority of these challenges arose from significant variability in either the quantity or quality of these domains. Surgical providers exhibited examples of resilient strategies to anticipate, monitor, respond to, and learn from these challenges. Resource variability rather than lack of resources underlies many contextual challenges to safe surgical care in a LMIC setting. Understanding these challenges and resilient strategies to overcome them is critical for both LMIC surgical providers and surgeons from HICs working in similar settings.

  17. Simple Automatic File Exchange (SAFE) to Support Low-Cost Spacecraft Operation via the Internet

    Science.gov (United States)

    Baker, Paul; Repaci, Max; Sames, David

    1998-01-01

    Various issues associated with Simple Automatic File Exchange (SAFE) are presented in viewgraph form. Specific topics include: 1) Packet telemetry, Internet IP networks and cost reduction; 2) Basic functions and technical features of SAFE; 3) Project goals, including low-cost satellite transmission to data centers to be distributed via an Internet; 4) Operations with a replicated file protocol; 5) File exchange operation; 6) Ground stations as gateways; 7) Lessons learned from demonstrations and tests with SAFE; and 8) Feedback and future initiatives.

  18. Safe operation of research reactors and critical assemblies. Code of practice and annexes. 1984 ed

    International Nuclear Information System (INIS)

    1984-01-01

    The safe operation of research reactors and critical assemblies (hereafter termed 'reactors') requires proper design, construction, management and supervision. This Code of Practice deals mainly with management and supervision. The provisions of the Code apply to the whole life of the reactor, including modification, updating and upgrading. The Code may be subject to revision in the light of experience and the state of technology. The Code is aimed at defining minimum requirements for the safe operation of reactors. Emphasis is placed on which safety requirements should be met rather than on specifying how these requirements may be met. The Code also provides guidance and information to persons and authorities responsible for the operation of reactors. The Code recommends that documents dealing with the operation of reactors and including safety analyses be prepared and submitted for review and approval to a regulatory body. Operation would be authorized on the understanding that it would comply with limits and conditions designed to ensure safety. The Code covers a wide range of reactor types, which gives rise to a variety of safety issues. Safety issues applicable to specific reactor types only (e.g. fast reactors) are not necessarily covered in this Code. Some of the recommendations in the Code are not directly applicable to critical assemblies. A recommendation may therefore be interpreted according to the type of reactor concerned. In such cases the words 'adequate' and 'appropriate' are used to mean 'adequate' or 'appropriate' for the type of reactor under consideration.

  19. Management of nuclear power plants for safe operation

    International Nuclear Information System (INIS)

    1984-01-01

    This Guide identifies the main objectives and responsibilities of management with respect to safe operation of nuclear power plants. The Guide discusses the factors to be considered in structuring the operating organization to meet these objectives, to establish the management programmes that assure the safety tasks are performed, and to see that the services and facilities needed to accomplish the tasks are available. The Guide is primarily addressed to safety matters directly related to the operating phase. It assumes, in other words, that the safety aspects of siting, design, manufacturing and construction have been resolved. However, it also covers the interrelationships between operations and design, construction and commissioning, including the involvement of the operating organization in appropriate reviews of safety issues with reference to the future operating phase. The Guide is mainly restricted to matters of principle in relation to management-level decision making aimed at establishing safety policies. It is therefore not suitable for implementing such policies at the operational level. The IAEA Codes of Practice and Safety Guides provide detailed guidance for the latter purpose in those areas considered appropriate

  20. Fail-safe computer-based plant protection systems

    International Nuclear Information System (INIS)

    Keats, A.B.

    1983-01-01

    A fail-safe mode of operation for computers used in nuclear reactor protection systems was first evolved in the UK for application to a sodium cooled fast reactor. The fail-safe properties of both the hardware and the software were achieved by permanently connecting test signals to some of the multiplexed inputs. This results in an unambiguous data pattern, each time the inputs are sequentially scanned by the multiplexer. The ''test inputs'' simulate transient excursions beyond defined safe limits. The alternating response of the trip algorithms to the ''out-of-limits'' test signals and the normal plant measurements is recognised by hardwired pattern recognition logic external to the computer system. For more general application to plant protection systems, a ''Test Signal Generator'' (TSG) is used to compute and generate test signals derived from prevailing operational conditions. The TSG, from its knowledge of the sensitivity of the trip algorithm to each of the input variables, generates a ''test disturbance'' which is superimposed upon each variable in turn, to simulate a transient excursion beyond the safe limits. The ''tripped'' status yielded by the trip algorithm when using data from a ''disturbed'' input forms part of a pattern determined by the order in which the disturbances are applied to the multiplexer inputs. The data pattern formed by the interleaved test disturbances is again recognised by logic external to the protection system's computers. This fail-safe mode of operation of computer-based protection systems provides a powerful defence against common-mode failure. It also reduces the importance of software verification in the licensing procedure. (author)

  1. Software functions for safe operation - learning from Sizewell-B

    International Nuclear Information System (INIS)

    Welbourne, D.

    1996-01-01

    Future nuclear plants will use computer-based systems extensively. Regulatory acceptance must be planned and not underestimated. Commercial software packages will simplify it, but costly analysis and demonstration may be needed. Multiplexed control needs preparation of extensive configuration data and careful checking. On-screen soft control will need consideration of the integrity of the control path. Display design should follow human factors analysis of the operators' needs, and display layout needs great care for clarity. Computer-based system with planned quality will then bring great benefits in safe operation. (author) 1 fig., 3 refs

  2. Planetary boundaries: exploring the safe operating space for humanity

    Science.gov (United States)

    Johan Rockström; Will Steffen; Kevin Noone; Asa Persson; F. Stuart Chapin; Eric Lambin; Timothy M. Lenton; Marten Scheffer; Carl Folke; Hans Joachim Schellnhuber; Björn Nykvist; Cynthia A. de Wit; Terry Hughes; Sander van der Leeuw; Henning Rodhe; Sverker Sörlin; Peter K. Snyder; Robert Costanza; Uno Svedin; Malin Falkenmark; Louise Karlberg; Robert W. Corell; Victoria J. Fabry; James Hansen; Brian Walker; Diana Liverman; Katherine Richardson; Paul Crutzen; Jonathan Foley

    2009-01-01

    Anthropogenic pressures on the Earth System have reached a scale where abrupt global environmental change can no longer be excluded. We propose a new approach to global sustainability in which we define planetary boundaries within which we expect that humanity can operate safely. Transgressing one or more planetary boundaries may be deleterious or even catastrophic due...

  3. Psychosocial aspect of safe operation in Japanese nuclear power plants

    International Nuclear Information System (INIS)

    Kuroda, Isao

    1988-01-01

    It is not easy to reveal the reasons of safe operation of N.P.P. because many complicated factors are interrelated. However, to clarify the effective factors of the recent safe operation of Japanese N.P.P. is the important thema of research to continue this condition and the more improved level. At present, the follwing factors can be pointed out; 1) Influential safety policy of regulatory structures. 2) Enthusiastic and careful company policy on N.P.P. safety. 3) Close and stable relationship of the industries with companies on research, training and maintenance. 4) Collaborated safety research among scientific facilities, companies and manufacturers. 5) Good organization and management for N.P.P. personnel. 6) Well organized training program in company and training facilities. 7) Highly motivated N.P.P. personnel with high educational background. 8) Company atmosphere on N.P.P. safety. 9) Public opinion on nuclear power safety. (author)

  4. A logic scheme for regulating safe operation of research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Ahmad, E E [Reactor Department, Nuclear Research Center, Atomic Energy Authority, Cairo (Egypt); Effat, A; Rahman, F A [Operational Saety Dept, National Center of Nuclear Safety and Radiation Control Atomic Energy Authority, Cairo (Egypt)

    1997-12-31

    This investigation presents a logic scheme for regulating the safe operation of research reactor in accordance with the new revision of SS-35 and revised by the 10 CFR. It emphasizes the regulatory inspection and enforcement (RI end E) during the reactor operation phase. IT is developed to provide information, guidance and recommendations to be taken when constructing the RI and E program that could be applied to the operational phase of the egyptian Research Reactors. In the operational phase, the regulatory inspection (RI) means an examination, observation, measurement, or test undertaken or on behalf of the nuclear regulatory body (NRB) during operation to verify that the nuclear materials, components, systems and structures as well operational activities, processes, procedures and personnel competence and performance are in accordance with the requirements established or the provisions approved by NRB or specified in the operational license or contained in regulations. Regulatory inspection includes both routine and non-routine ones. Any of them may be announced or unannounced. The problems identified by the RI must be resolved by the proper RE actions. The RE actions include investigative and corrective RE actions. These RI and E procedures for regulating safe operation of research reactors are presented as flow charts and then developed as a computer logic scheme. The software program is very efficient, very friendly, very simple and is interactive in nature such that the program asks the user certain questions about essential steps that guide the (RI and E) for research reactors, and user responds. The program proceeds based on this response until all the necessary steps for (RI and E) are accomplished. 5 figs.

  5. Management of nuclear power plants for safe operation

    International Nuclear Information System (INIS)

    Kueffer, K.

    1980-01-01

    This lecture covers management aspects which have an immediate bearing on safety and identifies the objectives and tasks of management which are required for safe operation of a nuclear power plant and is based on the Codes of Practice and Safety Guides of the IAEA as well as arrangements in use at the Swiss Nuclear Power Station Beznau. This lecture - discusses the factors to be considered in structuring the operating organization, the support to be provided to plant management, the services and facilities needed and the management system for assuring the safety tasks are performed - describes the responsibilities of plant management and operating organization - outlines the requirements for recruitment, training and retraining as well as qualification and authorization of personnel - describes the programmes for maintenance, testing, examination, inspection, radiological protection, quality assurance, waste management, fuel management, emergency arrangement and security - describes the development of plant operating procedures including procedures to protect the personnel - outlines the requirements for initial and subsequent operation - describes the importance for evaluation and feedback of operating experience - describes the procedures for changes in hardware, procedures and set points - outlines the information flow and the requirements in reference to records and reports. (orig./RW)

  6. A QMU approach for characterizing the operability limits of air-breathing hypersonic vehicles

    International Nuclear Information System (INIS)

    Iaccarino, Gianluca; Pecnik, Rene; Glimm, James; Sharp, David

    2011-01-01

    The operability limits of a supersonic combustion engine for an air-breathing hypersonic vehicle are characterized using numerical simulations and an uncertainty quantification methodology. The time-dependent compressible flow equations with heat release are solved in a simplified configuration. Verification, calibration and validation are carried out to assess the ability of the model to reproduce the flow/thermal interactions that occur when the engine unstarts due to thermal choking. quantification of margins and uncertainty (QMU) is used to determine the safe operation region for a range of fuel flow rates and combustor geometries. - Highlights: → In this work we introduce a method to study the operability limits of hypersonic scramjet engines. → The method is based on a calibrated heat release model. → It accounts explicitly for uncertainties due to flight conditions and model correlations. → We examine changes due to the combustor geometry and fuel injection.

  7. From Planetary Boundaries to national fair shares of the global safe operating space - How can the scales be bridged?

    Science.gov (United States)

    Häyhä, Tiina; Cornell, Sarah; Lucas, Paul; van Vuuren, Detlef; Hoff, Holger

    2016-04-01

    The planetary boundaries framework proposes precautionary quantitative global limits to the anthropogenic perturbation of crucial Earth system processes. In this way, it marks out a planetary 'safe operating space' for human activities. However, decisions regarding resource use and emissions are mostly made at much smaller scales, mostly by (sub-)national and regional governments, businesses, and other local actors. To operationalize the planetary boundaries, they need to be translated into and aligned with targets that are relevant at these smaller scales. In this paper, we develop a framework that addresses the three dimension of bridging across scales: biophysical, socio-economic and ethical, to provide a consistent universally applicable approach for translating the planetary boundaries into national level context-specific and fair shares of the safe operating space. We discuss our findings in the context of previous studies and their implications for future analyses and policymaking. In this way, we help link the planetary boundaries framework to widely- applied operational and policy concepts for more robust strong sustainability decision-making.

  8. Recommended Practices for the Safe Design and Operation of Flywheels

    Energy Technology Data Exchange (ETDEWEB)

    Bender, Donald Arthur [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-12-01

    Flywheel energy storage systems are in use globally in increasing numbers . No codes pertaining specifically to flywheel energy storage exist. A number of industrial incidents have occurred. This protocol recommends a technical basis for safe flywheel de sign and operation for consideration by flywheel developers, users of flywheel systems and standards setting organizations.

  9. The safe operation zone of the spark ignition engine working with dual renewable supplemented fuels (hydrogen+ethyl alcohol)

    Energy Technology Data Exchange (ETDEWEB)

    Al-Baghdadi, Maher Abdul-Resul Sadiq [Babylon Univ., Dept. of Mechanical Engineering, Babylon (Iraq)

    2001-04-01

    The effect of the amount of hydrogen/ethyl alcohol addition on the performance and pollutant emission of a four-stroke spark ignition engine has been studied. The results of the study show that all engine performance parameters have been improved when operating the gasoline spark ignition engine with dual addition of hydrogen and ethyl alcohol. The important improvements of alcohol addition are to reduce the NOx emission while increasing the higher useful compression ratio and output power of hydrogen-supplemented engine. An equation has been derived from experimental data to specify the least quantity of ethyl alcohol blended with gasoline and satisfying constant NOx emission when hydrogen is added. A chart limiting the safe operation zone of the engine fueled with dual renewable supplemented fuel, (hydrogen and ethyl alcohol) has been produced. The safe zone provides lower NOx and CO emission, lower s.f.c. and higher brake power compared to an equivalent gasoline engine. When ethyl alcohol is increased over 30%, it causes unstable engine operation which can be related to the fact that the fuel is not vaporized, and this causes a reduction in both brake power and efficiency. (Author)

  10. Universality, marginal operators, and limit cycles

    International Nuclear Information System (INIS)

    Glazek, Stanislaw D.; Wilson, Kenneth G.

    2004-01-01

    The universality of renormalization-group limit-cycle behavior is illustrated with a simple discrete Hamiltonian model. A nonperturbative renormalization-group equation for the model is soluble analytically at criticality and exhibits one marginal operator (made necessary by the limit cycle) and an infinite set of irrelevant operators. Relevant operators are absent. The model exhibits an infinite series of bound-state energy eigenvalues. This infinite series approaches an exact geometric series as the eigenvalues approach zero--also a consequence of the limit cycle. Wegner's eigenvalues for irrelevant operators are calculated generically for all choices of parameters in the model. We show that Wegner's eigenvalues are independent of location on the limit cycle, in contrast with Wegner's operators themselves, which vary depending on their location on the limit cycle. An example is then used to illustrate numerically how one can tune the initial Hamiltonian to eliminate the first two irrelevant operators. After tuning, the Hamiltonian's bound-state eigenvalues converge much more quickly than otherwise to an exact geometric series

  11. Unmanned Aerial Systems Traffic Management (UTM): Safely Enabling UAS Operations in Low-Altitude Airspace

    Science.gov (United States)

    Jung, Jaewoo; Kopardekar, Parimal H.

    2016-01-01

    Flexibility where possible, and structure where necessary. Consider the needs of national security, safe airspace operations, economic opportunities, and emerging technologies. Risk-based approach based on population density, assets on the ground, density of operations, etc. Digital, virtual, dynamic, and as needed UTM services to manage operations.

  12. 49 CFR 398.5 - Parts and accessories necessary for safe operation.

    Science.gov (United States)

    2010-10-01

    ... REGULATIONS TRANSPORTATION OF MIGRANT WORKERS § 398.5 Parts and accessories necessary for safe operation. (a... not be of welded construction. The installation shall be such as not to cause cracking, warping, or... high, by attachment of sideboards to the permanent body construction if necessary. Stake body...

  13. Water hydraulic manipulator for fail safe and fault tolerant remote handling operations at ITER

    International Nuclear Information System (INIS)

    Nieminen, Peetu; Esque, Salvador; Muhammad, Ali; Mattila, Jouni; Vaeyrynen, Jukka; Siuko, Mikko; Vilenius, Matti

    2009-01-01

    Department of Intelligent Hydraulics and Automation (IHA) of Tampere University of Technology has been involved in the European Fusion program since 1994 within the ITER reactor maintenance activities. In this paper we discuss the design and development of a six degrees of freedom water hydraulic manipulator with a force feedback for teleoperation tasks. The manipulator is planned to be delivered to Divertor Test Platform 2 (DTP2) during year 2008. The paper also discusses the possibility to improve the fail safe and redundant operation of the manipulator. During the design of the water hydraulic manipulator, special provisions have been made in order to meet the safety requirements such as servo valve block for redundant operation and safety vane brakes for fail safe operation.

  14. Operational limits and disruptions in ITER

    Energy Technology Data Exchange (ETDEWEB)

    Tsunematsu, T; Mizoguchi, T; Yoshino, R [Japan Atomic Energy Research Inst., Tokyo (Japan); Borrass, K; Engelmann, F; Pacher, G; Pacher, H [Max-Planck-Institut fuer Plasmaphysik, Garching (Germany, F.R.). NET Design Team; Cohen, S; Post, D [Princeton Univ., NJ (USA). Plasma Physics Lab.; Hogan, J; Uckan, N A [Oak Ridge National Lab., TN (USA); Krasheninnikov, S; Mukhovatov, V; Parail, V

    1990-12-15

    Detailed knowledge of the operational limits for beta, q and the plasma density will be required for successful and flexible operation of ITER. In this paper, the present data base and guidelines on operational limits and disruptions in the ITER design are presented. 10 refs., 1 fig.

  15. Safe and efficient operation of multistage cold compressor systems

    International Nuclear Information System (INIS)

    Kauschke, M.; Haberstroh, C.; Quack, H.

    1996-01-01

    Large refrigeration rates in the temperature range of super fluid helium can only be obtained with the help of centrifugal cold compressors. For the large 2 K systems, four compression stages are necessary to reach atmospheric pressure. Centrifugal cold compressors are quite sensitive to mass flow and suction temperature variations; but these have to be expected in a real system. The first step in the systems design is to find safe and efficient quasi-stationary modes of operation. The system which is being proposed for the TESLA refrigerators relies on two features. The first is to allow the room temperature screw compressor, downstream of the cold compressors to work occasionally with a subatmospheric suction pressure. The second is to stabilize the suction temperature of the third stage of compression at about 10 K. With these features it is possible, that in all modes of operation all four compressor stages operate exactly at their design point

  16. Organisational factors important to the safe operation of NPPs

    International Nuclear Information System (INIS)

    Frischknecht, Albert; Baumont, Genevieve

    2000-01-01

    The purpose of this paper is to present the achievements of a group of human factor specialists known as Expanded Task Force on Human Factors (ETF). ETF is part of the Principal Working Group No.1 (PWG1) on 'Operating Experience and Human Factors' of the Committee on Nuclear Safety Installations (CSNI) of the OECD Nuclear Energy Agency (NEA). Today, as shown by incident analysis, technology is so far developed that human behaviour and organisational deficiencies can contribute to a major part of the root causes of incidents in nuclear power plants. The influence of the organisation on the safe behaviour and performance of individuals is recognised as a relevant issue for the safety of nuclear power plants (NPPs). The need for an up-to-date basis of knowledge in this area was recognised by CSNI and therefore the ETF organised a workshop, in Switzerland, in 1998, on Organisational Factors. During the workshop, different aspects of organisational influences on the safe operation of NPPs were discussed and twelve important organisational factors concerning safety related activities in a NPP were identified. The result of the workshop is summarised in a state-of-the-art Report (SOAR) 'Identification and Assessment of Organisational Factors Related to the Safety of NPPs' issued by the OECD/NEA. The present paper gives an overview on the main findings of the workshop and conclusions concerning the evaluation of organisational factors. (author)

  17. Operational limits and conditions and operating procedures for research reactors. Safety guide

    International Nuclear Information System (INIS)

    2008-01-01

    This publication provides practical guidance on all important aspects of developing, formulating and presenting the operational limits and conditions as well as the operating procedures for research reactors. It covers the concept of operational limits and conditions, their content, and the responsibilities of the operating organization with respect to their establishment, modification, documentation and compliance. The guidance also covers the training of operating personnel on performing periodic testing, established by the operational limits and conditions, and operating procedures

  18. 78 FR 75289 - Airworthiness Directives; BAE Systems (Operations) Limited Airplanes

    Science.gov (United States)

    2013-12-11

    ... introduce a new safe life of 16,000 flight cycles (FC) for certain NLG main fittings, having a Part Number... AD would require revising the maintenance program by incorporating a new safe-life limitation for the... steering to the left. Cracks in the NLG Bell Housing are not detectable with the NLG fitted to the...

  19. Safe Reentry for False Aneurysm Operations in High-Risk Patients.

    Science.gov (United States)

    Martinelli, Gian Luca; Cotroneo, Attilio; Caimmi, Philippe Primo; Musica, Gabriele; Barillà, David; Stelian, Edmond; Romano, Angelo; Novelli, Eugenio; Renzi, Luca; Diena, Marco

    2017-06-01

    In the absence of a standardized safe surgical reentry strategy for high-risk patients with large or anterior postoperative aortic false aneurysm (PAFA), we aimed to describe an effective and safe approach for such patients. We prospectively analyzed patients treated for PAFA between 2006 and 2015. According to the preoperative computed tomography scan examination, patients were divided into two groups according to the anatomy and extension of PAFA: in group A, high-risk PAFA (diameter ≥3 cm) developed in the anterior mediastinum; in group B, low-risk PAFA (diameter <3 cm) was situated posteriorly. For group A, a safe surgical strategy, including continuous cerebral, visceral, and coronary perfusion was adopted before resternotomy; group B patients underwent conventional surgery. We treated 27 patients (safe reentry, n = 13; standard approach, n = 14). Mean age was 60 years (range, 29 to 80); 17 patients were male. Mean interval between the first operation and the last procedure was 4.3 years. Overall 30-day mortality rate was 7.4% (1 patient in each group). No aorta-related mortality was observed at 1 and 5 years in either group. The Kaplan-Meier overall survival estimates at 1 and 5 years were, respectively, 92.3% ± 7.4% and 73.4% ± 13.4% in group A, and 92.9% ± 6.9% and 72.2% ± 13.9% in group B (log rank test, p = 0.830). Freedom from reoperation for recurrent aortic disease was 100% at 1 year and 88% at 5 years. The safe reentry technique with continuous cerebral, visceral, and coronary perfusion for high-risk patients resulted in early and midterm outcomes similar to those observed for low-risk patients undergoing conventional surgery. Copyright © 2017 The Society of Thoracic Surgeons. Published by Elsevier Inc. All rights reserved.

  20. Safe design and operation of fluidized-bed reactors: Choice between reactor models

    NARCIS (Netherlands)

    Westerink, E.J.; Westerterp, K.R.

    1990-01-01

    For three different catalytic fluidized bed reactor models, two models presented by Werther and a model presented by van Deemter, the region of safe and unique operation for a chosen reaction system was investigated. Three reaction systems were used: the oxidation of benzene to maleic anhydride, the

  1. Basic national requirements for safe design, construction and operation

    International Nuclear Information System (INIS)

    Franzen, L.F.

    1980-01-01

    Nuclear power plants have to be save. Vendors and utilities operating such plants, are convinced that their plants meet this requirement. Who, however, is establishing the safety requirements to be met by those manufacturing and operating nuclear power plants. What are the mechanisms to control whether the features provided assure the required safety level. Who controls whether the required and planned safety features are really provided. Who is eventually responsible for assuring safety after commissioning of a nuclear power plant. These fundamental questions being raised in many discussions on safety and environmental protection are dealt with in the following sections: (1) Fundamental safety requirements on nuclear power plants, in which such items as risk, legal bases and licensing procedure are discussed, (2) Surveillance during construction, in which safety analysis report, siting, safety evaluation, document examination, quality assurance, and commissioning testing are dealt with, (3) Operating tests and conditions in which recurrent inspections, environmental protection during operation, investigation of abnormal occurences and backfitting requirements as reviewed, and (4) Safety philosophy and safety policy to conclude this presentation. The German approach to nuclear safety serves as an example for an effective way of assuring safe nuclear power. (orig.)

  2. LANSCE Beam Current Limiter (XL)

    International Nuclear Information System (INIS)

    Gallegos, F.R.; Hall, M.J.

    1997-01-01

    The Radiation Security System (RSS) at the Los Alamos Neutron Science Center (LANSCE) is an engineered safety system that provides personnel protection from prompt radiation due to accelerated proton beams. The Beam Current Limiter (XL), as an active component of the RSS, limits the maximum average current in a beamline, thus the current available for a beam spill accident. Exceeding the pre-set limit initiates action by the RSS to mitigate the hazard (insertion of beam stoppers in the low energy beam transport). The beam limiter is an electrically isolated, toroidal transformer and associated electronics. The device was designed to continuously monitor beamline currents independent of any external timing. Fail-safe operation was a prime consideration in its development. Fail-safe operation is defined as functioning as intended (due to redundant circuitry), functioning with a more sensitive fault threshold, or generating a fault condition. This report describes the design philosophy, hardware, implementation, operation, and limitations of the device

  3. Manpower development for safe operation of nuclear power plant. China. Emergency operating procedures. Activity: 5.1.4-Task-11. Technical report

    International Nuclear Information System (INIS)

    Walsh, L.A.

    1994-01-01

    This report covers the period of engagement from July 11, 1994 through July 22, 1994. The events and topics of discussion are as follows: History of Emergency Operating Procedure EOP Development; Emergency Operating Procedures (Event Based, Critical Safe Function Status Trees and Functional Recovery Response Procedures); Transition from Emergency Operating Procedures to Severe Accident Management Guidelines

  4. Planetary Boundaries: Exploring the Safe Operating Space for Humanity

    DEFF Research Database (Denmark)

    Richardson, Katherine; Rockström, Johan; Steffen, Will

    2009-01-01

    boundaries are rough, first estimates only, surrounded by large uncertainties and knowledge gaps. Filling these gaps will require major advancements in Earth System and resilience science. The proposed concept of "planetary boundaries" lays the groundwork for shifting our approach to governance...... and management, away from the essentially sectoral analyses of limits to growth aimed at minimizing negative externalities, toward the estimation of the safe space for human development. Planetary boundaries define, as it were, the boundaries of the "planetary playing field" for humanity if we want to be sure...

  5. Density limit in FTU tokamak during Ohmic operation

    International Nuclear Information System (INIS)

    Frigione, D.; Pieroni, L.

    1993-01-01

    The understanding of the physical mechanisms that regulate the density limit in a Tokamak is very important in view of a future fusion reactor. On one hand density enters as a factor in the figure of merit needed to achieve a burning plasma, and on the other hand a high edge density is a prerequisite for avoiding excessive erosion of the first walls and to limit the impurity influx into the hot plasma core. Furthermore a reactor should work in a safe zone of the operation parameters in order to avoid disruptive instabilities. The density limit problem has been tackled since the 70's, but so far a unique physics picture has not still emerged. In the last few years, due to the availability of better diagnostics, especially for the plasma edge, the use of pellet injectors to fuel the plasma and the experience gained on many different Tokamak, a consensus has been reached on the edge density as the real parameter responsible for the density limit. There are still two main mechanisms invoked to explain this limit: one refers to the power balance between the heat conducted and/or convected across the plasma radius and the power lost by impurity line radiation at the edge. When the latter overcomes the former, shrinking of the current channel occurs, which leads to instabilities due to tearing modes (usually the m/n=2/1) and then to disruption. The other explanation, for now valid for divertor machines, is based on the particle and energy balance in the scrape off layer (SOL). The limit in the edge density is then associated with the thermal collapse of the divertor plasma. In this work we describe the experiments on the density limit in FTU with Ohmic heating, the reason why we also believe that the limit is on the edge density, and discuss its relation to a simple model based on the SOL power balance valid for a limiter Tokamak. (author) 7 refs., 4 figs

  6. Unmanned Aerial Systems Traffic Management (UTM): Safely Enabling UAS Operations in Low-Altitude Airspace

    Science.gov (United States)

    Rios, Joseph

    2016-01-01

    Currently, there is no established infrastructure to enable and safely manage the widespread use of low-altitude airspace and UAS flight operations. Given this, and understanding that the FAA faces a mandate to modernize the present air traffic management system through computer automation and significantly reduce the number of air traffic controllers by FY 2020, the FAA maintains that a comprehensive, yet fully automated UAS traffic management (UTM) system for low-altitude airspace is needed. The concept of UTM is to begin by leveraging concepts from the system of roads, lanes, stop signs, rules and lights that govern vehicles on the ground today. Building on its legacy of work in air traffic management (ATM), NASA is working with industry to develop prototype technologies for a UAS Traffic Management (UTM) system that would evolve airspace integration procedures for enabling safe, efficient low-altitude flight operations that autonomously manage UAS operating in an approved low-altitude airspace environment. UTM is a cloud-based system that will autonomously manage all traffic at low altitudes to include UASs being operated beyond visual line of sight of an operator. UTM would thus enable safe and efficient flight operations by providing fully integrated traffic management services such as airspace design, corridors, dynamic geofencing, severe weather and wind avoidance, congestion management, terrain avoidance, route planning re-routing, separation management, sequencing spacing, and contingency management. UTM removes the need for human operators to continuously monitor aircraft operating in approved areas. NASA envisions concepts for two types of UTM systems. The first would be a small portable system, which could be moved between geographical areas in support of operations such as precision agriculture and public safety. The second would be a Persistent system, which would support low-altitude operations in an approved area by providing continuous automated

  7. Premiering SAFE for Safety Added Fuel Element - 15020

    International Nuclear Information System (INIS)

    Bhowmik, P.K.; Shamim, J.A.; Suh, K.Y.; Suh, K.S.

    2015-01-01

    The impact of the Fukushima accident has been the willingness to implement passive safety measures in reactor design and to simplify reactor design itself. Within this framework, a new fuel element, named SAFE (Safety Added Fuel Element) based on the concept of accident tolerant fuel, is presented. SAFE is a new type of fuel element cooled internally and externally by light water and with stainless steel as the cladding material. The removal of boron may trigger a series of changes which may simplify the system greatly. A simplified thermal analysis of SAFE shows that the fuel centerline temperature is well below the maximal limit during the normal operation of the plant

  8. Unmanned Aircraft Systems Traffic Management (UTM) Safely Enabling UAS Operations in Low-Altitude Airspace

    Science.gov (United States)

    Kopardekar, Parimal H.

    2016-01-01

    Unmanned Aircraft System (UAS) Traffic Management (UTM) Enabling Civilian Low-Altitude Airspace and Unmanned Aircraft System Operations What is the problem? Many beneficial civilian applications of UAS have been proposed, from goods delivery and infrastructure surveillance, to search and rescue, and agricultural monitoring. Currently, there is no established infrastructure to enable and safely manage the widespread use of low-altitude airspace and UAS operations, regardless of the type of UAS. A UAS traffic management (UTM) system for low-altitude airspace may be needed, perhaps leveraging concepts from the system of roads, lanes, stop signs, rules and lights that govern vehicles on the ground today, whether the vehicles are driven by humans or are automated. What system technologies is NASA exploring? Building on its legacy of work in air traffic management for crewed aircraft, NASA is researching prototype technologies for a UAS Traffic Management (UTM) system that could develop airspace integration requirements for enabling safe, efficient low-altitude operations. While incorporating lessons learned from the today's well-established air traffic management system, which was a response that grew out of a mid-air collision over the Grand Canyon in the early days of commercial aviation, the UTM system would enable safe and efficient low-altitude airspace operations by providing services such as airspace design, corridors, dynamic geofencing, severe weather and wind avoidance, congestion management, terrain avoidance, route planning and re-routing, separation management, sequencing and spacing, and contingency management. One of the attributes of the UTM system is that it would not require human operators to monitor every vehicle continuously. The system could provide to human managers the data to make strategic decisions related to initiation, continuation, and termination of airspace operations. This approach would ensure that only authenticated UAS could operate

  9. Application of digital solutions to help the safe and efficient operation of nuclear power plants

    International Nuclear Information System (INIS)

    Ortega P, F.; Fernandez F, S.

    2017-09-01

    In the search for excellence, the emergence of solutions to digitize nuclear power plants is an opportunity to optimize the operation and safety of them. The new technologies available today in the market, applied under a global vision of the operation, can contribute to the excellent operation of nuclear power plants in terms of efficiency and effectiveness. Tecnatom has a long experience in various areas related to the operation of the plants, giving the aforementioned global vision, essential to develop global solutions that pursue the safe and efficient operation of the operation. (Author)

  10. Ensuring safe operation at the Loviisa nuclear power plant

    International Nuclear Information System (INIS)

    Regnell, B.

    1985-01-01

    Safe operation of a nuclear plant can be achieved only if the plant is designed according to stringent safety principles, if the construction and commissioning work meets high standards and finally if proper attention is paid to the safety aspects in all operational activities. Clearly formulated safety principles and standards are required for all these steps. In the early phases of the Loviisa project only a few IAEA codes of practice and safety guides were available. Their usefulness was, however, felt early, and valuable guidance was offered by them in formulating the quality assurance programme, for example. The paper describes the approach taken in order to achieve high operational safety at the first nuclear power station in Finland, the Loviisa plant. The involvement in the project of the plant owner, Imatran Voima Oy (IVO), was very large, the company serving as its own architect-engineer. Experience has shown that the thorough knowledge of the plant, down to the finest details, obtained by extensive participation in design, erection and commissioning of the plant, is invaluable in the actual operation of the plant. This manifests itself most clearly in the event of malfunctions and incidents or if modifications have to be undertaken. Many different activities affecting the operational safety can be identified: actual operation of the plant, including the creation and maintaining of technical specifications, procedures, instructions, documentation systems, etc.; maintenance, repair and modification work; in-service inspection and testing practices; component failure data collection and analysis; incident reporting, collection and evaluation systems; operator training; quality assurance programme; procedures and implementation; reviews of operational safety by an independent safety committee; and supervision by the safety authorities. In the paper, all these activities are described in some detail. (author)

  11. Deep geological repositories. Safe operation and long-term safety in the prism of reversibility

    Energy Technology Data Exchange (ETDEWEB)

    Espivent, Camille; Tichauer, Michael [IRSN, Fontenay-aux-Roses (France)

    2015-07-01

    A deep geological repository is the reference solution enshrined in the French law for the long-term management of high-level radioactive waste. The current project is led by Andra, the French radioactive waste management organization. As a technical support organization, IRSN's mission is, on the basis of the safety case produced by Andra, to assess the safety of such a facility at its various stages of development, that is to say the design, construction, operation and post-closure phases of the facility. Such a facility will have to meet specific requirements, within different time frames as stated above. One of the requirements is ''reversibility'': in fact, French law poses that the geological disposal will have to be ''reversible'' for a certain time, yet not fully defined. Reversibility is nevertheless believed encompassing both the decision making process related to the waste emplacement process during operational phase and the ability to retrieve waste, should such a decision be made. Thus, underground structures have to be designed and operated to allow both waste emplacement and removal. Moreover, future decision making about the disposal process will have to rely on a sound technical basis. This implies a data collection scheme and a monitoring program of the facility to check if the disposal process is bound by limits, controls and conditions compatible with (i) a safe operation of the facility and (ii) the state of the facility that the operator wants to achieve at the time of its closure, so that long-term safety is guaranteed. Therefore, technical criteria and key parameters have to be selected and monitored during construction and operation, that is to say for decades. Then, reversibility have to make room for corrective actions, including the retrieval of waste, if something goes wrong and especially if the facility is not seen as safe anymore, especially in the perspective of long-term safety. To

  12. Deep geological repositories. Safe operation and long-term safety in the prism of reversibility

    International Nuclear Information System (INIS)

    Espivent, Camille; Tichauer, Michael

    2015-01-01

    A deep geological repository is the reference solution enshrined in the French law for the long-term management of high-level radioactive waste. The current project is led by Andra, the French radioactive waste management organization. As a technical support organization, IRSN's mission is, on the basis of the safety case produced by Andra, to assess the safety of such a facility at its various stages of development, that is to say the design, construction, operation and post-closure phases of the facility. Such a facility will have to meet specific requirements, within different time frames as stated above. One of the requirements is ''reversibility'': in fact, French law poses that the geological disposal will have to be ''reversible'' for a certain time, yet not fully defined. Reversibility is nevertheless believed encompassing both the decision making process related to the waste emplacement process during operational phase and the ability to retrieve waste, should such a decision be made. Thus, underground structures have to be designed and operated to allow both waste emplacement and removal. Moreover, future decision making about the disposal process will have to rely on a sound technical basis. This implies a data collection scheme and a monitoring program of the facility to check if the disposal process is bound by limits, controls and conditions compatible with (i) a safe operation of the facility and (ii) the state of the facility that the operator wants to achieve at the time of its closure, so that long-term safety is guaranteed. Therefore, technical criteria and key parameters have to be selected and monitored during construction and operation, that is to say for decades. Then, reversibility have to make room for corrective actions, including the retrieval of waste, if something goes wrong and especially if the facility is not seen as safe anymore, especially in the perspective of long-term safety. To

  13. Limited Blood Transfusions Are Safe in Orthopaedic Trauma Patients.

    Science.gov (United States)

    Dolenc, Andrea J; Morris, William Z; Como, John J; Wagner, Karl G; Vallier, Heather A

    2016-12-01

    Controversy exists over association of blood transfusions with complications. The purpose was to assess effects of limited transfusions on complication rates and hospital course. Level 1 trauma center. Three hundred seventy-one consecutive patients with Injury Severity Score ≥16 underwent fixation of fractures of spine (n = 111), pelvis (n = 72), acetabulum (n = 57), and/or femur (n = 179). Those receiving >3 units of packed red blood cell were excluded. Fracture type, associated injuries, treatment details, ventilation time, complications, and hospital stay were prospectively recorded. Ninety-eight patients with 107 fractures received limited transfusion, and 119 patients with 123 fractures were not transfused. The groups did not differ in age, fracture types, time to fixation, or associated injuries. Lowest hematocrit was lower in the transfused group (22.8 vs. 30.0, P < 0.0001). Surgical duration (3:23 vs. 2:28) and estimated blood loss (462 vs. 211 mL) were higher in transfused patients (all P < 0.003). Pulmonary complications occurred in 12% of transfused and 4% of nontransfused, (P = 0.10). Mean days of mechanical ventilation (2.51 vs. 0.45), intensive care unit days (4.5 vs. 1.5) and total hospital stay (8.8 vs. 5.7) were higher in transfused patients (all P ≤ 0.006). After multivariate analysis, limited transfusion was associated with increased hospital and intensive care unit stays and mechanical ventilation time, but not with complications. Patients receiving ≤3 units of packed red blood cell had lower hematocrit and greater surgical burden, but no difference in complications versus the nontransfused group. Limited blood transfusions are likely safe, excepting a possible association with longer mechanical ventilation times and hospital stays. Therapeutic level III. See Instructions for Authors for a complete description of levels of evidence.

  14. Main corrective measures in an early phase of nuclear power plants’ preparation for safe long term operation

    Energy Technology Data Exchange (ETDEWEB)

    Krivanek, Robert, E-mail: r.krivanek@iaea.org [International Atomic Energy Agency (IAEA), Department of Nuclear Safety and Security, Operational Safety Section, Vienna 1400 (Austria); Fiedler, Jan, E-mail: fiedler@fme.vutbr.cz [University of Technology Brno, Faculty of Mechanical Engineering, Energy Institute, Technická 2896/2, 616 69 Brno (Czech Republic)

    2017-05-15

    Highlights: • Results of SALTO missions provide the most important issues for safe long term operation (LTO) of nuclear power plants. • The most important technical corrective measures in an early phase of preparation for safe LTO are described. • Their satisfactory resolution creates a basis for further activities to demonstrate preparedness for safe LTO. - Abstract: This paper presents the analysis of main technical deficiencies of nuclear power plants (NPPs) in preparedness for safe long term operation (LTO) and the main corrective measures in an early phase of preparation for safe LTO of NPPs. It focuses on technical aspects connected with management of physical ageing of NPP structures, systems and components (SSCs). It uses as a basis results of IAEA SALTO missions performed between 2005 and 2016 (see also paper NED8805 in Nuclear Engineering and Design in May 2016) and the personal experiences of the authors with preparation of NPPs for safe LTO. This paper does not discuss other important aspects of safe LTO of NPPs, e.g. national nuclear energy policies, compliance of NPPs with the latest international requirements on design, obsolescence, environmental impact and economic aspects of LTO. Chapter 1 provides a brief introduction of the current status of the NPP’ fleet in connection with LTO. Chapter 2 provides an overview of SALTO peer review service results with a focus on deficiencies related to physical ageing of safety SSCs and a demonstration that SSCs will perform their safety function during the intended period of LTO. Chapter 3 discusses the main corrective measures which NPPs typically face during the preparation for demonstration of safe LTO. Chapter 4 summarizes the current status of the NPP’ fleet in connection with LTO and outlines further steps needed in preparation for safe LTO.

  15. Quasi-steady-state operation around operational limit in HT-7

    International Nuclear Information System (INIS)

    Li, J.; Xie, J.K.; Wan, B.N.; Luo, J.R.; Gao, X.; Zhao, Y.; Yang, Y.; Kuang, G.L.; Bao, Y.; Ding, B.J.; Wan, Y.X.

    2001-01-01

    Efforts have been made on HT-7 tokamak for extending the stable operation boundaries. Extensive RF boronization and siliconization have been used and wider operational Hugill diagram was obtained. Transit density reached 1.3 time of Greenwald density limit in ohmic discharges. Stationary high performance discharge with q a =2.1 has been obtained after siliconization. Confinement improvement was obtained due to the significant reduction of electron thermal diffusivity χ e in the out region of the plasma. Improved confinement phase was also observed by LHCD under the density range 70%∼120% of Greenwald density limit. The weak hollow current density profile was attribute to off-axis LHW power deposition. Code simulations and measurements showed a good agreement of off-axis LHW deposition. Supersonic molecular beam injection has been successfully used to get stable high-density operation in the range of Greenwald density limit. (author)

  16. Identification of efforts required for continued safe operation of KANUPP

    International Nuclear Information System (INIS)

    Ghafoor, M.A.; Hashmi, J.A.; Siddiqui, Z.H.

    1991-01-01

    Kanupp, the first commercial CANDU PHWR, rated at 137 MWe, was built on turnkey basis by the Canadian General Electric Company for the Pakistan Atomic Energy Commission, and went operational in October, 1972 near Karachi. It has operated since then with a lifetime average availability factor of 51.5% and capacity factor of 25%. In 1976, Kanupp suffered loss of technical support from its original vendors due to the Canadian embargo on export of nuclear technology. Simultaneously, the world experienced the most explosive development and advancement in electronic and computer technology, accelerating the obsolescence of such equipment and systems installed in Kanupp. Replacement upgrading of obsolete computers, control and instrumentation was thus the first major set of efforts realized as essential f or continued safe operation. On the other hand, Kanupp was able to cope with the normal maintenance of its process, mechanical and electrical equipment till the late 80's. But now many of these components are reaching the end of their useful life, and developing chronic problems due to ageing, which can only be solved by complete replacement. This is much more difficult for custom-made nuclear process equipment, e.g. the reactor internals and the fuelling machine. Public awareness and international concern about nuclear safety have increased significantly since the TMI and Chernobyl events. Corresponding realization of the critical role of human factors and the importance of operational experience feedback, has helped Kanupp by opening international channels of communication, including renewed cooperation on CANDU technology. The safety standards and criteria for CANDU as well as other NPPs have matured and evolved gradually over the past two decades. First Kanupp has to ensure that its present ageing-induced equipment problems are resolved to satisfy the original safety requirements and public risk targets which are still internationally acceptable. But as a policy, we

  17. Identification of efforts required for continued safe operation of KANUPP

    Energy Technology Data Exchange (ETDEWEB)

    Ghafoor, M A; Hashmi, J A; Siddiqui, Z H [Karachi Nuclear Power Plant, Karachi (Pakistan)

    1991-04-01

    Kanupp, the first commercial CANDU PHWR, rated at 137 MWe, was built on turnkey basis by the Canadian General Electric Company for the Pakistan Atomic Energy Commission, and went operational in October, 1972 near Karachi. It has operated since then with a lifetime average availability factor of 51.5% and capacity factor of 25%. In 1976, Kanupp suffered loss of technical support from its original vendors due to the Canadian embargo on export of nuclear technology. Simultaneously, the world experienced the most explosive development and advancement in electronic and computer technology, accelerating the obsolescence of such equipment and systems installed in Kanupp. Replacement upgrading of obsolete computers, control and instrumentation was thus the first major set of efforts realized as essential f or continued safe operation. On the other hand, Kanupp was able to cope with the normal maintenance of its process, mechanical and electrical equipment till the late 80's. But now many of these components are reaching the end of their useful life, and developing chronic problems due to ageing, which can only be solved by complete replacement. This is much more difficult for custom-made nuclear process equipment, e.g. the reactor internals and the fuelling machine. Public awareness and international concern about nuclear safety have increased significantly since the TMI and Chernobyl events. Corresponding realization of the critical role of human factors and the importance of operational experience feedback, has helped Kanupp by opening international channels of communication, including renewed cooperation on CANDU technology. The safety standards and criteria for CANDU as well as other NPPs have matured and evolved gradually over the past two decades. First Kanupp has to ensure that its present ageing-induced equipment problems are resolved to satisfy the original safety requirements and public risk targets which are still internationally acceptable. But as a policy, we

  18. Safely Enabling Civilian Unmanned Aerial System (UAS) Operations in Low-Altitude Airspace by Unmanned Aerial System Traffic Management (UTM)

    Science.gov (United States)

    Kopardekar, Parimal Hemchandra

    2015-01-01

    Many UAS will operate at lower altitude (Class G, below 2000 feet). There is an urgent need for a system for civilian low-altitude airspace and UAS operations. Stakeholders want to work with NASA to enable safe operations.

  19. 77 FR 46633 - Parts and Accessories Necessary for Safe Operation: Brakes; Adjustment Limits

    Science.gov (United States)

    2012-08-06

    ... the online instructions for submitting comments. Mail: Docket Management Facility: U.S. Department of... operational use * * * The Agency believes, however, that it is appropriate to require motor carriers to take... function of automatic slack adjusters, citing the National Transportation Safety Board's 2006 Safety...

  20. Integrated Life Cycle Management: A Strategy for Plants to Extend Operating Lifetimes Safely with High Operational Reliability

    International Nuclear Information System (INIS)

    Esselman, Thomas; Bruck, Paul; Mengers, Charles

    2012-01-01

    Nuclear plant operators are studying the possibility of extending their existing generating facilities operating lifetime to 60 years and beyond. Many nuclear plants have been granted licenses to operate their facilities beyond the original 40 year term; however, in order to optimize the long term operating strategies, plant decision-makers need a consistent approach to support their options. This paper proposes a standard methodology to support effective decision-making for the long-term management of selected station assets. Methods detailed are intended to be used by nuclear plant site management, equipment reliability personnel, long term planners, capital asset planners, license renewal staff, and others that intend to look at operation between the current time and the end of operation. This methodology, named Integrated Life Cycle Management (ILCM), will provide a technical basis to assist decision makers regarding the timing of large capital investments required to get to the end of operation safely and with high plant reliability. ILCM seeks to identify end of life cycle failure probabilities for individual plant large capital assets and attendant costs associated with their refurbishment or replacement. It will provide a standard basis for evaluation of replacement and refurbishment options for these components. ILCM will also develop methods to integrate the individual assets over the entire plant thus assisting nuclear plant decision-makers in their facility long term operating strategies. (author)

  1. Who's Got the Bridge? - Towards Safe, Robust Autonomous Operations at NASA Langley's Autonomy Incubator

    Science.gov (United States)

    Allen, B. Danette; Cross, Charles D.; Motter, Mark A.; Neilan, James H.; Qualls, Garry D.; Rothhaar, Paul M.; Tran, Loc; Trujillo, Anna C.; Crisp, Vicki K.

    2015-01-01

    NASA aeronautics research has made decades of contributions to aviation. Both aircraft and air traffic management (ATM) systems in use today contain NASA-developed and NASA sponsored technologies that improve safety and efficiency. Recent innovations in robotics and autonomy for automobiles and unmanned systems point to a future with increased personal mobility and access to transportation, including aviation. Automation and autonomous operations will transform the way we move people and goods. Achieving this mobility will require safe, robust, reliable operations for both the vehicle and the airspace and challenges to this inevitable future are being addressed now in government labs, universities, and industry. These challenges are the focus of NASA Langley Research Center's Autonomy Incubator whose R&D portfolio includes mission planning, trajectory and path planning, object detection and avoidance, object classification, sensor fusion, controls, machine learning, computer vision, human-machine teaming, geo-containment, open architecture design and development, as well as the test and evaluation environment that will be critical to prove system reliability and support certification. Safe autonomous operations will be enabled via onboard sensing and perception systems in both data-rich and data-deprived environments. Applied autonomy will enable safety, efficiency and unprecedented mobility as people and goods take to the skies tomorrow just as we do on the road today.

  2. 76 FR 54721 - Parts and Accessories Necessary for Safe Operation: Brakes; Adjustment Limits

    Science.gov (United States)

    2011-09-02

    ... operational use. Based on these fundamental performance characteristics of s-cam brakes, the August 2005 final... maintenance task (e.g., readjusting the brakes or replacing an inoperable slack adjuster) at the inspection..., slack adjusters, linings/pads, and drums/rotors. * * * * * (e) Clamp, Bendix DD-3, bolt-type, and...

  3. Conditions Of Safe Ship Operations And Sea Waterway Parameters Based On The Reconstruction Of Świnoujście-Szczecin Fairway

    Directory of Open Access Journals (Sweden)

    Gucma Stanisław

    2015-09-01

    Full Text Available This paper describes the state vector of safe ship operation on sea waterways. The author determines relationships between the state vector of safe ship operation and parameters of sea waterway system elements. These include three subsystems: area, navigation and traffic control. These relationships have been exemplified with the 68-kilometre Świnoujście-Szczecin fairway, presently under reconstruction. A systematic approach to sea waterway design is globally unique.

  4. Proceedings of the conference on the Safety in Reactor Operations - TopSafe 2012 Transactions

    International Nuclear Information System (INIS)

    2012-01-01

    TopSafe 2012 provides a forum for addressing the current status and future perspectives with regards to safety at nuclear installations worldwide. In view of the on-going discussions and initiatives that have been taken over the last months the European Nuclear Society (ENS) decided organising this edition of this topical conference from 22 to 26 April 2012 in Helsinki, Finland. TopSafe 2012 focus on three main subjects: Safety and related analyses in operating nuclear power plants and other nuclear installations; Safety and Risk Assessment; Trends in nuclear safety for existing and future installations. The conference is directed at a broad range of experts in the area of nuclear safety, including professionals from the different disciplines involved in the safety of nuclear power plants, fuel cycle installations and research reactors. It is aimed at professionals coming from the research organisations, universities, vendors, operators, regulatory bodies as well as policy makers. Top level representatives of the Countries that are constructing new nuclear power plants are invited. Regulators of all individual Countries with nuclear programme are expected to contribute the Conference. (authors)

  5. Selection of exception limits for all actinide nuclides based on revised criteria for safe international transport

    International Nuclear Information System (INIS)

    Lavarenne, C.; Rouyer, V.; Sert, G.; Mennerdahl, D.; Dean, C.; Barton, N.; Jean, F.

    2003-01-01

    Since 1998, there have been some speculations about future transport of significant quantities and concentrations of other actinide nuclides than the four currently listed in the regulation for the safe transport of the radioactive material. Therefore, it raised a need to specify exception limits for such actinides. Additionally, the total fissile nuclide mass per consignment of excepted packages was limited in the 1996 edition of the regulations (a conveyance limit is preliminary supported in the 2003 revision). The proposed changes of the rules have to take this new control into account. The European Community (DGTREN) decided to fund a project related to this subject. In order to define credible exception limits, it was necessary to have reasonably accurate data for all actinide nuclides. Then the authors of the study decided to perform calculations with different codes (MONK, MCNP, CRISTAL, SCALE) and different cross-section libraries (JEF2.2, ENDFB, JENDL, etc.). This article presents the work achieved and gives propositions of modification for the IAEA requirements for the Safe Transport of Radioactive Material related to, firstly, the list of the fissile materials, and secondly, the rule to determine the quantities of actinide nuclides that can be excepted from the requirements for the packages containing fissile materials. The participants acknowledge the DGTREN who made this work possible due to its support. (author)

  6. What influences youth to operate all-terrain vehicles safely?

    Science.gov (United States)

    Grummon, A. H.; Heaney, C. A.; Dellinger, W. A.; Wilkins, J. R.

    2014-01-01

    The operation of all-terrain vehicles (ATVs) by youth has contributed to the incidence of serious and fatal injuries among children. This study explored factors related to the frequency with which youth wore a helmet and refrained from engaging in three risky driving behaviors (driving at risky speeds, on paved roads and on unfamiliar terrain) while operating an ATV. Youth (n = 248) aged 9–14 from central Ohio and one of their parents completed self-report measures of ATV safety behaviors, youth general propensity for risk taking, protection motivation and parental behaviors to facilitate youth safety. Data from two focus groups provided insight on quantitative results. Analyses revealed considerable variation in the frequency with which youth performed the safety behaviors, with 13- and 14-year-olds reporting less frequent safe behavior than 9- to 12-year-olds. Multiple regression analyses suggested that parental behaviors, such as providing reminders to wear a helmet, were associated with more frequent helmet use but were not associated with risky driving behaviors. Youth’s general propensity toward risk taking was not associated with helmet use and only associated with riskydriving behaviors among the 13- and 14-year-olds. Self-efficacy was an important predictor across both age groups and behaviors. Implications for injury prevention are discussed. PMID:24740837

  7. Supplement to safety analysis report. 306-W building operations safety requirement

    International Nuclear Information System (INIS)

    Richey, C.R.

    1979-08-01

    The operations safety requirements (OSRs) presented in this report define the conditions, safe boundaries, and management control needed for safely conducting operations with radioactive materials in the Pacific Northwest Laboratory (PNL) 306-W building. The safety requirements are organized in five sections. Safety limits are safety-related process variables that are observable and measurable. Limiting conditions cover: equipment and technical conditions and characteristics of the facility and operations necessary for continued safe operation. Surveillance requirements prescribe the requirements for checking systems and components that are essential to safety. Equipment design controls require that changes to process equipment and systems be independently checked and approved to assure that the changes will have no adverse effect on safety. Administrative controls describe and discuss the organization and administrative systems and procedures to be used for safe operation of the facility. Details of the implementation of the operations safety requirements are prescribed by internal PNL documents such as criticality safety specifications and radiation work procedures

  8. Early detection of power system disturbances as a condition for safe operation of the Dukovany NPP in the 'Island operation mode'

    International Nuclear Information System (INIS)

    Petruzela, I.

    1997-01-01

    The ''Frequency Plan'' worked out for the Czech Power System specifies a set of preventive measures along with the set of the frequency ranges. This problem was solved in details for the Dukovany nuclear power plant. The design changes under preparation support a reliable as well as safe operation in the island-operation mode until a full restoration of the whole power system. The design modifications are based on the following three main innovations: An incorporation of the FREA 16 frequency relay into the protection circuits; large modifications in turbine control loops; installation of software routine for the operator to support the island operation mode. The capability of the island operation has been demanded by relevant regulations both for the operating units and for that under construction. The capability can be tested under the transition to houseloads, as well as through the direct simulation of abnormal grid conditions. 1 fig

  9. The Role of Well Control Training in Developing Safe Onshore and Offshore Oil Drilling Operations

    Science.gov (United States)

    Abulhassn, Aber

    2016-01-01

    This research investigates the role of the International Well Control Forum (IWCF) Rotary Drilling Well Control Training Program in developing safe oil drilling operations from the perspective of onshore and offshore drilling crews. The research methodology is a qualitative case study. A total of 40 IWCF candidates were interviewed, with 10 from…

  10. Safe Energy Source in Battery-operated Toys for Children.

    Science.gov (United States)

    Rossi, Alfredo; Vignola, Silvia; Nason, Francesca; Boschetti, Federica; Bramerio, Manuela; Bailini, Alessandro; Pinarello, Giordano

    2017-11-01

    Serious and even fatal consequences of disk batteries ingestion in children are well known. Among other applications, disk batteries are used to power small toys, from which they can be unexpectedly extracted and swallowed. We tested a new cell intended for little toys (green cell [GC]), after 6 and 12 hours of in vitro close contact with esophageal swine mucosa. The GC was compared with lithium and silver button batteries under the same experimental conditions. Tissues in contact with the GC did not show pH variations nor histological alterations after 6 and 12 hours. In such conditions, statistically significant differences were found between the GC and the lithium and silver batteries. So far, multidisciplinary medical effort has been driven to both emergency approach and subsequent operative strategies in children with ingested batteries. Our trial demonstrates the possibility to primarily prevent battery-induced damages by designing new-generation safe cells with no tissue toxicity to power little toys intended for children.

  11. Dynamic operator actions analysis for inherently safe fast reactors and light water reactors

    International Nuclear Information System (INIS)

    Ho, V.; Apostolakis, G.

    1988-01-01

    A comparative dynamic human actions analysis of inherently safe fast reactors (ISFRs) and light water reactors (LWRs) in terms of systems response and estimated human error rates is presented. Brief overviews of the ISFR and LWR systems are given to illustrate the design differences. Key operator actions required by the ISFR reactor shutdown and decay heat removal systems are identified and are compared with those of the LWR. It is observed that, because of the passive nature of the ISFR safety-related systems, a large time window is available for operator actions during transient events. Furthermore, these actions are fewer in number, are less complex, and have lower error rates and less severe consequences than those of the LWRs. We expect the ISFR operator errors' contribution to risk is smaller (at least in the context of the existing human reliability models) than that of the LWRs. (author)

  12. Conceptual design report for tank farm restoration and safe operations, project W-314

    Energy Technology Data Exchange (ETDEWEB)

    Briggs, S.R., Westinghouse Hanford

    1996-05-02

    This Conceptual Design Report (CDR) presents the conceptual level design approach that satisfies the established technical requirements for Project W-314, `Tank Farm Restoration and Safe Operations.` The CDR also addresses the initial cost and schedule baselines for performing the proposed Tank Farm infrastructure upgrades. The scope of this project includes capital improvements to Hanford`s existing tank farm facilities(primarily focused on Double- Shell Tank Farms) in the areas of instrumentation/control, tank ventilation, waste transfer, and electrical systems.

  13. Operational limits and conditions for nuclear power plants

    International Nuclear Information System (INIS)

    1979-01-01

    This Safety Guide was prepared as part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to nuclear power plants. It covers the concept of operational limits and conditions, their content as applicable to various types of thermal reactors, and the responsibilities of the operating organization regarding their establishment, modification, compliance and documentation. The principles of the operational limits and conditions are established in section 3 of the Agency's Code of Practice on Safety in Nuclear Power Plant Operation, including Commissioning and Decommissioning (IAEA Safety Series No. 50-C-O), which this present Safety Guide supplements. In order to present all pertinent information in this Guide, the provisions of section 3 of the Code are repeated

  14. Safe operation of existing radioactive waste management facilities at Dalat Nuclear Research Institute

    International Nuclear Information System (INIS)

    Pham Van Lam; Ong Van Ngoc; Nguyen Thi Nang

    2000-01-01

    The Dalat Nuclear Research Reactor was reconstructed from the former TRIGA MARK-II in 1982 and put into operation in March 1984. The combined technology for radioactive waste management was newly designed and put into operation in 1984. The system for radioactive waste management at the Dalat Nuclear Research Institute (DNRI) consists of radioactive liquid waste treatment station and disposal facilities. The treatment methods used for radioactive liquid waste are coagulation and precipitation, mechanical filtering and ion- exchange. Near-surface disposal of radioactive wastes is practiced at DNRI In the disposal facilities eight concrete pits are constructed for solidification and disposal of low level radioactive waste. Many types of waste generated in DNRI and in some Nuclear Medicine Departments in the South of Vietnam are stored in the disposal facilities. The solidification of sludge has been done by cementation. Hydraulic compactor has done volume reduction of compatible waste. This paper presents fifteen-years of safe operation of radioactive waste management facilities at DNRI. (author)

  15. Review of operational aids for nuclear plant operators

    International Nuclear Information System (INIS)

    Kisner, R.A.

    1983-01-01

    Many approaches are being explored to improve the safety of nuclear plant operations. One approach is to supply high-quality, relevant information by means of computer-based diagnostic systems to assist plant operators in performing their operational and safety-related roles. The evaluation of operational aids to ensure safe plant operations is a necessary function of NRC. This work has two purposes: to collect limited data on a diversity of operational aids, and to provide a method for evaluating the safety implications of the functions of proposed operational aids. After a discussion of the method evaluation now under study, this paper outlines this data collection to date

  16. 14 CFR 91.1055 - Pilot operating limitations and pairing requirement.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Pilot operating limitations and pairing... Ownership Operations Program Management § 91.1055 Pilot operating limitations and pairing requirement. (a... aircraft being flown, and the pilot in command is not an appropriately qualified check pilot, the pilot in...

  17. Proposal for a new normalization reference in LCA based on “safe operating space”: presentation of framework and global factors at midpoint level

    DEFF Research Database (Denmark)

    Bjørn, Anders; Hauschild, Michael Zwicky

    Planetary boundaries have been suggested for a range of environmental impacts,such as climate change, eutrophying nutrients and land use. The boundaries demarcate the safe operating space of humanity: Staying within the space ensures environmental sustainability, while exceeding it risks pushing...... ecosystems into alternative regimes, leading to adverse effects for humanity. Planetary boundaries can be applied as policy targets. To promote a societal development in the direction of these targets, an indicator system is needed that measures the fraction of the safe operating space that a given activity...... normalization factors in units compatible with characterized results at midpoint level in LCA. Our suggested framework allows expressing normalized results in units of “sustainable person years”. Normalization factors are derived by dividing the safe operating space by the global population. The proposed...

  18. How to operate safely steam generators with multiple tube through-wall defects

    International Nuclear Information System (INIS)

    Hernalsteen, P.

    1993-01-01

    For a Nuclear Power Plant (NPP) of the Pressurized Water Reactor (PWR) type, the Steam Generator (SG) tube bundle represents the major but also the thinnest part of the primary pressure boundary. To the extent that no tube material has yet been identified to be immune to corrosion, defects may initiate in service and easily propagate through wall. While not a desirable feature, a Through Wall Deep (TWD) defect does not necessarily pose a threat to either the structural integrity or leaktightness and this paper shows how SG can (and indeed, do) operate safely and reliably while having many tubes affected by deep and even TWD defects

  19. LANSCE beam current limiter

    International Nuclear Information System (INIS)

    Gallegos, F.R.

    1996-01-01

    The Radiation Security System (RSS) at the Los Alamos Neutron Science Center (LANSCE) provides personnel protection from prompt radiation due to accelerated beam. Active instrumentation, such as the Beam Current Limiter, is a component of the RSS. The current limiter is designed to limit the average current in a beam line below a specific level, thus minimizing the maximum current available for a beam spill accident. The beam current limiter is a self-contained, electrically isolated toroidal beam transformer which continuously monitors beam current. It is designed as fail-safe instrumentation. The design philosophy, hardware design, operation, and limitations of the device are described

  20. Test and evaluation plan for Project W-314 tank farm restoration and safe operations

    International Nuclear Information System (INIS)

    Hays, W.H.

    1998-01-01

    The ''Tank Farm Restoration and Safe Operations'' (TFRSO), Project W-314 will restore and/or upgrade existing Hanford Tank Farm facilities and systems to ensure that the Tank Farm infrastructure will be able to support near term TWRS Privatization's waste feed delivery and disposal system and continue safe management of tank waste. The capital improvements provided by this project will increase the margin of safety for Tank Farms operations, and will aid in aligning affected Tank Farm systems with compliance requirements from applicable state, Federal, and local regulations. Secondary benefits will be realized subsequent to project completion in the form of reduced equipment down-time, reduced health and safety risks to workers, reduced operating and maintenance costs, and minimization of radioactive and/or hazardous material releases to the environment. The original regulatory (e.g., Executive Orders, WACS, CFRS, permit requirements, required engineering standards, etc.) and institutional (e.g., DOE Orders, Hanford procedures, etc.) requirements for Project W-314 were extracted from the TWRS S/RIDs during the development of the Functions and Requirements (F and Rs). The entire family of requirements were then validated for TWRS and Project W-314. This information was contained in the RDD-100 database and used to establish the original CDR. The Project Hanford Management Contract (PHMC) team recognizes that safety, quality, and cost effectiveness in the Test and Evaluation (T and E) program is achieved through a planned systematic approach to T and E activities. It is to this end that the Test and Evaluation Plan (TEP) is created. The TEP for the TFRSO Project, was developed based on the guidance in HNF-IP-0842, and the Good Practice Guide GPG-FM-005, ''Test and Evaluation,'' which is derived from DOE Order 430.1, ''Life Cycle Asset Management.'' It describes the Test and Evaluation program for the TFRSO project starting with the definitive design phase and ending

  1. 46th Annual meeting on nuclear technology (AMNT 2015). Key topic / Enhanced safety and operation excellence / Sustainable reactor operation management - safe, efficient, valuable

    International Nuclear Information System (INIS)

    Fischer, Erwin

    2015-01-01

    Summary report on the following Topical Session of the 46 th Annual Conference on Nuclear Technology (AMNT 2015) held in Berlin, 5 to 7 May 2015: - Sustainable Reactor Operation Management - Safe, Efficient, Valuable (Erwin Fischer) The other Sessions of the Key Topics - ''Outstanding Know-How and Sustainable Innovations'', - ''Enhanced Safety and Operation Excellence'' and - ''Decommissioning Experience and Waste Management Solutions'' have been covered in atw 7 (2015) and will be covered in further issues of atw.

  2. [Prevention of adverse effects in latex allergic patients: organizing a latex safe operating theatre].

    Science.gov (United States)

    Bonalumi, Sabrina; Barbonaglia, Patrizia; Bertocchi, Carmen

    2006-01-01

    In 2001 the General Health Direction of Region Lombardia approved (decree n. 22303) a guideline for the prevention of latex allergic reactions in patients and health care workers. This document provides general recommendations in order to standardize behaviors in regional health care facilities. The reason is due to a rise in the incident of reactions to latex products in the last 20 years. Nowadays the prevalence is higher in certain risk groups (subjected to frequent and repeated exposures) rather than the general population. The aim of the project was to organize a latex safe operating theatre in the Ospedale Maggiore Policlinico, Mangiagalli e Regina Elena of Milan (Fondazione) and to standardize behaviors in order to prevent adverse effects in latex allergic patients. Thanks to the literature review and the creation of a multidisciplinar team, we produced a protocol. Therefore, we requested manufacturers the certification of the latex content of their products. Results and conclusion. When latex allergic patients need to undergone surgery in our hospital, a latex safe operating theatre is organized by personnel following a multidisciplinar protocol. No allergic reactions were experienced during surgical procedures after the creation of an environment as free as possible from latex contamination. The project will involve an emergency room, one room or more of a ward and of the outpatients department.

  3. VISIR: technological infrastructure of an operational service for safe and efficient navigation in the Mediterranean Sea

    Science.gov (United States)

    Mannarini, Gianandrea; Turrisi, Giuseppe; D'Anca, Alessandro; Scalas, Mario; Pinardi, Nadia; Coppini, Giovanni; Palermo, Francesco; Carluccio, Ivano; Scuro, Matteo; Cretì, Sergio; Lecci, Rita; Nassisi, Paola; Tedesco, Luca

    2016-08-01

    VISIR (discoVerIng Safe and effIcient Routes) is an operational decision support system (DSS) for optimal ship routing designed and implemented in the frame of the TESSA (TEchnology for Situational Sea Awareness) project. The system is aimed to increase safety and efficiency of navigation through the use of forecast environmental fields and route optimization. VISIR can be accessed through a web interface (www.visir-nav.com) and mobile applications for both iOS and Android devices. This paper focuses on the technological infrastructure developed for operating VISIR as a DSS. Its main components are described, the performance of the operational system is assessed through experimental measurements, and a few case studies are presented.

  4. 76 FR 42534 - Mandatory Reliability Standards for Interconnection Reliability Operating Limits; System...

    Science.gov (United States)

    2011-07-19

    ... Reliability Operating Limits; System Restoration Reliability Standards AGENCY: Federal Energy Regulatory... data necessary to analyze and monitor Interconnection Reliability Operating Limits (IROL) within its... Interconnection Reliability Operating Limits, Order No. 748, 134 FERC ] 61,213 (2011). \\2\\ The term ``Wide-Area...

  5. 14 CFR 135.397 - Small transport category airplane performance operating limitations.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Small transport category airplane... PERSONS ON BOARD SUCH AIRCRAFT Airplane Performance Operating Limitations § 135.397 Small transport category airplane performance operating limitations. (a) No person may operate a reciprocating engine...

  6. Denying Sanctuary: Rejecting Safe Havens in Counterinsurgency Operations

    National Research Council Canada - National Science Library

    Monarch, Robert M

    2009-01-01

    Physical sanctuary is one of the bedrocks of a successful insurgency. Denial of these safe havens is critical to a successful counterinsurgency campaign and the eventual defeat of the insurgents by the host state...

  7. 14 CFR 135.399 - Small nontransport category airplane performance operating limitations.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Small nontransport category airplane... PERSONS ON BOARD SUCH AIRCRAFT Airplane Performance Operating Limitations § 135.399 Small nontransport category airplane performance operating limitations. (a) No person may operate a reciprocating engine or...

  8. Changing nuclear plant operating limits during startup and shutdown

    International Nuclear Information System (INIS)

    Arnold, E.C.; Carlson, R.W.; Ray, N.K.; Roarty, D.H.

    1990-01-01

    During startup and shutdown operation of pressurized water reactor (PWR) nuclear power plants, a low pressure decay heat removal system is used to maintain core cooling. During these phases of operation, there are numerous operating practices and design limits to meet special and sometimes conflicting requirements unique to these operations. This paper evaluates the impact and interdependencies of recent issues on plant operation and design

  9. Risk based limits for Operational Safety Requirements

    International Nuclear Information System (INIS)

    Cappucci, A.J. Jr.

    1993-01-01

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

  10. The Safe Zone Range for Cup Anteversion Is Narrower Than for Inclination in THA.

    Science.gov (United States)

    Murphy, William S; Yun, Ho Hyun; Hayden, Brett; Kowal, Jens H; Murphy, Stephen B

    2018-02-01

    Cup malposition is a common cause of impingement, limitation of ROM, acceleration of bearing wear, liner fracture, and instability in THA. Previous studies of the safe zone based on plain radiographs have limitations inherent to measuring angles from two-dimensional projections. The current study uses CT to measure component position in stable and unstable hips to assess the presence of a safe zone for cup position in THA. (1) Does acetabular component orientation, when measured on CT, differ in stable components and those revised for recurrent instability? (2) Do CT data support historic safe zone definitions for component orientation in THA? We identified 34 hips that had undergone revision of the acetabulum for recurrent instability that also had a CT scan of the pelvis between August 2003 and February 2017. We also identified 175 patients with stable hip replacements who also had a CT study for preoperative planning and intraoperative navigation of the contralateral side. For each CT study, one observer analyzed major factors including acetabular orientation, femoral anteversion, combined anteversion (the sum of femoral and anatomic anteversion), pelvic tilt, total offset difference, head diameter, age, sex, and body mass index. These measures were then compared among stable hips, hips with cup revision for anterior instability, and hips with cup revision for posterior instability. We used a clinically relevant measurement of operative anteversion and inclination as opposed to the historic use of radiographic anteversion and inclination. The percentage of unstable hips in the historic Lewinnek safe zone was calculated, and a new safe zone was proposed based on an area with no unstable hips. Anteriorly unstable hips compared with stable hips had higher operative anteversion of the cup (44° ± 12° versus 31° ± 11°, respectively; mean difference, 13°; 95% confidence interval [CI], 5°-21°; p = 0.003), tilt-adjusted operative anteversion of the cup (40°

  11. 46{sup th} Annual meeting on nuclear technology (AMNT 2015). Key topic / Enhanced safety and operation excellence / Sustainable reactor operation management - safe, efficient, valuable

    Energy Technology Data Exchange (ETDEWEB)

    Fischer, Erwin [E.ON Kernkraft GmbH, Global Unit Next Generation, Hannover (Germany)

    2015-08-15

    Summary report on the following Topical Session of the 46{sup th} Annual Conference on Nuclear Technology (AMNT 2015) held in Berlin, 5 to 7 May 2015: - Sustainable Reactor Operation Management - Safe, Efficient, Valuable (Erwin Fischer) The other Sessions of the Key Topics - ''Outstanding Know-How and Sustainable Innovations'', - ''Enhanced Safety and Operation Excellence'' and - ''Decommissioning Experience and Waste Management Solutions'' have been covered in atw 7 (2015) and will be covered in further issues of atw.

  12. Dukovany NPP - Safely 16 TERA

    International Nuclear Information System (INIS)

    Vlcek, J.

    2008-01-01

    In this presentation increasing of power output of the Dukovany NPP is reviewed. To operate all Dukovany Units safely with the perspective of long-term operation (LTO) of 50 - 60 years it is proposed.

  13. Managing Cassini Safe Mode Attitude at Saturn

    Science.gov (United States)

    Burk, Thomas A.

    2010-01-01

    The Cassini spacecraft was launched on October 15, 1997 and arrived at Saturn on June 30, 2004. It has performed detailed observations and remote sensing of Saturn, its rings, and its satellites since that time. In the event safe mode interrupts normal orbital operations, Cassini has flight software fault protection algorithms to detect, isolate, and recover to a thermally safe and commandable attitude and then wait for further instructions from the ground. But the Saturn environment is complex, and safety hazards change depending on where Cassini is in its orbital trajectory around Saturn. Selecting an appropriate safe mode attitude that insures safe operation in the Saturn environment, including keeping the star tracker field of view clear of bright bodies, while maintaining a quiescent, commandable attitude, is a significant challenge. This paper discusses the Cassini safe table management strategy and the key criteria that must be considered, especially during low altitude flybys of Titan, in deciding what spacecraft attitude should be used in the event of safe mode.

  14. Limitations of the inspection and testing concepts for pressurised components from the viewpoint of operating experience

    International Nuclear Information System (INIS)

    Schulz, H.

    2001-01-01

    The role of in-service inspection and testing is to contribute to a safe and reliable operation of systems, structures and components. It is therefore the objective of inspections and tests to identify malfunctions and degradations at a stage early enough to avoid detrimental impacts on safety as well as on the reliability of the plant. Taking mostly the pressure boundary of German light-water reactors as an example, it is the intention of this paper to analyse how successful present inspection and testing requirements are and to discuss limitations. Based on a review of the world-wide operating experience the following questions of a more generic nature are addressed: - Are the relevant damage mechanisms being addressed in our codes and standards? - What are the criteria to develop a representative scope of inspection? - How to maintain a sufficient level of information for a decreasing number of nuclear power plants in operation? It can be concluded that the revision of codes and standards according to lessons learned from operating experience remains as an ongoing process. Furthermore, the criteria applied to derive a representative scope of inspection need to be addressed in more detail, specifically with respect to corrosion. The continuous evaluation of operating experience of a large number of plants is the most valuable source to identify beginning degradations. (author)

  15. 46 CFR 180.205 - Survival craft-vessels operating on limited coastwise routes.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Survival craft-vessels operating on limited coastwise... Craft § 180.205 Survival craft—vessels operating on limited coastwise routes. (a) Except as allowed by... survival craft required by § 180.204(d). (e) Each vessel certificated to operate on a limited coastwise...

  16. International conference on safe decommissioning for nuclear activities: Assuring the safe termination of practices involving radioactive materials. Contributed papers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    Thousands of operations involving the use of radioactive substances will end during the current century. While there is considerable regulatory experience in the 'front end' of the regulatory system for practices, the experience at the back end is more limited as fewer practices have actually been terminated. When a practice is terminated because the facility has reached the end of its useful life, action has to betaken to ensure the safe shutdown of the facility and allow the removal of regulatory controls. There are many issues involved in the safe termination of practices. These include setting criteria for the release of material and sites from regulatory control; determining the suitability of the various options for decommissioning nuclear facilities, managing the waste and material released from control (recycling, reuse or disposal), and the eventual remediation of the site. Some countries have put in place regulatory infrastructures and have developed programmes to manage the associated decommissioning and remediation activities. Other countries are at the stage of assessing what is involved in terminating such practices. The purpose of this Conference is to foster an information exchange on the safe an orderly termination of practices that involve the use of radioactive substances, including both decommissioning and environmental remediation, and to promote improved coherence internationally on strategies and criteria for the safe termination of practices.

  17. International conference on safe decommissioning for nuclear activities: Assuring the safe termination of practices involving radioactive materials. Contributed papers

    International Nuclear Information System (INIS)

    2002-01-01

    Thousands of operations involving the use of radioactive substances will end during the current century. While there is considerable regulatory experience in the 'front end' of the regulatory system for practices, the experience at the back end is more limited as fewer practices have actually been terminated. When a practice is terminated because the facility has reached the end of its useful life, action has to betaken to ensure the safe shutdown of the facility and allow the removal of regulatory controls. There are many issues involved in the safe termination of practices. These include setting criteria for the release of material and sites from regulatory control; determining the suitability of the various options for decommissioning nuclear facilities, managing the waste and material released from control (recycling, reuse or disposal), and the eventual remediation of the site. Some countries have put in place regulatory infrastructures and have developed programmes to manage the associated decommissioning and remediation activities. Other countries are at the stage of assessing what is involved in terminating such practices. The purpose of this Conference is to foster an information exchange on the safe an orderly termination of practices that involve the use of radioactive substances, including both decommissioning and environmental remediation, and to promote improved coherence internationally on strategies and criteria for the safe termination of practices

  18. Water chemistry technology. One of the key technologies for safe and reliable nuclear power plant operation

    International Nuclear Information System (INIS)

    Uchida, Shunsuke; Katsumura, Yosuke

    2013-01-01

    Water chemistry control is one of the key technologies to establish safe and reliable operation of nuclear power plants. Continuous and collaborative efforts of plant manufacturers and plant operator utilities have been focused on optimal water chemistry control, for which, a trio of requirements for water chemistry should be simultaneously satisfied: (1) better reliability of reactor structures and fuel rods; (2) lower occupational exposure and (3) fewer radwaste sources. Various groups in academia have carried out basic research to support the technical bases of water chemistry in plants. The Research Committee on Water Chemistry of the Atomic Energy Society of Japan (AESJ), which has now been reorganized as the Division of Water Chemistry (DWC) of AESJ, has played important roles to promote improvements in water chemistry control, to share knowledge about and experiences with water chemistry control among plant operators and manufacturers and to establish common technological bases for plant water chemistry and then to transfer them to the next generation of plant workers engaged in water chemistry. Furthermore, the DWC has tried and succeeded arranging R and D proposals for further improvement in water chemistry control through roadmap planning. In the paper, major achievements in plant technologies and in basic research studies of water chemistry in Japan are reviewed. The contributions of the DWC to the long-term safe management of the damaged reactors at the Fukushima Daiichi Nuclear Power Plant until their decommissioning are introduced. (author)

  19. Beznau II nuclear power plant: Expertise on NOK's request for the removal of the time limitation for the operation licence

    International Nuclear Information System (INIS)

    2004-03-01

    The Federal Agency for the Safety of Nuclear Installations (HSK) is the Swiss authority responsible for nuclear safety and protection against radioactivity in nuclear power plants. It has to examine the request of the North-East Swiss Power Corporation (NOK) concerning the removal of the operational time limitation for the Beznau-II reactor (KKB-II). In the present report HSK reviews the enterprise management and the safety of KKB-II on the basis of the results of the Periodic Safety Review. The Beznau nuclear power plant exhibits a very high degree of technical and organisational safety. During the past 10 years the plant has been operated in a safe manner. At the same time the plant has been improved and this guarantees that the mechanisms of ageing degradation are systematically identified and that measures can be taken that are possibly necessary. Under such conditions, the safety of KKB-II can be guarantied at all times. As a result of the management of quality, environmental and working safety conditions, the correct application and the continuous improvement of all processes important to safety are ensured. With these measures KKB has shown that safety is given priority over and against all other working goals. The examination by HSK of the Periodic Safety Review has shown that, in the past, KKB has applied modernisation measures independent of the licensing situation of the two reactor blocks. These modernisation measures largely contribute to the fact that the HSK examination did not reveal any significant safety deficiencies. Other improvement measures allow risk reduction or can bee seen as an adaptation to experience gained and to the state of the technological art. In conclusion, HSK states that no safety-relevant facts have been found which could prevent the removal of the time limitation on the operational licence for KKB-II. From the point of view of HSK, KKB-II fulfils the conditions for the safe continuation of operation

  20. 49 CFR 213.307 - Class of track: operating speed limits.

    Science.gov (United States)

    2010-10-01

    ... requirements for its intended class, it is to be reclassified to the next lower class of track for which it... 49 Transportation 4 2010-10-01 2010-10-01 false Class of track: operating speed limits. 213.307... Higher § 213.307 Class of track: operating speed limits. (a) Except as provided in paragraph (b) of this...

  1. 40 CFR 63.7323 - What procedures must I use to establish operating limits?

    Science.gov (United States)

    2010-07-01

    ... use to establish operating limits? (a) For a venturi scrubber applied to pushing emissions from a coke oven battery, you must establish site-specific operating limits for pressure drop and scrubber water... that meet the emission limit. (e) You may change the operating limit for a venturi scrubber, capture...

  2. 78 FR 47817 - Parts and Accessories Necessary for Safe Operation; Application for an Exemption From Van Hool N...

    Science.gov (United States)

    2013-08-06

    ... DEPARTMENT OF TRANSPORTATION Federal Motor Carrier Safety Administration [Docket No. FMCSA-2013-0314] Parts and Accessories Necessary for Safe Operation; Application for an Exemption From Van Hool N... exemption from Van Hool N.V. and Coach USA (Van Hool/Coach USA) to allow the use of double deck motorcoaches...

  3. Review of Issues Associated with Safe Operation and Management of the Space Shuttle Program

    Science.gov (United States)

    Johnstone, Paul M.; Blomberg, Richard D.; Gleghorn, George J.; Krone, Norris J.; Voltz, Richard A.; Dunn, Robert F.; Donlan, Charles J.; Kauderer, Bernard M.; Brill, Yvonne C.; Englar, Kenneth G.; hide

    1996-01-01

    At the request of the President of the United States through the Office of Science and Technology Policy (OSTP), the NASA Administrator tasked the Aerospace Safety Advisory Panel with the responsibility to identify and review issues associated with the safe operation and management of the Space Shuttle program arising from ongoing efforts to improve and streamline operations. These efforts include the consolidation of operations under a single Space Flight Operations Contract (SFOC), downsizing the Space Shuttle workforce and reducing costs of operations and management. The Panel formed five teams to address the potentially significant safety impacts of the seven specific topic areas listed in the study Terms of Reference. These areas were (in the order in which they are presented in this report): Maintenance of independent safety oversight; implementation plan for the transition of Shuttle program management to the Lead Center; communications among NASA Centers and Headquarters; transition plan for downsizing to anticipated workforce levels; implementation of a phased transition to a prime contractor for operations; Shuttle flight rate for Space Station assembly; and planned safety and performance upgrades for Space Station assembly. The study teams collected information through briefings, interviews, telephone conversations and from reviewing applicable documentation. These inputs were distilled by each team into observations and recommendations which were then reviewed by the entire Panel.

  4. A Short-Circuit Safe Operation Area Identification Criterion for SiC MOSFET Power Modules

    DEFF Research Database (Denmark)

    Reigosa, Paula Diaz; Iannuzzo, Francesco; Luo, Haoze

    2017-01-01

    This paper proposes a new method for the investigation of the short-circuit safe operation area (SCSOA) of state-of-the-art SiC MOSFET power modules rated at 1.2 kV based on the variations in SiC MOSFET electrical parameters (e.g., short-circuit current and gate–source voltage). According...... to the experimental results, two different failure mechanisms have been identified, both reducing the short-circuit capability of SiC power modules with respect to discrete SiC devices. Based on such failure mechanisms, two short-circuit safety criteria have been formulated: 1) the short-circuit...

  5. Safe handling of TBP and nitrates in the nuclear process industry

    International Nuclear Information System (INIS)

    Hyder, M.L.

    1994-07-01

    A laboratory and literature study was made of the reactions of tri-n-butyl phosphate (TBP) with nitric acid and nitrates. Its goal was to establish safe conditions for solvent extraction processes involving these chemicals. The damaging explosions at the Tomsk-7 PUREX plant in Russia graphically illustrated the potential hazard involved in such operations. The study has involved a review of prior and contemporary experiments, and new experiments to answer particular questions about these reactions. TBP extracts nitric acid and some metal nitrates from aqueous solutions. The resulting liquid contains both oxidant and reductant, and can react exothermically if heated sufficiently. Safe handling of these potentially reactive materials involves not only limiting the heat generated by the chemical reaction, but also providing adequate heat removal and venting. Specifically, the following recommendations are made to ensure safety: (1) tanks in which TBP-nitrate complexes are or may be present should be adequately vented to avoid pressurization. Data are supplied as a basis for adequacy; (2) chemically degraded TBP, or TBP that has sat a long time in the presence of acids or radiation, should be purified before use in solvent extraction; (3) evaporators in which TBP might be introduced should be operated at a controlled temperature, and their TBP content should be limited; (4) evaporator bottoms that may contain TBP should be cooled under conditions that ensure heat removal. Finally, process design should consider the potential for such reactions, and operators should be made aware of this potential, so that it is considered during training and process operation

  6. Safe and economic performance of nuclear power plant. Operation through meticulous Q/A programmes - a german example

    International Nuclear Information System (INIS)

    Schenk, H.J.

    1989-01-01

    Safe and reliable operation of a nuclear power plant over its life time of 40 to 60 years is the essential condition for an economic performance. This goal can be achieved by a qualified responsible staff realizing a high quality of operation and by maintaining high quality and technical standards in the plant in accordance with the status of science and technology. Quality assurance procedures have to verify this in detail, in close contact with the work to be performed. In this presentation I would like to describe our approach in Philippsburg to cope with this task

  7. Water chemistry - one of the key technologies for safe and reliable nuclear power plant operation

    International Nuclear Information System (INIS)

    Uchida, S.; Otoha, K.; Ishigure, K.

    2006-01-01

    Full text: Full text: Water chemistry control is one of the key technologies to establish safe and reliable operation of nuclear power plants. Continuous and collaborative efforts of plant manufacturers and plant operator utilities have been focused on optimal water chemistry control, for which, a trio of requirements for water chemistry, a) better reliability of reactor structures and fuels, b) lower occupational exposure, and c) fewer radwaste sources, should be simultaneously satisfied. The research committee related to water chemistry of the Atomic Energy Society of Japan has played important roles to enhance improvement in water chemistry control, to share knowledge and experience with water chemistry among plant operators and manufacturers, to establish common technological bases for plant water chemistry and then to transfer them to the next generation related to water chemistry. Furthermore, the committee has tried to contribute to arranging R and D proposals for further improvement in water chemistry control through road map planning

  8. Limits and conditions for permanent operation of the LVR-15 reactor

    International Nuclear Information System (INIS)

    1995-03-01

    The ''Limits and Conditions'' have been set up to demonstrate compliance with all nuclear safety requirements specified by the Decree of the Czechoslovak Atomic Energy Commission No. 9/1985, and to serve as a guide for the reactor operators to respond adequately to deviations from the required values in normal operation conditions. The publications is divided into the following chapters: (1) Safety limits of the LVR-15 reactor; (2) Adjusting the reactor protection and control system parameters; (3) Limiting conditions for normal operation modes; (4) Control requirements; and (5) reactor operation management. A document by the Institute for Research, Production, and Application of Radioisotopes specifying conditions for the acceptance of radioactive wastes to the central repository is appended. (P.A.). 7 tabs

  9. Exploratory system dynamics : A directed search for limits to global water use

    NARCIS (Netherlands)

    Kwakkel, J.H.; Timmermans, J.S.

    2012-01-01

    Rockström et al. (2009) introduced the concept of a safe operating space for humanity that will not push the planet out of the ‘Holocene state’. These limits are being investigated for various earth bound systems. Estimates of these limits are plagued by uncertainty. In case of the limits to the

  10. Design, qualification and operation of nuclear rockets for safe Mars missions

    International Nuclear Information System (INIS)

    Buden, D.; Madsen, W.W.; Olson, T.S.; Redd, L.R.

    1993-01-01

    Nuclear thermal propulsion modules planned for use on crew missions to Mars improve mission reliability and overall safety of the mission. This, as well as all other systems, are greatly enhanced if the system specifications take into account safety from design initiation, and operational considerations are well thought through and applied. For instance, the use of multiple engines in the propulsion module can lead to very high system safety and reliability. Operational safety enhancements may include: the use of multiple perigee burns, thus allowing time to ensure that all systems are functioning properly prior to departure from Earth orbit; the ability to perform all other parts of the mission in a degraded mode with little or no degradation of the mission; and the safe disposal of the nuclear propulsion module in a heliocentric orbit out of the ecliptic plane. The standards used to qualify nuclear rockets are one of the main cost drivers of the program. Concepts and systems that minimize cost and risk will rely on use of the element and component levels to demonstrate technology readiness and validation. Subsystem or systems testing then is only needed for verification of performance. Also, these will be the safest concepts because they will be more thoroughly understood and the safety margins will be well established and confirmed by tests

  11. A study on the Safe Operation of RHRS during Shut-Down and Low Power Operations of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Jeon, Moon Hun; Sung, Chang Kyung; Kim, Yang Suk; You, Sun Oh; Joo, In Chul [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

    1996-08-01

    The main objective is to perform basic research for safe operation of RHRs, which is an important part in the safety analysis of nuclear reactors during a mid-loop operation of nuclear power plants. To achieve this objective, a series of experiments have been performed to simulate the wave phenomena of countercurrent flow that may occur in the hot legs during a mid-loop operation. The major contents and the scope are as follows, To collect and to analyse existing experimental works and also numerical works which have been carried out using large computer codes. To collect and to analyse existing works on the flow patterns of two-phase flows. To perform a series of experiments to simulate the wave phenomena for the countercurrent two-phase flow in hot legs. To obtain correlations for the interfacial friction factor and the flow patterns for a countercurrent flow from the experimentally measured parameters. To obtain the interfacial friction factor between the two-phases of air-water countercurrent flow in a horizontal pipe, a series of experiments have been performed using two different sections of 0.05 m in diameter, whose lengths are 2 m and 4 m, respectively. The results presented here can be used as the fundamental information to obtain the most important thermal-hydraulic parameters such as flow patterns and interfacial friction factors for air-water two-phase flows, which are necessary for safety analyses and operation of nuclear power plants during a mid-loop operation. 46 refs., 8 tabs., 35 figs., 3 ills. (author)

  12. VISIR: technological infrastructure of an operational service for safe and efficient navigation in the Mediterranean Sea

    OpenAIRE

    G. Mannarini; G. Turrisi; A. D'Anca; M. Scalas; N. Pinardi; G. Coppini; F. Palermo; I. Carluccio; M. Scuro; S. Cretì; R. Lecci; P. Nassisi; L. Tedesco

    2016-01-01

    VISIR (discoVerIng Safe and effIcient Routes) is an operational decision support system (DSS) for optimal ship routing designed and implemented in the frame of the TESSA (TEchnology for Situational Sea Awareness) project. The system is aimed to increase safety and efficiency of navigation through the use of forecast environmental fields and route optimization. VISIR can be accessed through a web interface (www.visir-nav.com) and mobile applications for both iOS and Androi...

  13. Limiting the liability of the nuclear operator

    International Nuclear Information System (INIS)

    Reyners, P.

    1986-01-01

    This article discusses the questioning of a fundamental principle of the special nuclear third party liability regime by certain NEA countries: the limitation of the nuclear operator's liability. This regime, set up since the late fifties at European then at worldwide level, had until now been widely adopted in the national legislation of most of the countries with a nuclear power programme. The author analyses the different arguments in favour of restoring unlimited liability for the nuclear operator and attempts to define its implications for the future of the nuclear third party liability regime in NEA countries. (NEA) [fr

  14. Technical innovations at NPP Dukovany - for safe and efficient operation

    International Nuclear Information System (INIS)

    Sabata, M.; Vasa, I.

    2000-01-01

    Inherent features of the NPP Dukovany design provide a significant confidence in its nuclear safety assurance; among these features should be emphasised the reactor core stability and its control and protection system capability to hold the reactor in safe state following scram or accident conditions. Nevertheless, NPP Dukovany was designed in the early seventies, and current requirements for nuclear safety assurance are more strict and/or specific as a result of the technical development and lessons learned from nuclear accidents. The paper compares the safety design base established at the time of NPP Dukovany project implementation and the current reference design base. The paper also presents procedures applied to implement technical and operational measures which are introduced to fulfil the current basic safety criteria. The scope of such measures applied at NPP Dukovany is compared with that of EU countries introduced for the same reason - to meet the updated safety related requirements. Examples of some innovations already implemented or under implementation give an idea how NPP Dukovany proceeds in reaching the goal of harmonising its safety with the requirements to be met before the Czech Republic becomes a member country of the European Union. (author)

  15. Safety aspects of long term operation of water moderated reactors. Recommendations on the scope and content of programmes for safe long term operation. Final report of the extrabudgetary programme on safety aspects long term operation of water moderated reactors

    International Nuclear Information System (INIS)

    2007-07-01

    During the last two decades, the number of IAEA Member States giving high priority to continuing the operation of nuclear power plants beyond the time frame originally anticipated is increasing. This is related to the age of nuclear power plants connected to the grid worldwide. The IAEA started to develop guidance on the safety aspects of ageing management in the 1990s. Recognizing the development in a number of its Member States, the IAEA initiated this Extrabudgetary Programme on Safety Aspects of Long Term Operation of Water Moderated Reactors in 2003. The objective of the Programme was to establish recommendations on the scope and content of activities to ensure safe long term operation of water moderated reactors. The term long term operation is used to accommodate various approaches in Member States and is defined as operation beyond an initial time frame set forth in design, standards, licence, and/or regulations, that is justified by safety assessment, considering life limiting processes and features for systems, structures and components. The scope of the Programme included general long term operation framework, mechanical components and materials, electrical components and instrumentation and control, and structural components and structures. The scope of the Programme was limited to physical structures of the NPPs. Four working groups addressed the above indicated technical areas. The Programme steering committee provided coordination and guidance and served as a forum for the exchange of information. The Programme implementation relied on voluntary in kind and financial contributions from the Czech Republic, Hungary, Slovakia, Sweden, the United Kingdom and the USA as well as in kind contributions from Bulgaria, Finland, the Netherlands, the Russian Federation, Spain, the Ukraine, and the European Commission. This report summarizes the main results, conclusions and recommendations of this Programme and provides in the Appendices I-IV detailed

  16. Operational support of a safe operating envelope for fuel

    International Nuclear Information System (INIS)

    Chapman, T.J.; Gibb, R.A.

    1998-01-01

    The mandate of a station safety analysis group is to ensure that the station is operated and maintained in a manner consistent with the basis for our understanding of the safety consequences of process or human failures. As operating experience has developed an awareness of the significance of fuel manufacture and operating conditions on safety consequences has also grown. This awareness has led to a program that is designed to ensure that these influences are appropriately considered. This paper describes the projects that make up this program. (author)

  17. Modified hydraulic braking system limits angular deceleration to safe values

    Science.gov (United States)

    Briggs, R. S.; Council, M.; Green, P. M.

    1966-01-01

    Conventional spring actuated, hydraulically released, fail-safe disk braking system is modified to control the angular deceleration of a massive antenna. The hydraulic system provides an immediate preset pressure to the spring-loaded brake shoes and holds it at this value to decelerate the antenna at the desired rate.

  18. Operational limitations of light water reactors relating to fuel performance

    International Nuclear Information System (INIS)

    Cheng, H.S.

    1976-07-01

    General aspects of fuel performance for typical Boiling and Pressurized Water Reactors are presented. Emphasis is placed on fuel failures in order to make clear important operational limitations. A discussion of fuel element designs is first given to provide the background information for the subsequent discussion of several fuel failure modes that have been identified. Fuel failure experiences through December 31, 1974, are summarized. The operational limitations that are required to mitigate the effects of fuel failures are discussed

  19. Feedback control of a primary pump for safe and stable operation of a PIUS-type reactor

    International Nuclear Information System (INIS)

    Tasaka, K.; Imai, S.; Masaoka, H.; Tamaki, M.; Kukita, Y.

    1993-01-01

    A new automatic pump speed control system by using a measurement of the temperature distribution in the lower density lock is proposed for the PIUS-type reactor. This control system maintains the fluid temperature at the axial center of the lower density lock at the average of the fluid temperatures below and above the density lock in order to prevent the poison water from penetrating into the core during normal operation. The effectiveness of this control system was successfully confirmed by a series of experiments such as start-up and power ramping tests for the stable normal operation and a loss-of-feedwater test for the safe shutdown in an accident condition, using a small scale atmospheric pressure test loop which simulated the PIUS principle. (orig.)

  20. Limiting conditions for operation relaxation program

    International Nuclear Information System (INIS)

    Merz, J.F.

    1985-01-01

    The purpose of this effort was to assess the impact of system maintenance unavailability on plant risk to provide technical justification for the relaxation of system limiting conditions for operation from three to seven days. The primary goal of the relaxation program is to allow for more thorough equipment maintenance. A potential increase in out-of-service time for a particular outage caused by the performance of more effective repairs will be counterbalanced by a probable decrease in the frequency in the outage rate of a component. Benefits resulting from an increase in allowed outage time include: (a) a potential reduction in total system out-of-service time, (b) a minimization of challenges to plant systems, and (c) a reduction in the number of emergency technical specification change requests. This program therefore offers an opportunity to more effectively manage plant maintenance and operation

  1. 40 CFR 63.6640 - How do I demonstrate continuous compliance with the emission limitations and operating limitations?

    Science.gov (United States)

    2010-07-01

    ... 200 hours of operation from engine startup (engine burn-in period) are not violations. Rebuilt... units is limited to 100 hours per year. The owner or operator may petition the Administrator for... require maintenance and testing of emergency RICE beyond 100 hours per year. (4) You may operate your...

  2. Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies

    International Nuclear Information System (INIS)

    2001-01-01

    In co-operation with the OECD Nuclear Energy Agency (NEA), the Halden Reactor Project organised a Summer School on ''Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies'' in the period August 27-August 31, 2001. The Summer School was intended for scientists, engineers and technicians working for nuclear installations, engineering companies, industry and members of universities and research institutes, who wanted to broaden their nuclear background by getting acquainted with Man-Technology-Organisation-related subjects and issues. The Summer School should also serve to transfer knowledge to the ''young generation'' in the nuclear field. The following presentations were given: (1) Overview of the Nuclear Community and Current issues, (2) The Elements of Safety Culture; Evaluation of Events, (3) Quality Management (QM), (4) Probabilistic Risk Assessment (PSA), (5) Human Behaviour from the Viewpoint of Industrial Psychology, (6) Technical tour of the Halden Project Experimental Facilities, (7) Human Factors in Control Room Design, (8) Computerised Operator Support Systems (COSSs) and (9) Artificial Intelligence; a new Approach. Most of the contributions are overhead figures from spoken lectures

  3. Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    In co-operation with the OECD Nuclear Energy Agency (NEA), the Halden Reactor Project organised a Summer School on ''Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies'' in the period August 27-August 31, 2001. The Summer School was intended for scientists, engineers and technicians working for nuclear installations, engineering companies, industry and members of universities and research institutes, who wanted to broaden their nuclear background by getting acquainted with Man-Technology-Organisation-related subjects and issues. The Summer School should also serve to transfer knowledge to the ''young generation'' in the nuclear field. The following presentations were given: (1) Overview of the Nuclear Community and Current issues, (2) The Elements of Safety Culture; Evaluation of Events, (3) Quality Management (QM), (4) Probabilistic Risk Assessment (PSA), (5) Human Behaviour from the Viewpoint of Industrial Psychology, (6) Technical tour of the Halden Project Experimental Facilities, (7) Human Factors in Control Room Design, (8) Computerised Operator Support Systems (COSSs) and (9) Artificial Intelligence; a new Approach. Most of the contributions are overhead figures from spoken lectures.

  4. High performance discharges near the operational limit in HT-7

    International Nuclear Information System (INIS)

    Li Jiangang; Wan Baonian; Luo Jiarong; Gao Xiang; Zhao Yanping; Kuang Guangli; Zhang Xiaodong; Yang Yu; Yi Bao; Bojiang Ding; Jikang Xie; Yuanxi Wan

    2001-01-01

    Efforts have been made on the HT-7 tokamak to extend the stable operation boundaries. Extensive RF boronization and siliconization have been used and a wider operational Hugill diagram has been obtained. The transit density reached 1.3 times the Greenwald density limit in ohmic discharges. A stationary high performance discharge with q a =2.1 has been obtained after siliconization. Confinement improvement was obtained as a result of the significant reduction of electron thermal diffusivity χ e in the outer region of the plasma. An improved confinement phase was also observed with LHCD in the density range of 70-120% of the Greenwald density limit. Off-axis LH wave power deposition was attributed to the weak hollow current density profile. Code simulations and measurements showed good agreement with the off-axis LH wave deposition. Supersonic molecular beam injection has been successfully used to achieve stable high density operation in the region of the Greenwald density limit. (author)

  5. High performance operational limits of tokamak and helical systems

    International Nuclear Information System (INIS)

    Yamazaki, Kozo; Kikuchi, Mitsuru

    2003-01-01

    The plasma operational boundaries of tokamak and helical systems are surveyed and compared with each other. Global confinement scaling laws are similar and gyro-Bohm like, however, local transport process is different due to sawtooth oscillations in tokamaks and ripple transport loss in helical systems. As for stability limits, achievable tokamak beta is explained by ideal or resistive MHD theories. On the other hand, beta values obtained so far in helical system are beyond ideal Mercier mode limits. Density limits in tokamak are often related to the coupling between radiation collapse and disruptive MHD instabilities, but the slow radiation collapse is dominant in the helical system. The pulse length of both tokamak and helical systems is on the order of hours in small machines, and the longer-pulsed good-confinement plasma operations compatible with radiative divertors are anticipated in both systems in the future. (author)

  6. Curiosity's Autonomous Surface Safing Behavior Design

    Science.gov (United States)

    Neilson, Tracy A.; Manning, Robert M.

    2013-01-01

    The safing routines on all robotic deep-space vehicles are designed to put the vehicle in a power and thermally safe configuration, enabling communication with the mission operators on Earth. Achieving this goal is made a little more difficult on Curiosity because the power requirements for the core avionics and the telecommunication equipment exceed the capability of the single power source, the Multi-Mission Radioisotope Thermoelectric Generator. This drove the system design to create an operational mode, called "sleep mode", where the vehicle turns off most of the loads in order to charge the two Li-ion batteries. The system must keep the vehicle safe from over-heat and under-heat conditions, battery cell failures, under-voltage conditions, and clock failures, both while the computer is running and while the system is sleeping. The other goal of a safing routine is to communicate. On most spacecraft, this simply involves turning on the receiver and transmitter continuously. For Curiosity, Earth is above the horizon only a part of the day for direct communication to the Earth, and the orbiter overpass opportunities only occur a few times a day. The design must robustly place the Rover in a communicable condition at the correct time. This paper discusses Curiosity's autonomous safing behavior and describes how the vehicle remains power and thermally safe while sleeping, as well as a description of how the Rover communicates with the orbiters and Earth at specific times.

  7. Experience with dose limitation during preparations for sea dumping operations

    International Nuclear Information System (INIS)

    Fieuw, G.; Voorde, N. van de; Baekelandt, L.

    1982-01-01

    Since 1967 low-level radioactive wastes from operational nuclear facilities in Belgium have been dumped into the sea. The dumping is carried out in accordance with the recommendations issued by the IAEA under the London Convention. All these dumping operations have taken place under the surveillance of the Nuclear Energy Agency of the OECD. To limit the doses received by workers and the public during the various phases leading up to sea dumping, appropriate measures are required in connection with waste treatment and packaging, limitation of radiation levels, storage and handling, organization and selection of the means of transport and organization and means of monitoring. Although treatment and handling at the nuclear sites are entrusted to occupationally exposed workers, temporary labour is used for the transport and handling operations. Effective treatment and packaging reduce the risk of internal exposure to a negligible value. Meticulous planning and permanent personnel monitoring reduce the doses received by the workers to acceptable values not exceeding the statutory dose limits. The doses received by personnel involved in the preparations for sea dumping operations from 1967 to 1980 are given and a relationship is established between these doses and the activities handled. Experience shows that sea dumping operations do not entail unacceptable risks either for the workers concerned or for the population and allows us to optimize the methods used for loading, handling and transport. (author)

  8. Allowing variance may enlarge the safe operating space for exploited ecosystems.

    Science.gov (United States)

    Carpenter, Stephen R; Brock, William A; Folke, Carl; van Nes, Egbert H; Scheffer, Marten

    2015-11-17

    Variable flows of food, water, or other ecosystem services complicate planning. Management strategies that decrease variability and increase predictability may therefore be preferred. However, actions to decrease variance over short timescales (2-4 y), when applied continuously, may lead to long-term ecosystem changes with adverse consequences. We investigated the effects of managing short-term variance in three well-understood models of ecosystem services: lake eutrophication, harvest of a wild population, and yield of domestic herbivores on a rangeland. In all cases, actions to decrease variance can increase the risk of crossing critical ecosystem thresholds, resulting in less desirable ecosystem states. Managing to decrease short-term variance creates ecosystem fragility by changing the boundaries of safe operating spaces, suppressing information needed for adaptive management, cancelling signals of declining resilience, and removing pressures that may build tolerance of stress. Thus, the management of variance interacts strongly and inseparably with the management of resilience. By allowing for variation, learning, and flexibility while observing change, managers can detect opportunities and problems as they develop while sustaining the capacity to deal with them.

  9. Compliant Task Execution and Learning for Safe Mixed-Initiative Human-Robot Operations

    Science.gov (United States)

    Dong, Shuonan; Conrad, Patrick R.; Shah, Julie A.; Williams, Brian C.; Mittman, David S.; Ingham, Michel D.; Verma, Vandana

    2011-01-01

    We introduce a novel task execution capability that enhances the ability of in-situ crew members to function independently from Earth by enabling safe and efficient interaction with automated systems. This task execution capability provides the ability to (1) map goal-directed commands from humans into safe, compliant, automated actions, (2) quickly and safely respond to human commands and actions during task execution, and (3) specify complex motions through teaching by demonstration. Our results are applicable to future surface robotic systems, and we have demonstrated these capabilities on JPL's All-Terrain Hex-Limbed Extra-Terrestrial Explorer (ATHLETE) robot.

  10. Experience with respect to dose limitation in nuclear fuel service operations in the United Kingdom supporting civil nuclear power programmes

    International Nuclear Information System (INIS)

    Kennedy, J.W.

    1983-01-01

    Within the United Kingdom, the nuclear power generation programme is supported by nuclear fuel services including uranium enrichment, fuel fabrication and reprocessing, operated by British Nuclear Fuels Limited (BNFL). These have entailed the processing of large quantities of uranium and of plutonium and fission products arising in the course of irradiation of fuel in nuclear power stations and have necessitated substantial programmes for the radiological protection of the public and of the workers employed in the industry. This paper presents and reviews the statistics of doses recorded in the various sectors of nuclear fuel services operations against the background of the standards to which the industry is required to operate. A description is given of the development of BNFL policy in keeping with the objective of being recognized as among those industries regarded as safe and the resource implications of measures to reduce doses received by workers are reviewed in the light of experience. Finally, the paper reviews the epidemiological data which have been, and continue to be, collected for workers who have been employed in these nuclear fuel services. (author)

  11. Reactive, Safe Navigation for Lunar and Planetary Robots

    Science.gov (United States)

    Utz, Hans; Ruland, Thomas

    2008-01-01

    When humans return to the moon, Astronauts will be accompanied by robotic helpers. Enabling robots to safely operate near astronauts on the lunar surface has the potential to significantly improve the efficiency of crew surface operations. Safely operating robots in close proximity to astronauts on the lunar surface requires reactive obstacle avoidance capabilities not available on existing planetary robots. In this paper we present work on safe, reactive navigation using a stereo based high-speed terrain analysis and obstacle avoidance system. Advances in the design of the algorithms allow it to run terrain analysis and obstacle avoidance algorithms at full frame rate (30Hz) on off the shelf hardware. The results of this analysis are fed into a fast, reactive path selection module, enforcing the safety of the chosen actions. The key components of the system are discussed and test results are presented.

  12. Selection of exception limits for all actinide nuclides based on revised criteria for safe international transport and including storage delay

    International Nuclear Information System (INIS)

    Lavarenne, C.; Rouyer, V.; Mennerdahl, D.; Dean, C.; Barton, N.; Jean, F.

    2004-01-01

    Since 1998, there have been some speculations about future transport of significant quantities and concentrations of other actinide nuclides than the four currently listed in the regulation for the safe transport of the radioactive material. Therefore, it raised a need to specify exception limits for such actinides. In order to define credible exception limits, it was necessary to have reasonably accurate data for all actinide nuclides. Then the DGTREN/participants decided to perform calculations with different codes (MONK, MCNP, CRISTAL and SCALE) and different cross-section libraries (JEF2.2, ENDFB, etc.). The parameters of interest (such as k-infinite, critical masses) were determined. This article presents the work achieved and the questions raised, e.g. related to the effect of the radioactive decay of the isotopes on the criticality risks. It also points out the need for an evolution of the regulation of the safe transport of radioactive materials and gives a proposition of modification for the IAEA requirements related to, firstly, the list of the fissile materials, secondly, the rule to determine the quantities of actinide nuclides that can be excepted from the requirements for the packages containing fissile materials

  13. TFTR movable limiter instrumentation and controls

    International Nuclear Information System (INIS)

    Frankenberg, J.; Collins, D.; Kaufmann, D.; Mamoun, A.

    1983-01-01

    The TFTR movable limiter is a single poloidal limiter located within one 18 /SUP o/ segment of the vacuum vessel. It consists of three (3) interconnected inconel backing plates covered with titanium carbide coated graphite tiles. The backing plates are positioned by three independent screw drive actuators. Cooling water is fed through the horizontal port cover to tubes brazed onto the backs of the backing plates. Thermocouples monitor the limiter temperature. (1) and more fully described in refs. (1) and (2). The positioning actuators are driven by independently controlled DC servo motors, controlled either locally or from CICADA. Drive motor shaft position is monitored by chain driven encoders and potentiometers. Limiter blade position can be varied to suit any plasma within the operating range. CICADA is programmed to keep the limiter stroke within safe operating limits. A microprocessor duplicates the CICADA protective function allowing limiter operation without CICADA. The potentiometer signal is sent to an analog computer, which safeguards the limiter against failure of the encoders or the micro-processor. Cooling water flows through the limiter in 3 separate paths, one for each blade. The flow rate and temperature rise through each loop are measured accurately to allow CICADA to calculate the heat into each blade. The water system is also interlocked and alarmed to prevent dumping of water into the vacuum vessel

  14. Prioritizing essential surgery and safe anesthesia for the Post-2015 Development Agenda: operative capacities of 78 district hospitals in 7 low- and middle-income countries.

    Science.gov (United States)

    LeBrun, Drake G; Chackungal, Smita; Chao, Tiffany E; Knowlton, Lisa M; Linden, Allison F; Notrica, Michelle R; Solis, Carolina V; McQueen, K A Kelly

    2014-03-01

    Surgery has been neglected in low- and middle-income countries for decades. It is vital that the Post-2015 Development Agenda reflect that surgery is an important part of a comprehensive global health care delivery model. We compare the operative capacities of multiple low- and middle-income countries and identify critical gaps in surgical infrastructure. The Harvard Humanitarian Initiative survey tool was used to assess the operative capacities of 78 government district hospitals in Bangladesh (n = 7), Bolivia (n = 11), Ethiopia (n = 6), Liberia (n = 11), Nicaragua (n = 10), Rwanda (n = 21), and Uganda (n = 12) from 2011 to 2012. Key outcome measures included infrastructure, equipment availability, physician and nonphysician surgical providers, operative volume, and pharmaceutical capacity. Seventy of 78 district hospitals performed operations. There was fewer than one surgeon or anesthesiologist per 100,000 catchment population in all countries except Bolivia. There were no physician anesthesiologists in any surveyed hospitals in Rwanda, Liberia, Uganda, or in the majority of hospitals in Ethiopia. Mean annual operations per hospital ranged from 374 in Nicaragua to 3,215 in Bangladesh. Emergency operations and obstetric operations constituted 57.5% and 40% of all operations performed, respectively. Availability of pulse oximetry, essential medicines, and key infrastructure (water, electricity, oxygen) varied widely between and within countries. The need for operative procedures is not being met by the limited operative capacity in numerous low- and middle-income countries. It is of paramount importance that this gap be addressed by prioritizing essential surgery and safe anesthesia in the Post-2015 Development Agenda. Copyright © 2014 Mosby, Inc. All rights reserved.

  15. Inherent Tumor Characteristics That Limit Effective and Safe Resection of Giant Nonfunctioning Pituitary Adenomas.

    Science.gov (United States)

    Nishioka, Hiroshi; Hara, Takayuki; Nagata, Yuichi; Fukuhara, Noriaki; Yamaguchi-Okada, Mitsuo; Yamada, Shozo

    2017-10-01

    Surgical treatment of giant pituitary adenomas is sometimes challenging. We present our surgical series of giant nonfunctioning adenomas to shed light on the limitations of effective and safe tumor resection. The preoperative tumor characteristics, surgical approaches, outcome, and histology of giant nonfunctioning adenoma (>40 mm) in 128 consecutive surgical patients are reviewed. The follow-up period ranged from 19 to 113 months (mean 62.2 months). A transsphenoidal approach was used in the treatment of 109 patients and a combined transsphenoidal transcranial approach in 19 patients. A total of 93 patients (72.7%) underwent total resection or subtotal resection apart from the cavernous sinus (CS). The degree of tumor resection, excluding the marked CS invasion, was lower in tumors that were larger (P = 0.0107), showed massive intracranial extension (P = 0.0352), and had an irregular configuration (P = 0.0016). Permanent surgical complications developed in 28 patients (22.0%). Long-term tumor control was achieved in all patients by single surgery, including 43 patients with adjuvant radiotherapy. Most tumors were histologically benign, with a low MIB-1 index (inherent factors that independently limit effective resection. These high-risk tumors require an individualized therapeutic strategy. Copyright © 2017 Elsevier Inc. All rights reserved.

  16. Instructional maps of safe working methods and practices for separate types of opera-tions conducted in the oil mine

    Directory of Open Access Journals (Sweden)

    И. В. Климова

    2017-06-01

    Full Text Available Instructing personnel in the issues of labor protection and industrial safety at hazardous facilities is one of the main tasks that face the employer; the quality with which this procedure is organized and carried out defines not only company’s indicators, but the mere possibility of its normal functioning. The paper contains a detailed overview of the typical content of standard documentation, which is currently used when conducting operations in the oil mines of Yarega high-viscosity oil deposit. Distinct features and unique nature of this oil field require special measures to guarantee safety of personnel and all facilities in general.The author proposes and reviews an additional type of operating guidelines – instructional map of safe working methods and practices. It is more illustrative than existing documentation (charts of inclined shaft development, labor protection regulations, which allows to upgrade the process of instructing personnel in the oil mines, to improve the quality of instructions and to reduce the risk of emergencies, accidents, industrial injuries.The author reviews the structure of suggested instructional map, offers a detailed arrangement diagram for the main thematic sections of the map, as well as their content. Instructional maps are regarded as a type of operating guidelines that include: description and characteristics of equipment, instruments and appliances; general safety requirements; content and execution sequence of operational elements with their graphical images; distribution of responsibilities with an indication of their priority in case the operations are conducted by several workers; specific safety requirements for equipment, materials, instruments, safety clothes and footwear, personal protective gear etc. (prohibitions, warnings.Advantages and disadvantages of proposed instructional maps of safe working methods and practices are highlighted.

  17. MHD stability, operational limits and disruptions

    International Nuclear Information System (INIS)

    1999-01-01

    The present physics understandings of magnetohydrodynamic (MHD) stability of tokamak plasmas, the threshold conditions for onset of MHD instability, and the resulting operational limits on attainable plasma pressure (beta limit) and density (density limit), and the consequences of plasma disruption and disruption related effects are reviewed and assessed in the context of their application to a future DT burning reactor prototype tokamak experiment such as ITER. The principal considerations covered within the MHD stability and beta limit assessments are (i) magnetostatic equilibrium, ideal MHD stability and the resulting ideal MHD beta limit; (ii) sawtooth oscillations and the coupling of sawtooth activity to other types of MHD instability; (iii) neoclassical island resistive tearing modes and the corresponding limits on beta and energy confinement; (iv) wall stabilization of ideal MHD instabilities and resistive wall instabilities; (v) mode locking effects of non-axisymmetric error fields; (vi) edge localized MHD instabilities (ELMs, etc.); and (vii) MHD instabilities and beta/pressure gradient limits in plasmas with actively modified current and magnetic shear profiles. The principal considerations covered within the density limit assessments are (i) empirical density limits; (ii) edge power balance/radiative density limits in ohmic and L-mode plasmas; and (iii) edge parameter related density limits in H-mode plasmas. The principal considerations covered in the disruption assessments are (i) disruption causes, frequency and MHD instability onset; (ii) disruption thermal and current quench characteristics; (iii) vertical instabilities (VDEs), both before and after disruption, and plasma and in-vessel halo currents; (iv) after disruption runaway electron formation, confinement and loss; (v) fast plasma shutdown (rapid externally initiated dissipation of plasma thermal and magnetic energies); (vi) means for disruption avoidance and disruption effect mitigation; and

  18. Life Limiting Issues for Long Term Operation of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Esselman, Thomas; Gaertner, John

    2012-01-01

    This paper reports on a study which identified and characterized life limiting issues for consideration by nuclear plant owners in their decision to extend plant life or seek subsequent license renewal. As nuclear plants operate for longer periods, the risk that a condition in the plant or an event that occurs, at the plant or elsewhere, will cause a plant owner not to extend plant life increases. The Fukushima accident has made this concept concrete. This paper defines 'Life Limiting' concepts for nuclear plants. It identifies the highest risk conditions and events that may limit duration of continued operation in nuclear plants and employs a survey to prioritize these concerns. Methods for evaluating these risks and changing the capability of systems, structures, and components (SSC) to reduce and manage this risk in long term operation are presented. Integrated obsolescence -the existence of an accumulation of events or condition that can threaten long term operation- is discussed. Many of the life limiting conditions or events may be controllable by early identification, recognition, and mitigation of the potential threat. The recognition of conditions may allow measures to be taken to mitigate the condition. Recognition of the potential for events that may be life limiting may allow actions to be taken that will minimize the likelihood or consequences of the event. These actions may include enhanced research on the expected behavior of the SSC, risk assessment and management, and enhanced monitoring and aging management at the plant. (author)

  19. Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    In co-operation with the OECD Nuclear Energy Agency (NEA), the Halden Reactor Project organised a Summer School on ''Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies'' in the period August 27-August 31, 2001. The Summer School was intended for scientists, engineers and technicians working for nuclear installations, engineering companies, industry and members of universities and research institutes, who wanted to broaden their nuclear background by getting acquainted with Man-Technology-Organisation-related subjects and issues. The Summer School should also serve to transfer knowledge to the ''young generation'' in the nuclear field. The following presentations were given: (1) Overview of the Nuclear Community and Current issues, (2) The Elements of Safety Culture; Evaluation of Events, (3) Quality Management (QM), (4) Probabilistic Risk Assessment (PSA), (5) Human Behaviour from the Viewpoint of Industrial Psychology, (6) Technical tour of the Halden Project Experimental Facilities, (7) Human Factors in Control Room Design, (8) Computerised Operator Support Systems (COSSs) and (9) Artificial Intelligence; a new Approach. Most of the contributions are overhead figures from spoken lectures.

  20. Manpower development for safe operation of nuclear power plant. China. Simulator software development. UNDP-Activity: 2.1.8-IAEA-Task-01. Technical report

    International Nuclear Information System (INIS)

    Feng, C.P.

    1994-01-01

    In the frameworks of the project ''manpower development for safe operation of nuclear power plant'' the development of reactor simulator software is described. Qinshan nuclear power plant was chosen as a reference one

  1. Halden fuel and material experiments beyond operational and safety limits

    International Nuclear Information System (INIS)

    Volkov, Boris; Wiesenack, Wolfgang; McGrath, M.; Tverberg, T.

    2014-01-01

    One of the main tasks of any research reactor is to investigate the behavior of nuclear fuel and materials prior to their introduction into the market. For commercial NPPs, it is important both to test nuclear fuels at a fuel burn-up exceeding current limits and to investigate reactor materials for higher irradiation dose. For fuel vendors such tests enable verification of fuel reliability or for the safety limits to be found under different operational conditions and accident situations. For the latter, in-pile experiments have to be performed beyond some normal limits. The program of fuel tests performed in the Halden reactor is aimed mainly at determining: The thermal FGR threshold, which may limit fuel operational power with burn-up increase, the “lift-off effect” when rod internal pressure exceeds coolant pressure, the effects of high burn-up on fuel behavior under power ramps, fuel relocation under LOCA simulation at higher burn-up, the effect of dry-out on high burn-up fuel rod integrity. This paper reviews some of the experiments performed in the Halden reactor for understanding some of the limits for standard fuel utilization with the aim of contributing to the development of innovative fuels and cladding materials that could be used beyond these limits. (author)

  2. Safeguards Automated Facility Evaluation (SAFE) methodology

    International Nuclear Information System (INIS)

    Chapman, L.D.; Grady, L.M.; Bennett, H.A.; Sasser, D.W.; Engi, D.

    1978-01-01

    The SAFE procedure is an efficient method of evaluating the physical protection system of a nuclear facility. Since the algorithms used in SAFE for path generation and evaluation are analytical, many paths can be evaluated with a modest investment in computer time. SAFE is easy to use because the information required is well-defined and the interactive nature of this procedure lends itself to straightforward operation. The modular approach that has been taken allows other functionally equivalent modules to be substituted as they become available. The SAFE procedure has broad applications in the nuclear facility safeguards field as well as in the security field in general. Any fixed facility containing valuable materials or components to be protected from theft or sabotage could be analyzed using this same automated evaluation technique

  3. Limited Area Predictability: Is There A Limit To The Operational Usefulness of A Lam

    Science.gov (United States)

    Mesinger, F.

    The issue of the limited area predictability in the context of the operational experience of the Eta Model, driven by the LBCs of the NCEP global spectral (Avn) model, is examined. The traditional view is that "the contamination at the lateral boundaries ... limits the operational usefulness of the LAM beyond some forecast time range". In the case of the Eta this contamination consists not only of the lower resolution of the Avn LBCs and the much discussed mathematical "lateral boundary error", but also of the use of the LBCs of the previous Avn run, at 0000 and 1200 UTC estimated to amount to about an 8 h loss in accuracy. Looking for the signs of the Eta accuracy in relative terms falling behind that of the Avn we have examined the trend of the Eta vs Avn precipitation scores, the rms fits to raobs of the two models as a function of time, and the errors of these models at extended forecast times in placing the centers of major lows. In none of these efforts, some including forecasts out to 84 h, we were able to notice signs of the Eta accuracy being visibly affected by the inflow of the lateral boundary errors. It is therefore hypothesized that some of the Eta design features compensate for the increasing influence of the Avn LBC errors. Candidate features are discussed, with the eta coordinate being a contender to play a major role. This situation being possible for the pair of models discussed, existence of a general limit for the operational usefulness of a LAM seems questionable.

  4. Potential Operating Orbits for the SAFE-400

    International Nuclear Information System (INIS)

    Houts, Mike; Kos, Larry; Poston, David

    2002-01-01

    Safety must be ensured during all phases of space fission system design, development, fabrication, launch, operation, and shutdown. One potential space fission system application is fission electric propulsion (FEP), in which fission energy is converted into electricity and used to power high efficiency (Isp > 3000 s) electric thrusters. For these types of systems it is important to determine which operational scenarios ensure safety while allowing maximum mission performance and flexibility. Space fission systems are essentially non-radioactive at launch, prior to extended operation at high power. Once high power operation begins, system radiological inventory steadily increases as fission products build up. For a given fission product isotope, the maximum radiological inventory is typically achieved once the system has operated for a length of time equivalent to several half-lives. After that time, the isotope decays at the same rate it is produced, and no further inventory builds in. For an FEP mission beginning in Earth orbit, altitude and orbital lifetime increase as the propulsion system operates. Two simultaneous effects of fission propulsion system operation are thus (1) increasing fission product inventory and (2) increasing orbital lifetime. Phrased differently, as fission products build up, more time is required for the fission products to naturally convert back into non-radioactive isotopes. Simultaneously, as fission products build up, orbital lifetime increases, providing more time for the fission products to naturally convert back into nonradioactive isotopes. Operational constraints required to ensure safety can thus be quantified. (authors)

  5. Reactor limitation system improves the safety and availability of the Angra 2 nuclear power plant

    International Nuclear Information System (INIS)

    Souza Mendes, J.E. de

    1987-01-01

    Beyond the classic Reactor Protection System and Reactor Control System, nuclear plant Angra 2 has a third system called Reactor Limitation System which combines the intelligence features of the control systems with the high reliability of the protection systems. In determined events, which are not controlled by the control system (e.g.: load rejection, failure of one main reactor coolant pump), the Reactor Limitation System actuates automatically in order to lead the plant to a safe operating condition and so it avoids the actuation of the Reactor Protection System and consequently the reactor trip. This increases safety and availability of the plant and reduces component stresses. After the safe operating condition is reached, the process guidance automatically returns to the control systems. (Author) [pt

  6. Safe operation of nuclear ships

    International Nuclear Information System (INIS)

    Danilov, L.

    1982-01-01

    A summary is given of the experience with the three Soviet nuclear icebreakers, Lenin, Arktika and Sibir. Engineering problems, especially of reactor maintenance, and the way they have been overcome, are described. Reference is also made to improvements in reactor fuel and core design, and to safety aspects of the refuelling operation. (U.K.)

  7. 29 CFR 780.200 - Inclusion of forestry or lumbering operations in agriculture is limited.

    Science.gov (United States)

    2010-07-01

    ... 29 Labor 3 2010-07-01 2010-07-01 false Inclusion of forestry or lumbering operations in agriculture is limited. 780.200 Section 780.200 Labor Regulations Relating to Labor (Continued) WAGE AND HOUR... Lumbering Operations § 780.200 Inclusion of forestry or lumbering operations in agriculture is limited...

  8. Limits on CP-odd four-fermion operators containing the strange quark field

    International Nuclear Information System (INIS)

    Hamzaoui, C.; Pospelov, M.

    1999-01-01

    The bounds on the neutron electric dipole moment and T-odd nucleon-nucleon interaction are used to extract the limits on the effective CP-odd four-fermion operators containing a strange quark field. This completes the study of the dim=5,6 CP-odd operators built from light-quark fields. The limits are very strong and comparable to those obtained previously for operators containing up and down flavors. We also analyze the shift of the axionic vacuum, θ eff , induced by four-fermion operators in the presence of the PQ mechanism and conclude that this gives subleading contributions to CP-odd observables as compared with the direct ones. copyright 1999 The American Physical Society

  9. Safe application of a restrictive transfusion protocol in moderate-risk patients undergoing cardiac operations.

    Science.gov (United States)

    Song, Howard K; von Heymann, Christian; Jespersen, Christian M; Karkouti, Keyvan; Korte, Wolfgang; Levy, Jerrold H; Ranucci, Marco; Saugstrup, Trine; Sellke, Frank W

    2014-05-01

    Perioperative red blood cell transfusion is associated with adverse outcomes after cardiac operations. Although restrictive transfusion protocols have been developed, their safety and efficacy are not well demonstrated, and considerable variation in transfusion practice persists. We report our experience with a restrictive transfusion protocol. We analyzed the outcomes in 409 patients undergoing cardiac operations enrolled in a trial conducted at 30 centers worldwide. Blood products were administered on the basis of a transfusion algorithm applied across all centers, with a restrictive transfusion trigger of hemoglobin less than or equal to 6 g/dL. Transfusion was acceptable but not mandatory for hemoglobin 6 to 8 g/dL. For hemoglobin 8 to 10 g/dL, transfusion was acceptable only with evidence for end-organ ischemia. The patient population was moderately complex, with 20.5% having combined procedures and 29.6% having nonelective operations. The mean EuroSCORE for the population was 4.3, which predicted a substantial incidence of morbidity and mortality. Actual outcomes were excellent, with observed mortality of 0.49% and rates of cerebrovascular accident, myocardial infarction, and acute renal failure 1.2%, 6.1%, and 0.98%, respectively. The frequency of red blood cell transfusion was 33.7%, which varied significantly by center. Most transfusions (71.9%) were administered for hemoglobin 6 to 8 g/dL; 21.4% were administered for hemoglobin 8 to 10 g/dL with evidence for end-organ ischemia; 65.0% of patients avoided allogeneic transfusion altogether. A restrictive transfusion protocol can be safely applied in the care of moderate-risk patients undergoing cardiac operations. This strategy has significant potential to reduce transfusion and resource utilization in these patients, standardize transfusion practices across institutions, and increase the safety of cardiac operations. Copyright © 2014 The Society of Thoracic Surgeons. Published by Elsevier Inc. All rights

  10. On the intrinsic transient capability and limitations of solid oxide fuel cell systems

    OpenAIRE

    Mueller, F; Jabbari, F; Brouwer, J

    2009-01-01

    The intrinsic transient performance capability and limitation of integrated solid oxide fuel cell (SOFC) systems is evaluated based on the system balance-of-plant response and fuel cell operating requirements (i.e., allowable deviation from nominal operation). Specifically, non-dimensional relations are derived from conservation principles that quantify the maximum instantaneous current increase that a solid oxide fuel cell system can safely manage based on (1) the desired fuel cell operating...

  11. Designing a 'safe and just operating space' for the Chilika lagoon fishery of the Mahanadi delta, India

    Science.gov (United States)

    Cooper, Gregory; Dearing, John

    2017-04-01

    Annual fish production from the Chilika lagoon is worth US25-million/year, underpinning the livelihoods of 35,000 fishers and 200,000 secondary dependants. The system has a legacy of collapse, transitioning from annual production rates of 9000 tonnes to 1300 tonnes during the late-1980s, with resulting livelihood losses triggering the first recorded instances of economic migration from Chilika. Despite engineered recovery since 2000, the future persistence of Chilika's resource stock is uncertain. Climate change may strengthen freshwater and sediment delivery, promoting ecohydrological degradation through tidal outlet sedimentation, reduced salinity and freshwater weed growth. Simultaneously, human population growth, fleet motorisation and consumption demands threaten overexploitation driven collapse. These critical social-ecological drivers and feedbacks are projected into future by integrating system dynamics modelling with Monte Carlo inputs. Sustainable pathways are identified from outputs producing social-ecologically desirable futures, such as mid-century catch equalling maximum sustainable yield. The 'safe and just operating space' metaphor is regionalised by the limits of sustainable trajectories, such as the permissible number of active fishers, motorised boats and juvenile catch under alternative governance scenarios. These critical thresholds suggest policy-relevant guardrails for the sustainable governance of Chilika, in order to avoid regional productivity collapse, ecological degradation and livelihood losses. Benefits and trade-offs of alternative governance approaches are also discussed, aiding the optimisation of future regulatory decision-making.

  12. A guide to safe field operations

    Science.gov (United States)

    Yobbi, D.K.; Yorke, T.H.; Mycyk, R.T.

    1996-01-01

    Most functions of the U.S. Geological Survey (USGS), Water Resources Division (WRD) require employees to participate in numerous field activities ranging from routine meetings with cooperators, other federal and public officials, and private citizens to potentially hazardous assignments, such as making flood measurements and scuba diving to service underwater instruments. It is paramount that each employee be aware of safety procedures and operational policies of the WRD to ensure that (1) their activities avoid or minimize personal injury to the employee, coworkers, or anyone in the vicinity of the field activity, and (2) their conduct does not infringe on the personal or property rights of any individual or organization. The purpose of the guide is to familiarize employees with the operational and safety procedures expected to be followed by each employee as a representative of the WRD. It is also intended as a training tool for all new employees and a document to be reviewed by each employee before undertaking a field assignment. It includes general procedures that are standard and applicable to all field operations, such as communication, vehicle operation, and adequate preparation for anticipated weather conditions. It also includes a discussion of specific procedures and safety considerations for most of the routine field assignments undertaken by hydrologists and hydrologic technicians of the WRD. The guide is not intended to be a technical handbook outlining step-by-step procedures for performing specific tasks or a comprehensive discussion of every possible activity that may be undertaken by a USGS employee. Employees are referred to the Techniques for Water-Resources Investigations (TWRI) series for specific technical procedures and to the U.S. Geological Survey Safety and Environmental Health Handbook 445-1-H (USGS, August 1989), USGS Occupational Hazards and Safety Procedures Handbook 445-2-H (December 1993), the WRD notebook on Safety Policy and

  13. Low-temperature operating regime of the tokamak evacuating limiter

    International Nuclear Information System (INIS)

    Tokar', M.Z.

    1987-01-01

    The conditions for realizing the regime of strong recycling of a cold dense plasma of an evacuating limiter were determined based on a previously proposed model for describing the limiter layer of a tokamak. The scaling for the dependence of the gas pressure in the evacuation system on the average plasma density in the limiter layer was found, and agreed quantitatively with the results of measurements on the Alcator and ISX-B tokamaks. For the tokamak reactor of the INTOR scale the calculations show that the low-temperature operating regime of the evacuating limiter can be realized with a quite low pumping rate. It has the advantages of reduced erosion of the limiter and small fluxes of impurities into the working volume of the reactor. In addition, the relative concentration of the helium ash in the limiter layer does not exceed 2-3%, but the density of the main plasma is comparable to the proposed average density in the reactor. The concept of a stochastic limiter is of interest for lowering the plasma density in the limiter layer and lowering the thermal loads on the limiter

  14. Lack of recruitment in Lavandula stoechas subsp. pedunculata: a case of safe-site limitation

    Science.gov (United States)

    Sánchez, Ana M.; Peco, Begoña

    2007-01-01

    Lavandula stoechas subsp. pedunculata regeneration depends exclusively on the establishment of new individuals. Seed availability and seedling emergence and survival are therefore critical life stages and processes for species regeneration. In this study, seedling emergence and survival was monitored for two years in the scrub, both in clearings and adjacent to adult plants, and the surrounding perennial grassland, at 1, 3 and 5 m from the scrub. Soil seed bank spatial distribution was also studied for one year in the same two habitats, using the same sampling design. Soil seed availability in the scrub is high regardless of the distance from the adult individuals. On the contrary, the adjacent grassland shows a drastic fall in seed density, and almost no seedlings were observed there. In the scrub, seedling density was negatively related to distance from the three nearest adult plants in the clearings, and positively related to adult plant size beneath the adult Lavandula plants. There was also a negative relationship between seedling density and the percentage of bare soil. Only one seedling survived the first drought period, with no detection of effects of either position with respect to adult individuals or seedling density. We hypothesized that the study populations suffer a lack of appropriate safe sites within the scrubland while in the adjacent perennial grassland, observed low seed availability was added to safe-site limitation. That results in a lack of successful seedling establishments and a poor expansion potential of Lavandula scrublands, whose edges remain static in the short and medium term. As found in other Mediterranean scrubland, recruitment may only occur in years with particularly favourable weather, under disturbance regimes that increase seedling survival probability or when external dispersal agents increased seed availability in adequate places for Lavandula establishment.

  15. Congressional Authority to Limit U.S. Military Operations in Iraq

    National Research Council Canada - National Science Library

    Elsea, Jennifer K; Garcia, Michael J; Nicola, Thomas J

    2007-01-01

    .... The situation in Iraq has focused attention on whether Congress has the constitutional authority to legislate limits on the President's authority to conduct military operations in Iraq, even though...

  16. 78 FR 28278 - Operating Limitations at New York LaGuardia Airport

    Science.gov (United States)

    2013-05-14

    ... between carriers under the same marketing control up to 5 business days after the actual operation. This... of Extension to Order. SUMMARY: This action amends the Order Limiting Operations at New York... Rule on Slot Management and Transparency for LaGuardia Airport, John F. Kennedy International Airport...

  17. Assessment of safety levels in operation rooms at two major tertiary care public hospitals of Karachi. Safe surgery saves life

    International Nuclear Information System (INIS)

    Minhas, M.S.; Muzzammil, M.; Effendi, J.

    2017-01-01

    The objectives of this study are to determine the knowledge and attitude towards surgical safety among the health care professionals including surgeons, anaesthetist, hospital administrators, and operation room personnel and raise awareness towards the importance of safe surgery. Method: A pilot cross- sectional study of 543 healthcare providers working in the operating rooms and the surgical intensive care units was conducted in two tertiary care hospitals, within a study period of one month. A structured questionnaire was constructed and an informed verbal consent was taken. The questionnaire was then distributed; data collected and analysed on SPSS 20.0. Results: A total of 543 respondents participated in the study out of which there were 375 (69%) men and 168 (31%) women. The ages ranged between 23-58 years, mean 40.5+-24.74. There were 110 (20.25%) surgeons, 58 (10.68%) anaesthetist, 132 (24.30%) trainees, 125 (23.02%) technicians, and were 118 (21.73%) nurses. The question regarding briefing operation room personnel is important for patient safety was agreed by 532 (98%) respondents. Amongst the respondents, 239 (44%) did not feel safe to be operated in their own setup. Team communication improvement through the check list implementation was agreed by 483 (89%) respondents. 514 (94.7%) opted for the checklist to be used while they are being operated. That operation room personnel frequently disregard established protocols was agreed by 374 (69%) respondents. 193 (35.54%) of the respondents stated that it is difficult for them to speak up in the or if they perceive a problem with patient care. Conclusion: Operation room personnel were not aware of several important areas related to briefing, communication, safety attitude, following standard protocols and use of WHO Surgical Safety check list. A pre-post intervention study should be conducted after formal introduction of the Checklist. Successful implementation will require taking all stake holders on board

  18. The role of leading twist operators in the Regge and Lorentzian OPE limits

    Energy Technology Data Exchange (ETDEWEB)

    Costa, Miguel S. [Centro de Física do Porto, Departamento de Física e Astronomia,Faculdade de Ciências da Universidade do Porto,Rua do Campo Alegre 687, 4169-007 Porto (Portugal); Drummond, James [CERN,Geneva 23 (Switzerland); School of Physics and Astronomy, University of Southampton,Highfield, Southampton, SO17 1BJ (United Kingdom); LAPTH, CNRS et Université de Savoie,F-74941 Annecy-le-Vieux Cedex (France); Gonçalves, Vasco; Penedones, João [Centro de Física do Porto, Departamento de Física e Astronomia,Faculdade de Ciências da Universidade do Porto,Rua do Campo Alegre 687, 4169-007 Porto (Portugal)

    2014-04-14

    We study two kinematical limits, the Regge limit and the Lorentzian OPE limit, of the four-point function of the stress-tensor multiplet in Super Yang-Mills at weak coupling. We explain how both kinematical limits are controlled by the leading twist operators. We use the known expression of the four-point function up to three loops, to extract the pomeron residue at next-to-leading order. Using this data and the known form of pomeron spin up to next-to-leading order, we predict the behaviour of the four-point function in the Regge limit at higher loops. Specifically, we determine the leading log behaviour at any loop order and the next-to-leading log at four loops. Finally, we check the consistency of our results with conformal Regge theory. This leads us to predict the behaviour around J=1 of the OPE coefficient of the spin J leading twist operator in the OPE of two chiral primary operators.

  19. Safe operation of critical assemblies and research reactors. Code of practice and Technical appendix. 1971 ed

    International Nuclear Information System (INIS)

    Cox, J.

    1971-01-01

    This book is in two parts. The first is a Code of Practice for the Safe Operation of Critical Assemblies and Research Reactors, prepared as a result of a meeting of experts which took place in Vienna on 20-24 May 1968. The Code has been prepared by the International Atomic Energy Agency in co-operation with the World Health Organization, and its publication is sponsored by both organizations. In addition, the Code was approved by the Board of Governors of the International Atomic Energy Agency on 16 December 1968 as part of the Agency's safety standards, which are applied to operations undertaken by Member States with the assistance of the Agency. The Board, in approving the publication of the present book, also recommended Member States to take the Code into account in the formulation of national regulations and recommendations. The second part of the book is a Technical Appendix to give information and illustrative samples that would be helpful in implementing the Code of Practice. This second part, although published under the same cover, is not part of the Code. An extensive Bibliography, amplifying the Technical Appendix, is included at the end.

  20. Operating states of PFBR-primary sodium pump

    International Nuclear Information System (INIS)

    Sreedharan, K.V.; Rao, A.S.L.K.; Raju, C.; Kale, R.D.

    1994-01-01

    The proposed 500 MWe Prototype Fast Breeder Reactor (PFBR), the design of which is in progress at the Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam will be equipped with four centrifugal sodium pumps each in its primary and secondary circuits. This paper discusses the various operating states of the primary pumps viz. (i) normal steady state (ii) transient state operation. The paper also discusses the safe limits on the pump operating speed and a few design basis incidents. (author). 1 ref., 2 figs., 3 tabs

  1. Examination of a University-Affiliated Safe Ride Program

    Science.gov (United States)

    Gieck, D. Joseph; Slagle, David M.

    2010-01-01

    A university-affiliated safe ride program was evaluated to determine whether these programs can reduce drunk-driving related costs. Data was collected from 187 safe ride passengers during three nights of operation. Among the passengers, 93% were enrolled at a local University, 31% were younger than 21, and 40% reported a prior alcohol-related…

  2. Quality performance-based training enhances safe and effective transport operations

    International Nuclear Information System (INIS)

    McCall, D.L.

    1993-01-01

    If the hazardous materials transportation industry is to reduce human error, reduce accidents, and improve its public image, there must be assurance that transportation personnel are properly trained and qualified to perform their jobs in a safe and efficient manner. This training must make them intimately aware of the hazards and risks associated with transport activities, ensure understanding of responsibilities and liabilities unique to their job, and ensure that they can competently perform functional duties vital to safety. To ensure that trained and qualified personnel are on the job, it is essential that the training be performance-based and require trainees to demonstrate functional proficiency. Performance-based training has proven to be a highly effective means of ensuring personnel are qualified to conduct their assignments safely and efficiently. This training is designed around the basic premise that training must be provided that supplies the information necessary for each worker to perform their assigned duties at a predetermined and acceptable level of expertise and skill. (J.P.N.)

  3. 76 FR 18616 - Operating Limitations at New York LaGuardia Airport

    Science.gov (United States)

    2011-04-04

    ... under the same marketing control up to 5 business days after the actual operation. This post-transfer... of Extension to Order. SUMMARY: This action amends the Order Limiting Operations at New York..., 2008, and October 7, 2009. The Order remains effective until the final Congestion Management Rule for...

  4. Turning Off Frequently Overridden Drug Alerts: Limited Opportunities for Doing It Safely

    NARCIS (Netherlands)

    I.H. van der Sijs (Heleen); J.E.C.M. Aarts (Jos); T. van Gelder (Teun); M. Berg (Marc); A.G. Vulto (Arnold)

    2008-01-01

    textabstractObjectives: This study sought to identify opportunities to safely turn off frequently overridden drug-drug interaction alerts (DDIs) in computerized physician order entry (CPOE). Design: Quantitative retrospective analysis of drug safety alerts overridden during 1 month and qualitative

  5. Graphene oxide/metal nanocrystal multilaminates as the atomic limit for safe and selective hydrogen storage.

    Science.gov (United States)

    Cho, Eun Seon; Ruminski, Anne M; Aloni, Shaul; Liu, Yi-Sheng; Guo, Jinghua; Urban, Jeffrey J

    2016-02-23

    Interest in hydrogen fuel is growing for automotive applications; however, safe, dense, solid-state hydrogen storage remains a formidable scientific challenge. Metal hydrides offer ample storage capacity and do not require cryogens or exceedingly high pressures for operation. However, hydrides have largely been abandoned because of oxidative instability and sluggish kinetics. We report a new, environmentally stable hydrogen storage material constructed of Mg nanocrystals encapsulated by atomically thin and gas-selective reduced graphene oxide (rGO) sheets. This material, protected from oxygen and moisture by the rGO layers, exhibits exceptionally dense hydrogen storage (6.5 wt% and 0.105 kg H2 per litre in the total composite). As rGO is atomically thin, this approach minimizes inactive mass in the composite, while also providing a kinetic enhancement to hydrogen sorption performance. These multilaminates of rGO-Mg are able to deliver exceptionally dense hydrogen storage and provide a material platform for harnessing the attributes of sensitive nanomaterials in demanding environments.

  6. Operating manual for the critical experiments facility

    International Nuclear Information System (INIS)

    1986-01-01

    The operation of the Critical Experiments Facility (CEF) requires careful attention to procedures in order that all safety precautions are observed. Since an accident could release large amounts of radioactivity, careful operation and strict enforcement of procedures are necessary. To provide for safe operation, detailed procedures have been written for all phases of the operation of this facility. The CEF operating procedures are not to be construed to constitute a part ofthe Technical Specifications. In the event of any discrepancy between the information given herein and the Technical Specifications, limits set forth in the Technical Specifications apply. All normal and most emergency operation conditions are covered by procedures presented in this manual. These procedures are designed to be followed by the operating personnel. Strict adherence to these procedures is expected for the following reasons. (1) To provide a standard, safe method of performing all operations, the procedures were written by reactor engineers experienced in supervising the operation of reactors and were reviewed by an organization with over 30 years of reactor operating experience. (2) To have an up-to-date description of operating techniques available at all times for reference and review, it is necessary that the procedures be written

  7. Operating manual for the critical experiments facility

    Energy Technology Data Exchange (ETDEWEB)

    1986-01-01

    The operation of the Critical Experiments Facility (CEF) requires careful attention to procedures in order that all safety precautions are observed. Since an accident could release large amounts of radioactivity, careful operation and strict enforcement of procedures are necessary. To provide for safe operation, detailed procedures have been written for all phases of the operation of this facility. The CEF operating procedures are not to be construed to constitute a part ofthe Technical Specifications. In the event of any discrepancy between the information given herein and the Technical Specifications, limits set forth in the Technical Specifications apply. All normal and most emergency operation conditions are covered by procedures presented in this manual. These procedures are designed to be followed by the operating personnel. Strict adherence to these procedures is expected for the following reasons. (1) To provide a standard, safe method of performing all operations, the procedures were written by reactor engineers experienced in supervising the operation of reactors and were reviewed by an organization with over 30 years of reactor operating experience. (2) To have an up-to-date description of operating techniques available at all times for reference and review, it is necessary that the procedures be written.

  8. InaSAFE applications in disaster preparedness

    Science.gov (United States)

    Pranantyo, Ignatius Ryan; Fadmastuti, Mahardika; Chandra, Fredy

    2015-04-01

    Disaster preparedness activities aim to reduce the impact of disasters by being better prepared to respond when a disaster occurs. In order to better anticipate requirements during a disaster, contingency planning activities can be undertaken prior to a disaster based on a realistic disaster scenario. InaSAFE is a tool that can inform this process. InaSAFE is a free and open source software that estimates the impact to people and infrastructure from potential hazard scenarios. By using InaSAFE, disaster managers can develop scenarios of disaster impacts (people and infrastructures affected) to inform their contingency plan and emergency response operation plan. While InaSAFE provides the software framework exposure data and hazard data are needed as inputs to run this software. Then InaSAFE can be used to forecast the impact of the hazard scenario to the exposure data. InaSAFE outputs include estimates of the number of people, buildings and roads are affected, list of minimum needs (rice and clean water), and response checklist. InaSAFE is developed by Indonesia's National Disaster Management Agency (BNPB) and the Australian Government, through the Australia-Indonesia Facility for Disaster Reduction (AIFDR), in partnership with the World Bank - Global Facility for Disaster Reduction and Recovery (GFDRR). This software has been used in many parts of Indonesia, including Padang, Maumere, Jakarta, and Slamet Mountain for emergency response and contingency planning.

  9. Automatic limit switch system for scintillation device and method of operation

    International Nuclear Information System (INIS)

    Brunnett, C.J.; Ioannou, B.N.

    1976-01-01

    A scintillation scanner is described having an automatic limit switch system for setting the limits of travel of the radiation detection device which is carried by a scanning boom. The automatic limit switch system incorporates position responsive circuitry for developing a signal representative of the position of the boom, reference signal circuitry for developing a signal representative of a selected limit of travel of the boom, and comparator circuitry for comparng these signals in order to control the operation of a boom drive and indexing mechanism. (author)

  10. Seismic qualification of motor operated valves - alternate approach

    International Nuclear Information System (INIS)

    Bruck, P.M.; Eissa, M.A.

    1998-01-01

    This paper presents a potential alternate method for determining operating capacity of motor-operated valves subjected to seismic and other applicable loadings. As a result of programs at nuclear facilities to ensure the operational capability of MOVs (under NRC GL89-10), extensive analytical focus to develop the structural capability of valves has ensued. In the past, seismic qualification of valves typically addressed the strength of the topwork structure to resist inertial loading from excitation of the large valve actuator mass. These evaluations paid little or no consideration to the loading resulting from valve closing forces. The focus of the recent efforts is to develop the maximum operational capability of the valve, in terms of thrust, with consideration of seismic and other services loading as applicable. The alternate method outlined in this paper presents a series of thrust capacity curves, with reduction factors for seismic loading which can be applied and developed to determine safe thrust loadings without performing extensive analytical effort. A similar approach was put forward by the SQUG GIP approach to MOVs to ensure the safe operation of valves based on past earthquake experience. However, the GIP approach cannot be used to determine safe operational loads and thus has limited use in the necessary analysis required for GL89-10 programs at nuclear facilities. (orig.)

  11. Ageing management and knowledge base for safe long-term operation of japanese light water reactors

    International Nuclear Information System (INIS)

    Sekimura, N.

    2008-01-01

    There are 55 operating commercial light water reactor plants (32 BWRs and 23 PWRs) in Japan. Twelve (12) plants have been operating for more than 30 years. Utility companies are required to perform an 'Ageing Management Technical Assessment' be-fore the end of 30 years operation of each plant. The assessments for each plant have been evaluated by the Nuclear and Industry Safety Agency (NISA) of the Ministry of Economy Trade and Industry (WTI) for these 12 plants. The Japan Nuclear Energy Safety Organisation (JNES) has compiled Technical Review Manuals for six major degradation phenomena for the evaluation of Ageing Management Technical Assessment. A 'Road-map for Ageing and Plant Life Management' was established in 2005 by the Special Committee in the Atomic Energy Society of Japan under the commission from the JNES. Within the framework of the road-map, the major research and development fields are divided into the following four categories: 1) engineering information systems; 2) research and development of technologies for inspection, evaluation and repair of the components and materials; 3) development of codes and standards; 4) synthesised maintenance engineering. Continuous revision of the 'Strategy Maps for Ageing Management and Safe Long-term Operation' has been performed under the Coordinating Committee of Ageing Management to promote research and development activities by industries, government and academia, effectively and efficiently. Systematic development of the information basis for database and knowledge-base has been undertaken in addition to the development of codes and standards by academic societies through intensive domestic safety research collaborations and international collaboration. (author)

  12. On-line determination of operating limits incorporating constraint costs and reliability assessment

    International Nuclear Information System (INIS)

    Meisingset, M.; Lovas, G. G.

    1997-01-01

    Problems regarding power system operation following deregulation were discussed. The problems arise as a result of the increased power flow pattern created by deregulation and competitive power markets, resulting in power in excess of N-1, (the capacity of transmission lines available), which in turn creates bottlenecks. In a situation like this, constraint costs and security costs (i.e. the cost of supply interruptions) are incurred as the direct result of the deterministic criteria used in reliability assessment. This paper describes an on-line probabilistic method to determine operating limits based on a trade-off between constraint costs and security costs. The probability of the contingencies depend on the existing weather conditions, which therefore has significant impact on the calculated operating limit. In consequence, the proposed method allows power flow to exceed the N-1 limit during normal weather. Under adverse weather conditions the N-1 criteria should be maintained. 15 refs., 13 figs

  13. How safe is safe enough?

    International Nuclear Information System (INIS)

    Desnoyers, B.; Chanzy, Y.

    2004-01-01

    The IAEA Regulations for the Safe Transport of Radioactive Material, were historically established with the objective to reduce the probability that persons be exposed to unacceptable doses due to normal operation or accident situations during transport of radioactive material. Based on the International Basic Safety Standards for Protection against Ionizing Radiation (BSS), the definition, which was adopted for an unacceptable dose for an accident situation, is the excess of the maximum dose limits permissible in a single year for the occupational exposure of a worker in the BSS. Concerning the severity of accident situations, it has always be clearly stated that the objective of the tests for demonstrating ability to withstand accident conditions of transport was not to cover every accident condition, but solely most of them. The last available evaluations regarding the rate of accidents which are covered by the standardised accident conditions of transport defined in the IAEA Regulations give a range of about 80%, plus or minus 15% which depends on transport mode and studies. Consequently, slight variations in the capabilities of the packages to meet the specified performance would probably not have significant consequences on the protection level in case of accident. In the assessment of the compliance with the regulations, the tendency of experts, taking advantage of the enhanced performances of computer calculation codes, is to ask more and more calculations, with more and more accuracy, leading to more and more restrictions. Consequently, cost and delay are considerably increased without any evidence of an equivalent effect on the level of protection. This paper will initiate a reflection on the general objectives and principles when implementing the Regulations, in such a way that demonstrations remain cost effective, taking into account evolution of the techniques and a high level of safety

  14. Inherently safe in situ uranium recovery

    International Nuclear Information System (INIS)

    Krumhansl, James Lee; Beauheim, Richard Louis; Brady, Patrick Vane; Arnold, Bill Walter; Kanney, Joseph F.; McKenna, Sean Andrew

    2009-01-01

    Expansion of uranium mining in the United States is a concern to some environmental groups and sovereign Native American Nations. An approach which may alleviate some problems is to develop inherently safe in situ uranium recovery ('ISR') technologies. Current ISR technology relies on chemical extraction of trace levels of uranium from aquifers that, once mined, can still contain dissolved uranium and other trace metals that are a health concern. Existing ISR operations are few in number; however, high uranium prices are driving the industry to consider expanding operations nation-wide. Environmental concerns and enforcement of the new 30 ppb uranium drinking water standard may make opening new mining operations more difficult and costly. Here we propose a technological fix: the development of inherently safe in situ recovery (ISISR) methods. The four central features of an ISISR approach are: (1) New 'green' leachants that break down predictably in the subsurface, leaving uranium, and associated trace metals, in an immobile form; (2) Post-leachant uranium/metals-immobilizing washes that provide a backup decontamination process; (3) An optimized well-field design that increases uranium recovery efficiency and minimizes excursions of contaminated water; and (4) A combined hydrologic/geochemical protocol for designing low-cost post-extraction long-term monitoring. ISISR would bring larger amounts of uranium to the surface, leave fewer toxic metals in the aquifer, and cost less to monitor safely - thus providing a 'win-win-win' solution to all stakeholders.

  15. Safe sex

    Science.gov (United States)

    ... sex; Sexually transmitted - safe sex; GC - safe sex; Gonorrhea - safe sex; Herpes - safe sex; HIV - safe sex; ... contact. STIs include: Chlamydia Genital herpes Genital warts Gonorrhea Hepatitis HIV HPV Syphilis STIs are also called ...

  16. Upgraded safety analysis document including operations policies, operational safety limits and policy changes. Revision 2

    International Nuclear Information System (INIS)

    Batchelor, K.

    1996-03-01

    The National Synchrotron Light Source Safety Analysis Reports (1), (2), (3), BNL reports number-sign 51584, number-sign 52205 and number-sign 52205 (addendum) describe the basic Environmental Safety and Health issues associated with the department's operations. They include the operating envelope for the Storage Rings and also the rest of the facility. These documents contain the operational limits as perceived prior or during construction of the facility, much of which still are appropriate for current operations. However, as the machine has matured, the experimental program has grown in size, requiring more supervision in that area. Also, machine studies have either verified or modified knowledge of beam loss modes and/or radiation loss patterns around the facility. This document is written to allow for these changes in procedure or standards resulting from their current mode of operation and shall be used in conjunction with the above reports. These changes have been reviewed by NSLS and BNL ES and H committee and approved by BNL management

  17. A standardized and safe method of sterile field maintenance during intra-operative horizontal plane fluoroscopy

    Directory of Open Access Journals (Sweden)

    Kaska Serge C

    2010-12-01

    Full Text Available Abstract Background Intra-operative fluoroscopy for orthopaedic procedures frequently involves imaging in the horizontal plane, which requires the lower portion of the C-arm (x-ray tube to be rotated from an unsterile zone (beneath the table into the sterile field. To protect the integrity of the sterile field the C-arm must be draped repeatedly throughout the surgical case. The current, un-standardized, practice employs draping procedures which violate the Association of peri-Operative Registered Nurses (AORN Standards and Recommended Practices, waste time and material, and pose an increased risk for surgical site infection. Presentation of the hypothesis Use of a novel sterile C-arm drape (C-armor that maintains the integrity of the sterile field, will improve operating room efficiency and reduce surgical site infection risk factors. This reduction in risk factors may potentially reduce surgical site infections in orthopaedic surgical cases requiring repeated horizontal x-ray imaging. Testing the Hypothesis Savings in time and material and the reduction in surgical site infection risk factors afforded by using C-armor are intuitive to those skilled in the practice of orthopaedic surgery. Testing for a reduction in the number of microorganisms introduced to the surgical site by improved C-arm draping would be challenging due to the multiple confounding factors during a surgical operation. Determination of an absolute reduction in surgical site infections may be possible, but will require accounting for many confounding variables and a large study sample in order to achieve statistical significance. Implications of the Hypothesis Improved intraoperative workflow, healthcare savings and a reduction in surgical site infection risk factors will be achieved by utilizing a standardized and safe method of sterile field maintenance during intra-operative horizontal plane fluoroscopy.

  18. Safe handling of tritium

    International Nuclear Information System (INIS)

    1991-01-01

    The main objective of this publication is to provide practical guidance and recommendations on operational radiation protection aspects related to the safe handling of tritium in laboratories, industrial-scale nuclear facilities such as heavy-water reactors, tritium removal plants and fission fuel reprocessing plants, and facilities for manufacturing commercial tritium-containing devices and radiochemicals. The requirements of nuclear fusion reactors are not addressed specifically, since there is as yet no tritium handling experience with them. However, much of the material covered is expected to be relevant to them as well. Annex III briefly addresses problems in the comparatively small-scale use of tritium at universities, medical research centres and similar establishments. However, the main subject of this publication is the handling of larger quantities of tritium. Operational aspects include designing for tritium safety, safe handling practice, the selection of tritium-compatible materials and equipment, exposure assessment, monitoring, contamination control and the design and use of personal protective equipment. This publication does not address the technologies involved in tritium control and cleanup of effluents, tritium removal, or immobilization and disposal of tritium wastes, nor does it address the environmental behaviour of tritium. Refs, figs and tabs

  19. Evaluation of exposure limits to toxic gases for nuclear reactor control room operators

    International Nuclear Information System (INIS)

    Mahlum, D.D.; Sasser, L.B.

    1991-07-01

    We have evaluated ammonia, chlorine, Halon (actually a generic name for several halogenated hydro-carbons), and sulfur dioxide for their possible effects during an acute two-minute exposure in order to derive recommendations for maximum exposure levels. To perform this evaluation, we conducted a search to find the most pertinent literature regarding toxicity in humans and in experimental animals. Much of the literature is at least a decade old, not an unexpected finding since acute exposures are less often performed now than they were a few years ago. In most cases, the studies did not specifically examine the effects of two-minute exposures; thus, extrapolations had to be made from studies of longer-exposure periods. Whenever possible, we gave the greatest weight to human data, with experimental animal data serving to strengthen the conclusion arrived at from consideration of the human data. Although certain individuals show hypersensitivity to materials like sulfur dioxide, we have not attempted to factor this information into the recommendations. After our evaluation of the data in the literature, we held a small workshop. Major participants in this workshop were three consultants, all of whom were Diplomates of the American Board of Toxicology, and staff from the Nuclear Regulatory Commission. Our preliminary recommendations for two-minute exposure limits and the rationale for them were discussed and consensus reached on final recommendations. These recommendations are: (1) ammonia-300 to 400-ppm; (2) chlorine-30 ppm; (3) Halon 1301-5%; Halon 1211-2%; and (4) sulfur dioxide-100 ppm. Control room operators should be able to tolerate two-minute exposures to these levels, don fresh-air masks, and continue to operate the reactor if the toxic material is eliminated, or safely shut down the reactor if the toxic gas remains. 96 refs., 9 tabs

  20. Heat transfer characteristics and operation limit of pressurized hybrid heat pipe for small modular reactors

    International Nuclear Information System (INIS)

    Kim, Kyung Mo; Bang, In Cheol

    2017-01-01

    Highlights: • Thermal performances and operation limits of hybrid heat pipe were experimentally studied. • Models for predicting the operation limit of the hybrid heat pipe was developed. • Non-condensable gas affected heat transfer characteristics of the hybrid heat pipe. - Abstract: In this paper, a hybrid heat pipe is proposed for use in advanced nuclear power plants as a passive heat transfer device. The hybrid heat pipe combines the functions of a heat pipe and a control rod to simultaneously remove the decay heat generated from the core and shutdown the reactor under accident conditions. Thus, the hybrid heat pipe contains a neutron absorber in the evaporator section, which corresponds to the core of the reactor pressure vessel. The presence of the neutron absorber material leads to differences in the heated diameter and hydraulic diameter of the heat pipe. The cross-sectional areas of the vapor paths through the evaporator, adiabatic, and condenser sections are also different. The hybrid heat pipe must operate in a high-temperature, high-pressure environment to remove the decay heat. In other words, the operating pressure must be higher than those of the commercially available thermosyphons. Hence, the thermal performances, including operation limit of the hybrid heat pipe, were experimentally studied in the operating pressure range of 0.2–20 bar. The operating pressure of the hybrid heat pipe was controlled by charging the non-condensable gas which is unused method to achieve the high saturation pressure in conventional thermosyphons. The effect of operating pressure on evaporation heat transfer was negligible, while condensation heat transfer was affected by the amount of non-condensable gas in the test section. The operation limit of the hybrid heat pipe increased with the operating pressure. Maximum heat removal capacity of the hybrid heat pipe was up to 6 kW which is meaningful value as a passive decay heat removal device in the nuclear power

  1. 40 CFR Table 3 to Subpart Eeee of... - Operating Limits-High Throughput Transfer Racks

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Operating Limits-High Throughput Transfer Racks 3 Table 3 to Subpart EEEE of Part 63 Protection of Environment ENVIRONMENTAL PROTECTION... Throughput Transfer Racks As stated in § 63.2346(e), you must comply with the operating limits for existing...

  2. Operating limit study for the proposed solid waste landfill at Paducah Gaseous Diffusion Plant

    Energy Technology Data Exchange (ETDEWEB)

    Lee, D.W.; Wang, J.C.; Kocher, D.C.

    1995-06-01

    A proposed solid waste landfill at Paducah Gaseous Diffusion Plant (PGDP) would accept wastes generated during normal operations that are identified as non-radioactive. These wastes may include small amounts of radioactive material from incidental contamination during plant operations. A site-specific analysis of the new solid waste landfill is presented to determine a proposed operating limit that will allow for waste disposal operations to occur such that protection of public health and the environment from the presence of incidentally contaminated waste materials can be assured. Performance objectives for disposal were defined from existing regulatory guidance to establish reasonable dose limits for protection of public health and the environment. Waste concentration limits were determined consistent with these performance objectives for the protection of off-site individuals and inadvertent intruders who might be directly exposed to disposed wastes. Exposures of off-site individuals were estimated using a conservative, site-specific model of the groundwater transport of contamination from the wastes. Direct intrusion was analyzed using an agricultural homesteader scenario. The most limiting concentrations from direct intrusion or groundwater transport were used to establish the concentration limits for radionuclides likely to be present in PGDP wastes.

  3. Operating limit study for the proposed solid waste landfill at Paducah Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    Lee, D.W.; Wang, J.C.; Kocher, D.C.

    1995-06-01

    A proposed solid waste landfill at Paducah Gaseous Diffusion Plant (PGDP) would accept wastes generated during normal operations that are identified as non-radioactive. These wastes may include small amounts of radioactive material from incidental contamination during plant operations. A site-specific analysis of the new solid waste landfill is presented to determine a proposed operating limit that will allow for waste disposal operations to occur such that protection of public health and the environment from the presence of incidentally contaminated waste materials can be assured. Performance objectives for disposal were defined from existing regulatory guidance to establish reasonable dose limits for protection of public health and the environment. Waste concentration limits were determined consistent with these performance objectives for the protection of off-site individuals and inadvertent intruders who might be directly exposed to disposed wastes. Exposures of off-site individuals were estimated using a conservative, site-specific model of the groundwater transport of contamination from the wastes. Direct intrusion was analyzed using an agricultural homesteader scenario. The most limiting concentrations from direct intrusion or groundwater transport were used to establish the concentration limits for radionuclides likely to be present in PGDP wastes

  4. 40 CFR Table 1 to Subpart IIIi of... - Operating Limits for Capture Systems and Add-On Control Devices

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Operating Limits for Capture Systems... 63—Operating Limits for Capture Systems and Add-On Control Devices If you are required to comply with operating limits by § 63.3093, you must comply with the applicable operating limits in the following table...

  5. Assessment of concentration limit for the safe disposal of very low level wastes

    International Nuclear Information System (INIS)

    Nam, Yun Seog

    2008-02-01

    The large amounts of radionuclides are generated from the decommissioning of nuclear facilities (included the nuclear power plant). Because of this, countries or agencies using the nuclear power are one of considering issues for the effective disposal. Among decommissioning wastes, wastes have no or very limited radioactivity are disposed of in conventional landfill or recycled thought approval from regulatory control. And wastes like LILW (Low and Intermediate Level Wastes) or HLW (High Level Wastes) are sent the repository or the interim storage facilities. In order to solve the space problem of the LILW repository and reduce disposal costs, some LLW which are relatively lower than other LLW are classified as VLLW (Very Low Level Wastes). IAEA is added to the VLLW category of the radioactive waste classification and some countries are operating a VLLW disposal facility or will be operating. In this study, the VLLW acceptance criteria of each radionuclide are derived by considering the inadvertent human intrusion scenario applying to a study on the near-surface disposal (LILW). The effect of important parameter, especially, waste isolation period, dilution factor and food consumption rate, is considered. It is concluded that the concentration limits of radionuclides considering in this study are evaluated approximately between 1 and 100 Bq/g. These values are similar to the case of France and Spain and the IAEA's predicted values. Based on this study, acceptance criteria of VLLW disposal facilities are suggested. And this study is contributed to the public relations for the safety of the VLLW disposal facility

  6. A knowledge-based operator advisor system for integration of fault detection, control, and diagnosis to enhance the safe and reliable operation of nuclear power plants

    International Nuclear Information System (INIS)

    Bhatnagar, R.

    1989-01-01

    A Knowledged-Based Operator Advisor System has been developed for enhancing the complex task of maintaining safe and reliable operation of nuclear power plants. The operator's activities have been organized into the four tasks of data interpretation for abstracting high level information from sensor data, plant state monitoring for identification of faults, plan execution for controlling the faults, and diagnosis for determination of root causes of faults. The Operator Advisor System is capable of identifying the abnormal functioning of the plant in terms of: (1) deviations from normality, (2) pre-enumerated abnormal events, and (3) safety threats. The classification of abnormal functioning into the three categories of deviations from normality, abnormal events, and safety threats allows the detection of faults at three levels of: (1) developing faults, (2) developed faults, and (3) safety threatening faults. After the identification of abnormal functioning the system will identify the procedures to be executed to mitigate the consequences of abnormal functioning and will help the operator by displaying the procedure steps and monitoring the success of actions taken. The system also is capable of diagnosing the root causes of abnormal functioning. The identification, and diagnosis of root causes of abnormal functioning are done in parallel to the task of procedure execution, allowing the detection of more critical safety threats while executing procedures to control abnormal events

  7. Global opportunities in land and water use while staying within the safe (and just) operating space: quantifications of interactions and tradeoffs

    Science.gov (United States)

    Gerten, Dieter; Jägermeyr, Jonas; Heck, Vera

    2016-04-01

    Staying within the safe and just operating space as defined by multiple planetary boundaries will be a major challenge especially in view of anticipated future increases in food demand, the potential need for balancing climate change (e.g. through terrestrial carbon dioxide removal) and its impacts, and the water and land demand associated with these goals and measures. This presentation will show simulation results from a comprehensive model-based study on the global potentials of diverse crop management options considered as opportunities to stay within the planetary boundaries for human freshwater use and land-system change. The quantified on-farm options include rainwater harvesting, soil conservation and more efficient irrigation, all of which are designed to use neither more water nor more land for agriculture than is presently the case. Results show that irrigation efficiency improvements could save substantial amounts of water in many river basins (globally 48% of non-productive water consumption in an ambitious scenario), and if rerouted to irrigate neighbouring rainfed systems, could at the same time boost kilocalorie production by 26% globally. Low-tech solutions for small-scale farmers on water-limited croplands show the potential to increase rainfed yields to a similar extent. In combination, such ambitious yet achievable integrated water management strategies could increase global kcal production by 41% and close the water-related yield gap by 62%. Global climate change would have adverse effects on crop yields in many regions, but the improvements in water management quantified here could buffer such effects to a significant degree. Thus, a substantial amount of anticipated future needs for food production could be fulfilled without further approaching / transgressing planetary boundaries. In addition, it will be shown how large-scale biomass plantations for the purpose of terrestrial CO2 removal (climate engineering, potentially implemented should

  8. Worcester 1 Inch Solenoid-Actuated Gas-Operated VPS System Ball Valve

    International Nuclear Information System (INIS)

    VAN KATWIJK, C.

    2000-01-01

    1 inch Gas-operated full-port ball valve incorporates a solenoid and limit switches as integral parts of the actuator. The valve is normally open and fails safe to the closed position. The associated valve position switch is class GS

  9. Safe specification of operator precedence rules

    NARCIS (Netherlands)

    Afroozeh, A.; Brand, van den M.G.J.; Johnstone, A.; Scott, E.; Vinju, J.J.; Erwig, M.; Paige, R.F.; Van Wyk, E.

    2013-01-01

    In this paper we present an approach to specifying operator precedence based on declarative disambiguation constructs and an implementation mechanism based on grammar rewriting. We identify a problem with existing generalized context-free parsing and disambiguation technology: generating a correct

  10. Iterative co-creation for improved hand hygiene and aseptic techniques in the operating room: experiences from the safe hands study.

    Science.gov (United States)

    Erichsen Andersson, Annette; Frödin, Maria; Dellenborg, Lisen; Wallin, Lars; Hök, Jesper; Gillespie, Brigid M; Wikström, Ewa

    2018-01-04

    Hand hygiene and aseptic techniques are essential preventives in combating hospital-acquired infections. However, implementation of these strategies in the operating room remains suboptimal. There is a paucity of intervention studies providing detailed information on effective methods for change. This study aimed to evaluate the process of implementing a theory-driven knowledge translation program for improved use of hand hygiene and aseptic techniques in the operating room. The study was set in an operating department of a university hospital. The intervention was underpinned by theories on organizational learning, culture and person centeredness. Qualitative process data were collected via participant observations and analyzed using a thematic approach. Doubts that hand-hygiene practices are effective in preventing hospital acquired infections, strong boundaries and distrust between professional groups and a lack of psychological safety were identified as barriers towards change. Facilitated interprofessional dialogue and learning in "safe spaces" worked as mechanisms for motivation and engagement. Allowing for the free expression of different opinions, doubts and viewing resistance as a natural part of any change was effective in engaging all professional categories in co-creation of clinical relevant solutions to improve hand hygiene. Enabling nurses and physicians to think and talk differently about hospital acquired infections and hand hygiene requires a shift from the concept of one-way directed compliance towards change and learning as the result of a participatory and meaning-making process. The present study is a part of the Safe Hands project, and is registered with ClinicalTrials.gov (ID: NCT02983136 ). Date of registration 2016/11/28, retrospectively registered.

  11. Power-limited low-thrust trajectory optimization with operation point detection

    Science.gov (United States)

    Chi, Zhemin; Li, Haiyang; Jiang, Fanghua; Li, Junfeng

    2018-06-01

    The power-limited solar electric propulsion system is considered more practical in mission design. An accurate mathematical model of the propulsion system, based on experimental data of the power generation system, is used in this paper. An indirect method is used to deal with the time-optimal and fuel-optimal control problems, in which the solar electric propulsion system is described using a finite number of operation points, which are characterized by different pairs of thruster input power. In order to guarantee the integral accuracy for the discrete power-limited problem, a power operation detection technique is embedded in the fourth-order Runge-Kutta algorithm with fixed step. Moreover, the logarithmic homotopy method and normalization technique are employed to overcome the difficulties caused by using indirect methods. Three numerical simulations with actual propulsion systems are given to substantiate the feasibility and efficiency of the proposed method.

  12. 25 CFR 47.7 - What are the expenditure limitations for Bureau-operated schools?

    Science.gov (United States)

    2010-04-01

    ... schools? 47.7 Section 47.7 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR EDUCATION UNIFORM DIRECT FUNDING AND SUPPORT FOR BUREAU-OPERATED SCHOOLS § 47.7 What are the expenditure limitations for Bureau-operated schools? Each Bureau-operated school must spend all allotted funds in accordance with...

  13. Beam interlock system and safe machine parameters system 2010 and beyond

    CERN Document Server

    Todd, B

    2010-01-01

    The Beam Interlock System (BIS) and Safe Machine Parameters (SMP) system are central to the protection of the Large Hadron Collider (LHC) machine. The BIS has been critical for the safe operation of LHC from the first day of operation. It has been installed and commissioned, only minor enhancements are required in order to accommodate all future LHC machine protection requirements. At reduced intensity, the SMP system is less critical for LHC operation. As such, the current system satisfies the 2010 operational requirements. Further developments are required, both at the SMP Controller level, and at the system level, in order to accommodate the requirements of the LHC beyond 2010.

  14. Fail-safe logic elements for use with reactor safety systems

    International Nuclear Information System (INIS)

    Bobis, J.P.; McDowell, W.P.

    1976-01-01

    A complete fail-safe trip circuit is described which utilizes fail-safe logic elements. The logic elements used are analog multipliers and active bandpass filter networks. These elements perform Boolean operations on a set of AC signals from the output of a reactor safety-channel trip comparator

  15. Assesment of safe discharge limits in the nuclear industry

    International Nuclear Information System (INIS)

    Van As, D.

    1984-01-01

    Routine releases from the nuclear industry to the environment are controlled by three principles, viz. that the practice creating the effluents should be kept as low as reasonably achievable, and radiation dose limits should not be exceeded. In the nuclear industry, the discharge of radioactive effluent is controlled by a system of dose limitation. The application of this system to conventional effluents require: i) a quantitative relationship between intake and effect so as to establish intake limits; ii) environmental models that will allow calculation of the relationship between discharge and intake; iii) a measure of the total detriment due to the discharge. For such a system discharge limits can be established for the desired level of risk (safety)

  16. New maintenance strategy of Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant for effective ageing management and safe long-term operation

    International Nuclear Information System (INIS)

    Inagaki, Takeyuki; Yamashita, Norimichi

    2009-01-01

    Fukushima Dai-ichi Nuclear Power Plant is the oldest among three nuclear power plants owned and operated by Tokyo Electric Power Company, which consists of six boiling water reactor units. The commercial operation of Unit 1 was commenced in 1971 (37 years old) and Unit 6 in 1978 (29 years old). Currently ageing degradations of systems, structures and components are managed through maintenance programs, component replacement/refurbishment programs and long-term maintenance plans. The long-term maintenance plans are established through ageing management component replacement/refurbishment programs reviews performed before the 30th year of operation and they are for safe and reliable operation after 30 years (long-term operation). However the past maintenance actions and past component replacement/refurbishment programs were not always proactive and past operational experience and maintenance practices suggest that effective/proactive ageing management programs be introduced in earlier stage of the plant operation. In this circumstance, Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant are setting up a new maintenance strategy that includes 1) improving the normal maintenance programs by using ageing degradation data, 2) effective use of information on internal/external operational experience and maintenance practices related to ageing, and 3) proactive component/equipment refurbishment programs during a refreshment outage for safe and reliable long-term operation. To accomplish the goal of this strategy, strengthening engineering capability of plant staff members is a crucial required for the plant. The objective of this paper is to briefly explain main results ageing management reviews, past and current significant ageing issues and management programs against them, and the new maintenance strategy established by Tokyo Electric Power Company and Fukushima Dai-ichi Nuclear Power Plant. (author)

  17. 78 FR 57319 - Children's Online Privacy Protection Rule Safe Harbor Proposed Self-Regulatory Guidelines...

    Science.gov (United States)

    2013-09-18

    ...-AB20 Children's Online Privacy Protection Rule Safe Harbor Proposed Self-Regulatory Guidelines; kidSAFE... proposed self-regulatory guidelines submitted by the kidSAFE Seal Program (``kidSAFE''), owned and operated... enabling industry groups or others to submit to the Commission for approval self-regulatory guidelines that...

  18. Digital computer operation of a nuclear reactor

    International Nuclear Information System (INIS)

    Colley, R.W.

    1984-01-01

    A method is described for the safe operation of a complex system such as a nuclear reactor using a digital computer. The computer is supplied with a data base containing a list of the safe state of the reactor and a list of operating instructions for achieving a safe state when the actual state of the reactor does not correspond to a listed safe state, the computer selects operating instructions to return the reactor to a safe state

  19. Working safely with ionising radiation

    International Nuclear Information System (INIS)

    McDowell, D.J.

    1990-01-01

    A small leaflet provides information on working safely with ionizing radiation. Topics covered include the types of radiation, radiological units, external radiation, contamination and internal radiation, methods of protection form radiation, radiation monitors, protective clothing for contamination, personal dosemeters, radiation dose limits for classified workers and finally the Ionising Radiations Regulations 1985. (UK)

  20. Operational characteristics of nuclear power plants - modelling of operational safety

    International Nuclear Information System (INIS)

    Studovic, M.

    1984-01-01

    By operational experience of nuclear power plants and realize dlevel of availability of plant, systems and componenst reliabiliuty, operational safety and public protection, as a source on nature of distrurbances in power plant systems and lessons drawn by the TMI-2, in th epaper are discussed: examination of design safety for ultimate ensuring of safe operational conditions of the nuclear power plant; significance of the adequate action for keeping proess parameters in prescribed limits and reactor cooling rquirements; developed systems for measurements detection and monitoring all critical parameters in the nuclear steam supply system; contents of theoretical investigation and mathematical modeling of the physical phenomena and process in nuclear power plant system and components as software, supporting for ensuring of operational safety and new access in staff education process; program and progress of the investigation of some physical phenomena and mathematical modeling of nuclear plant transients, prepared at faculty of mechanical Engineering in Belgrade. (author)

  1. Multi-objective design and operation of Solid Oxide Fuel Cell (SOFC) Triple Combined-cycle Power Generation systems: Integrating energy efficiency and operational safety

    International Nuclear Information System (INIS)

    Sharifzadeh, Mahdi; Meghdari, Mojtaba; Rashtchian, Davood

    2017-01-01

    Highlights: • Integrating Solid Oxide Fuel Cells with thermal power plants enhance overall energy efficiency. • However, the high degree of process integration in hybrid power plants limits the operating window. • Multi-objective optimization was applied for integrated design and operation. • The Pareto optimal solutions demonstrated strong trade-off between energy efficiency and operational safety. - Abstract: Energy efficiency is one of the main pathways for energy security and environmental protection. In fact, the International Energy Agency asserts that without energy efficiency, 70% of targeted emission reductions are not achievable. Despite this clarity, enhancing the energy efficiency introduce significant challenge toward process operation. The reason is that the methods applied for energy-saving pose the process operation at the intersection of safety constraints. The present research aims at uncovering the trade-off between safe operation and energy efficiency; an optimization framework is developed that ensures process safety and simultaneously optimizes energy-efficiency, quantified in economic terms. The developed optimization framework is demonstrated for a solid oxide fuel cell (SOFC) power generation system. The significance of this industrial application is that SOFC power plants apply a highly degree of process integration resulting in very narrow operating windows. However, they are subject to significant uncertainties in power demand. The results demonstrate a strong trade-off between the competing objectives. It was observed that highly energy-efficient designs feature a very narrow operating window and limited flexibility. For instance, expanding the safe operating window by 100% will incur almost 47% more annualized costs. Establishing such a trade-off is essential for realizing energy-saving.

  2. 40 CFR Table 2 to Subpart Ddddd of... - Operating Limits for Boilers and Process Heaters With Particulate Matter Emission Limits

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 13 2010-07-01 2010-07-01 false Operating Limits for Boilers and Process Heaters With Particulate Matter Emission Limits 2 Table 2 to Subpart DDDDD of Part 63 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) NATIONAL EMISSION...

  3. UAV Research at NASA Langley: Towards Safe, Reliable, and Autonomous Operations

    Science.gov (United States)

    Davila, Carlos G.

    2016-01-01

    Unmanned Aerial Vehicles (UAV) are fundamental components in several aspects of research at NASA Langley, such as flight dynamics, mission-driven airframe design, airspace integration demonstrations, atmospheric science projects, and more. In particular, NASA Langley Research Center (Langley) is using UAVs to develop and demonstrate innovative capabilities that meet the autonomy and robotics challenges that are anticipated in science, space exploration, and aeronautics. These capabilities will enable new NASA missions such as asteroid rendezvous and retrieval (ARRM), Mars exploration, in-situ resource utilization (ISRU), pollution measurements in historically inaccessible areas, and the integration of UAVs into our everyday lives all missions of increasing complexity, distance, pace, and/or accessibility. Building on decades of NASA experience and success in the design, fabrication, and integration of robust and reliable automated systems for space and aeronautics, Langley Autonomy Incubator seeks to bridge the gap between automation and autonomy by enabling safe autonomous operations via onboard sensing and perception systems in both data-rich and data-deprived environments. The Autonomy Incubator is focused on the challenge of mobility and manipulation in dynamic and unstructured environments by integrating technologies such as computer vision, visual odometry, real-time mapping, path planning, object detection and avoidance, object classification, adaptive control, sensor fusion, machine learning, and natural human-machine teaming. These technologies are implemented in an architectural framework developed in-house for easy integration and interoperability of cutting-edge hardware and software.

  4. 40 CFR Table 4 to Subpart Ddddd of... - Operating Limits for Boilers and Process Heaters With Hydrogen Chloride Emission Limits

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 13 2010-07-01 2010-07-01 false Operating Limits for Boilers and Process Heaters With Hydrogen Chloride Emission Limits 4 Table 4 to Subpart DDDDD of Part 63 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) NATIONAL EMISSION STANDARDS...

  5. 40 CFR Table 2 of Subpart Aaaaaaa... - Emission Limits for Asphalt Roofing Manufacturing (Coating) Operations

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 14 2010-07-01 2010-07-01 false Emission Limits for Asphalt Roofing Manufacturing (Coating) Operations 2 Table 2 of Subpart AAAAAAA of Part 63 Protection of Environment... AAAAAAA of Part 63—Emission Limits for Asphalt Roofing Manufacturing (Coating) Operations For * * * 1...

  6. The Resident-Run Minor Surgery Clinic: A Pilot Study to Safely Increase Operative Autonomy.

    Science.gov (United States)

    Wojcik, Brandon M; Fong, Zhi Ven; Patel, Madhukar S; Chang, David C; Petrusa, Emil; Mullen, John T; Phitayakorn, Roy

    increased operative autonomy as the greatest strength. Implementation of a resident-run minor surgery clinic is a safe and effective method to increase trainee operative autonomy. The rotation is well suited for mid-level residents, as it provides an opportunity for realistic self-evaluation and focused learning that may enhance their operative experience during senior level rotations. Copyright © 2016 Association of Program Directors in Surgery. Published by Elsevier Inc. All rights reserved.

  7. Safeguards Automated Facility Evaluation (SAFE) methodology

    International Nuclear Information System (INIS)

    Chapman, L.D.; Grady, L.M.; Bennett, H.A.; Sasser, D.W.; Engi, D.

    1978-08-01

    An automated approach to facility safeguards effectiveness evaluation has been developed. This automated process, called Safeguards Automated Facility Evaluation (SAFE), consists of a collection of a continuous stream of operational modules for facility characterization, the selection of critical paths, and the evaluation of safeguards effectiveness along these paths. The technique has been implemented on an interactive computer time-sharing system and makes use of computer graphics for the processing and presentation of information. Using this technique, a comprehensive evaluation of a safeguards system can be provided by systematically varying the parameters that characterize the physical protection components of a facility to reflect the perceived adversary attributes and strategy, environmental conditions, and site operational conditions. The SAFE procedure has broad applications in the nuclear facility safeguards field as well as in the security field in general. Any fixed facility containing valuable materials or components to be protected from theft or sabotage could be analyzed using this same automated evaluation technique

  8. EU-US transport task force workshop on transport in fusion plasmas: transport near operational limits

    International Nuclear Information System (INIS)

    Connor, J W; Garbet, X; Giannone, L; Greenwald, M; Hidalgo, C; Loarte, A; Mantica, P

    2003-01-01

    This conference report summarizes the contributions to, and discussions at, the 9th EU-US transport task force workshop on 'transport in fusion plasmas: transport near operational limits', held in Cordoba, Spain, during 9-12 September 2002. The workshop was organized under three main headings: edge localized mode physics and confinement, profile dynamics and confinement and confinement near operational limits: density and beta limits; this report follows the same structure

  9. Guidelines for safe process operations and maintenance

    CERN Document Server

    2010-01-01

    First-line managers have to maintain the integrity of facilities, control manufacturing processes, and handle unusual or emergency situations, as well as respond to the pressures of production demand. On a daily basis, they are closest to the operating personnel who may be injured by a process accident, and they are in the best position to spot problem conditions and to act to contain them. This book offers these managers ""how-to"" information on process safety management program execution in the operations and maintenance departments, recommending technical and administrative process safety

  10. 40 CFR 60.2215 - What else must I report if I have a deviation from the operating limits or the emission limitations?

    Science.gov (United States)

    2010-07-01

    ... performance test was conducted that deviated from any emission limitation. (b) The deviation report must be... deviation from the operating limits or the emission limitations? 60.2215 Section 60.2215 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) STANDARDS OF PERFORMANCE FOR...

  11. 40 CFR 60.2957 - What else must I report if I have a deviation from the operating limits or the emission limitations?

    Science.gov (United States)

    2010-07-01

    ..., or if a performance test was conducted that showed a deviation from any emission limitation. (b) The... deviation from the operating limits or the emission limitations? 60.2957 Section 60.2957 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) STANDARDS OF PERFORMANCE FOR...

  12. Providing safe drinking water to 1.2 billion unserved people

    Energy Technology Data Exchange (ETDEWEB)

    Gadgil, Ashok J.; Derby, Elisabeth A.

    2003-06-01

    Despite substantial advances in the past 100 years in public health, technology and medicine, 20% of the world population, mostly comprised of the poor population segments in developing countries (DCs), still does not have access to safe drinking water. To reach the United Nations (UN) Millennium Goal of halving the number of people without access to safe water by 2015, the global community will need to provide an additional one billion urban residents and 600 million rural residents with safe water within the next twelve years. This paper examines current water treatment measures and implementation methods for delivery of safe drinking water, and offers suggestions for making progress towards the goal of providing a timely and equitable solution for safe water provision. For water treatment, based on the serious limitations of boiling water and chlorination, we suggest an approach based on filtration coupled with ultraviolet (UV) disinfection, combined with public education. Additionally, owing to the capacity limitations for non-governmental organizations (NGOs) to take on this task primarily on their own, we suggest a strategy based on financially sustainable models that include the private sector as well as NGOs.

  13. General aviation accidents related to exceedance of airplane weight/center of gravity limits.

    Science.gov (United States)

    Boyd, Douglas D

    2016-06-01

    Obesity, affects a third of the US population and its corollary occupant weight adversely impacts safe flight operations. Increased aircraft weight results in longer takeoff/landing distances, degraded climb gradients and airframe failure may occur in turbulence. In this study, the rate, temporal changes, and lethality of accidents in piston-powered, general aviation aircraft related to exceeding the maximum aircraft weight/center of gravity (CG) limits were determined. Nation-wide person body mass were from the National Health and Nutrition Examination Survey. The NTSB database was used to identify accidents related to operation of aircraft outside of their weight/CG envelope. Statistical analyses employed T-tests, proportion tests and a Poisson distribution. While the average body mass climbed steadily (p<0.001) between 1999 and 2014 the rate of accidents related to exceedance of the weight/CG limits did not change (p=0.072). However, 57% were fatal, higher (p<0.001) than the 21% for mishaps attributed to other causes/factors. The majority (77%) of accidents were due to an overloaded aircraft operating within its CG limits. As to the phase of flight, accidents during takeoff and those occurring enroute carried the lowest (50%) and highest (85%) proportion of fatal accidents respectively. While the rate of general aviation accidents related to operating an aircraft outside of its weight/CG envelope has not increased over the past 15 years, these types of accidents carry a high risk of fatality. Airmen should be educated as to such risks and to dispel the notion held by some that flights may be safely conducted with an overloaded aircraft within its CG limits. Copyright © 2016 Elsevier Ltd. All rights reserved.

  14. 40 CFR Table 3 to Subpart Ddddd of... - Operating Limits for Boilers and Process Heaters With Mercury Emission Limits and Boilers and...

    Science.gov (United States)

    2010-07-01

    ... operating limits: If you demonstrate compliance with applicable mercury and/or total selected metals... applicable emission limits for mercury and/or total selected metals. 2. Fabric filter control a. Install and... applicable emission limits for mercury and/or total selected metals. 4. Dry scrubber or carbon injection...

  15. The safe use of radiation sources

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    As a means of promoting safety in the use of radiation sources, as well as encouraging consistency in regulatory control, the IAEA has from time to time organized training courses with the co-operation of Member State governments and organizations, to inform individuals from developing countries with appropriate responsibilities on the provisions for the safe use and regulation of radiation sources. Three such courses on the safe use of radiation sources have been held in both the USA, with the co-operation of the United States Government, and in Dublin, Ireland, with the co-operation of the Irish Government. The Training Course on the Safe Use and Regulation of Radiation Sources has been successfully given to over 77 participants from over 30 countries during the last years. The course is aimed at providing a basis of radiation protection knowledge in all aspects of the uses of radiation and of radiation sources that are used today. It is the intention of this course to provide a systematic enhancement of radioisotope safety in countries with developing radiological programmes through a core group of national authorities. The IAEA's training programmes provide an excellent opportunity for direct contact with lecturers that have extensive experience in resolving issues faced by developing countries and in providing guidance documents useful in addressing their problems. This document uses this collective experience and provides valuable technical information regarding the safety aspects of the uses not only of sealed and unsealed sources of radiation, but also for those machines that produce ionizing radiation. The first of these training courses, 'Safety and Regulation of Unsealed Sources' was held in Dublin, Ireland, June through July 1989 with the co-operation of the Nuclear Energy Board and Trinity College. This was an interregional training course, the participants came from all over the world. The second and third interregional courses, 'Safety and Regulation

  16. The safe use of radiation sources

    International Nuclear Information System (INIS)

    1995-01-01

    As a means of promoting safety in the use of radiation sources, as well as encouraging consistency in regulatory control, the IAEA has from time to time organized training courses with the co-operation of Member State governments and organizations, to inform individuals from developing countries with appropriate responsibilities on the provisions for the safe use and regulation of radiation sources. Three such courses on the safe use of radiation sources have been held in both the USA, with the co-operation of the United States Government, and in Dublin, Ireland, with the co-operation of the Irish Government. The Training Course on the Safe Use and Regulation of Radiation Sources has been successfully given to over 77 participants from over 30 countries during the last years. The course is aimed at providing a basis of radiation protection knowledge in all aspects of the uses of radiation and of radiation sources that are used today. It is the intention of this course to provide a systematic enhancement of radioisotope safety in countries with developing radiological programmes through a core group of national authorities. The IAEA's training programmes provide an excellent opportunity for direct contact with lecturers that have extensive experience in resolving issues faced by developing countries and in providing guidance documents useful in addressing their problems. This document uses this collective experience and provides valuable technical information regarding the safety aspects of the uses not only of sealed and unsealed sources of radiation, but also for those machines that produce ionizing radiation. The first of these training courses, 'Safety and Regulation of Unsealed Sources' was held in Dublin, Ireland, June through July 1989 with the co-operation of the Nuclear Energy Board and Trinity College. This was an interregional training course, the participants came from all over the world. The second and third interregional courses, 'Safety and Regulation

  17. Role and Responsibilities of the Operator

    International Nuclear Information System (INIS)

    Fox, M.; Bacon, A.

    2016-01-01

    As the world leader in the maritime transport of radioactive material (RAM) International Nuclear Service (INS) and its subsidiary, Pacific Nuclear Transport Limited (PNTL) have pioneered the standards for safe and secure transport operations. This paper will highlight these standards from an operator's perspective and provide an overview of how the company would respond to a safety or security related incident. In matching these standards against the national and international maritime regulations, INS will continue to lead the way on the worldwide transport of RAM thus supporting the nuclear fuel cycle and overall global threat reduction. (author)

  18. Safe operation and maintenance of research reactor

    International Nuclear Information System (INIS)

    Munsorn, S.

    1999-01-01

    The first Thai Research Reactor (TRR-1) was established in 1961 at the Office of Atomic Energy for Peace (OAEP), Bangkok. The reactor was light water moderated and cooled, using HEU plate-type with U 3 O 8 - Al fuel meat and swimming pool type. The reactor went first critical on October 27, 1962 and had been licensed to operate at 1 MW (thermal). On June 30, 1975 the reactor was shutdown for modification and the core and control system was disassemble and replaced by that of TRIGA Mark III type while the pool cooling system, irradiation facilities and other were kept. Thus the name TRR-1/M1' has been designed due to this modification the fuel has been changed from HEU plate type to Uranium Zirconium Hydride (UZrH) Low Enrichment Uranium (LEU) which include 4 Fuel Follower Control Rods and 1 Air Follower Control Rod. The TRR-1/M1 went critical on November 7, 1977 and the purpose of the operation are training, isotope production and research. Nowadays the TRR-1/M1 has been operated with core loading No.12 which released power of 1,056 MWD. (as of October 1998). The TRR-1/M1 has been operated at the power of 1.2 MW, three days a week with 34 hours per week, Shut-down on Monday for weekly maintenance and Tuesday for special experiment. The everage energy released is about 40.8 MW-hour per week. Every year, the TRR-1/M1 is shut-down about 2 months between February to March for yearly maintenance. (author)

  19. Safe operation and maintenance of research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Munsorn, S. [Reactor Operation Division, Office of Atomic Energy for Peace, Chatuchak, Bangkok (Thailand)

    1999-10-01

    The first Thai Research Reactor (TRR-1) was established in 1961 at the Office of Atomic Energy for Peace (OAEP), Bangkok. The reactor was light water moderated and cooled, using HEU plate-type with U{sub 3}O{sub 8}- Al fuel meat and swimming pool type. The reactor went first critical on October 27, 1962 and had been licensed to operate at 1 MW (thermal). On June 30, 1975 the reactor was shutdown for modification and the core and control system was disassemble and replaced by that of TRIGA Mark III type while the pool cooling system, irradiation facilities and other were kept. Thus the name TRR-1/M1' has been designed due to this modification the fuel has been changed from HEU plate type to Uranium Zirconium Hydride (UZrH) Low Enrichment Uranium (LEU) which include 4 Fuel Follower Control Rods and 1 Air Follower Control Rod. The TRR-1/M1 went critical on November 7, 1977 and the purpose of the operation are training, isotope production and research. Nowadays the TRR-1/M1 has been operated with core loading No.12 which released power of 1,056 MWD. (as of October 1998). The TRR-1/M1 has been operated at the power of 1.2 MW, three days a week with 34 hours per week, Shut-down on Monday for weekly maintenance and Tuesday for special experiment. The everage energy released is about 40.8 MW-hour per week. Every year, the TRR-1/M1 is shut-down about 2 months between February to March for yearly maintenance. (author)

  20. Canadian East Coast offshore petroleum industry safe lifting practices respecting offshore pedestal cranes, offshore containers, loose gear, other lifting devices, and operational best practices : standard practices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-11-15

    This document was developed by a working group with representatives from the petroleum industry, the Offshore Petroleum Boards and Certifying Authorities. It outlines industry best practices for operators responsible for the management, planning and execution of offshore lifting operations. Its purpose is to assist in the interpretation of applicable legislation and standards. Considered within the practice are safe design requirements, manufacture, certification, testing, maintenance and inspection requirements for pedestal cranes, offshore containers, loose gear and lifting devices. Operational best practices for lifting operations are also included along with a section that identifies additional requirements for personnel lifting operations, including personnel transfers by crane and man-riding operations. 82 refs., 2 tabs., 4 figs., 3 appendices.

  1. Operating limits for subassembly deformation in EBR-II

    International Nuclear Information System (INIS)

    Bottcher, J.H.

    1977-01-01

    The deformation of a subassembly in response to the core environment is frequently the life limiting factor for that component in an LMFBR. Deformation can occur as diametral and axial growth or bowing of the subassembly. Such deformation has caused several handling problems in both the core and the storage basket of EBR-II and may also have contributed to reactivity anomalies during reactor operation. These problems generally affect plant availability but the reactivity anomalies could lead to a potential safety hazard. Because of these effects the deformation mechanisms must be understood and modeled. Diametral and axial growth of subassembly ducts in EBR-II is due to swelling and creep and is a function of temperature, neutron fluence and stress. The source of stress in a duct is the hydraulic pressure difference across the wall. By coupling the calculated subassembly growth rate to the available clearance in the core or storage basket a limiting neutron fluence, or exposure, can be established

  2. The occupational exposure limit for fluid aerosol generated in metalworking operations: limitations and recommendations.

    Science.gov (United States)

    Park, Donguk

    2012-03-01

    The aim of this review was to assess current knowledge related to the occupational exposure limit (OEL) for fluid aerosols including either mineral or chemical oil that are generated in metalworking operations, and to discuss whether their OEL can be appropriately used to prevent several health risks that may vary among metalworking fluid (MWF) types. The OEL (time-weighted average; 5 mg/m(3), short-term exposure limit ; 15 mg/m(3)) has been applied to MWF aerosols without consideration of different fluid aerosol-size fractions. The OEL, is also based on the assumption that there are no significant differences in risk among fluid types, which may be contentious. Particularly, the health risks from exposure to water-soluble fluids may not have been sufficiently considered. Although adoption of The National Institute for Occupational Safety and Health's recommended exposure limit for MWF aerosol (0.5 mg/m(3)) would be an effective step towards minimizing and evaluating the upper respiratory irritation that may be caused by neat or diluted MWF, this would fail to address the hazards (e.g., asthma and hypersensitivity pneumonitis) caused by microbial contaminants generated only by the use of water-soluble fluids. The absence of an OEL for the water-soluble fluids used in approximately 80-90 % of all applicants may result in limitations of the protection from health risks caused by exposure to those fluids.

  3. Inherently safe technologies-chemical and nuclear

    International Nuclear Information System (INIS)

    Weinberg, A.M.

    1984-01-01

    Probabilistic risk assessments show an inverse relationship between the likelihood and the consequences of nuclear and chemical plant accidents, but the Bhopal accident has change public complacency about the safety of chemical plants to such an extent that public confidence is now at the same low level as with nuclear plants. The nuclear industry's response was to strengthen its institutions and improve its technologies, but the public may not be convinced. One solution is to develop reactors which do not depend upon the active intervention of humans of electromechanical devices to deal with emergencies, but which have physical properties that limit the possible temperature and power of a reactor. The Process Inherent Ultimately Safe and the modular High-Temperature Gas-Cooled reactors are two possibilities. the chemical industry needs to develop its own inherently safe design precepts that incorporate smallness, safe processes, and hardening against sabotage. 5 references

  4. Safe management of radioactive waste in Ghana

    International Nuclear Information System (INIS)

    Glover, E.T.; Fletcher, J.J.

    2000-01-01

    The Ghana Atomic Energy Commission was established in 1963 by an Act of Parliament, Act 204 for the Promotion, Development and Peaceful Application of Nuclear Techniques for the Benefit of Ghana. As in many developing countries the use of nuclear application is growing considerably in importance within the national economy. The Radiation Protection Board was established as the national regulatory authority and empowered by the Radiation Protection Instrument LI 1559 (1993). The above regulations, Act 204 and LI 1559 provided a minimum legal basis for regulatory control of radioactive waste management as it deals with waste management issues in a very general way and is of limited practical use to the waste producer. Hence the National Radioactive Waste Management Centre was established in July 1995 to carry out waste safety operations in Ghana. This paper highlights steps that have been taken to develop a systemic approach for the safe management of radioactive waste in the future and those already in existence. (author)

  5. Light water ultra-safe plant concept

    International Nuclear Information System (INIS)

    Klevans, E.

    1989-01-01

    Since the accident at Three Mile Island (TMI), Penn State Nuclear Engineering Department Faculty and Staff have considered various methods to improve already safe reactor designs and public perception of the safety of Nuclear Power. During 1987 and 1988, the Department of Energy provided funds to the Nuclear Engineering Department at Penn State to investigate a plant reconfiguration originated by M.A. Schultz called ''The Light Water Ultra-Safe Plant Concept''. This report presents a final summary of the project with references to several masters' theses and addendum reports for further detail. The two year research effort included design verification with detailed computer simulation of: (a) normal operation characteristics of the unique pressurizing concept, (b) severe transients without loss of coolant, (c) combined primary and secondary system modeling, and (d) small break and large break loss of coolant accidents. Other studies included safety analysis, low power density core design, and control system design to greatly simplify the control room and required operator responses to plant upset conditions. The overall conclusion is that a reconfigured pressurized water reactor can achieve real and perceived safety improvements. Additionally, control system research to produce greatly simplified control rooms and operator requirements should be continued in future projects

  6. Evolution and development of laws, regulations, criteria and human resources to ensure the safe decommissioning of nuclear facilities in Thailand

    International Nuclear Information System (INIS)

    Keinmeesuke, S.

    2006-01-01

    The Research Reactor, TRR-1 (renamed TRR-1/M1 after core replacement) in Thailand has been operated for more than 43 years. This ageing reactor will be facing shutdown in the near future. Laws and Regulations have been continually developed to assure the safe operation of nuclear facilities, particularly of the research reactor, and to ensure the safe decommissioning of the reactor after its operational life. However, the Thai nuclear legislation is still not applicable to a number of areas. Office of Atoms for Peace is working toward development of a new consolidated Act. In addition, the licensing steps for modification and decommissioning are added to the new Ministerial Regulation and to the new guidance documents on the licensing process for research reactors. Regulations, guidance and criteria for approval of decommissioning are being developed using the IAEA Safety Standards Series as the main basis for drafting. Human resource development is considered as one of the key important factor to ensure safe decommissioning of the installation. Staffing and training of the operating organization and the regulatory body personnel have been addressed to ensure the achievement of competency level. Simple methods and technologies are the best means for implementation while learning from experience of others will help and support us in our attempt to be the 'second First'. IAEA advice and assistance on the decommissioning of nuclear facilities in countries with limited resources is desirable. (author)

  7. Shift scheduling limits for the nuclear industry NRC policy and recommendations

    International Nuclear Information System (INIS)

    Koontz, J.; Morisseau, D.; Lewis, P.

    1985-01-01

    A study on shift scheduling and use of overtime and their effects on human performance in nuclear and non-nuclear industries was conducted. An analysis of the literature, current practices, and federal policy on shift scheduling resulted in human factors recommendations for limiting hours of work in the nuclear industry for nuclear power plant personnel conducting safety related functions. Recommended limits on total hours of work were developed by a panel of experts for both 8-hour and 12-hour daily shift schedules for weekly, biweekly, monthly, and annual work periods. The study results are particularly applicable to control room operators but should also be considered for other personnel where performance degradation due to fatigue could directly affect safe plant operations

  8. How safe are nuclear power plants

    International Nuclear Information System (INIS)

    Danzmann, H.J.

    1976-01-01

    The question 'how safe are nuclear power plants' can be answered differently - it depends on how the term 'safety' is understood. If the 'safety of supply' is left out as a possibility of interpretation, then the alternative views remain: Operational safety in the sense of reliability and safety of personnel and population. (orig.) [de

  9. Safe laparoscopic colorectal surgery performed by trainees

    DEFF Research Database (Denmark)

    Langhoff, Peter Koch; Schultz, Martin; Harvald, Thomas

    2013-01-01

    Laparoscopic surgery for colorectal cancer is safe, but there have been hesitations to implement the technique in all departments. One of the reasons for this may be suboptimal learning possibilities since supervised trainees have not been allowed to do the operations to an adequate extent...

  10. Safe injection procedures, injection practices, and needlestick ...

    African Journals Online (AJOL)

    Nermine Mohamed Tawfik Foda

    2017-01-10

    Jan 10, 2017 ... Background: Of the estimated 384,000 needle-stick injuries occurring in hospitals each year, 23% occur in surgical settings. This study was conducted to assess safe injection procedures, injection practices, and circumstances contributing to needlestick and sharps injures (NSSIs) in operating rooms.

  11. The inherently-safe power reactor DYONISOS (Dynamic Nuclear Inherently-Safe Reactor Operating with Spheres)

    International Nuclear Information System (INIS)

    Taube, M.; Lanfranchi, M.; Weissenfluh, Th. von; Ligou, J.; Yadigaroglu, G.; Taube, P.

    1986-01-01

    A philosophy of inherent safety is formulated and an inherently-safe thermal power reactor is presented. Solid fuel in the form of spheres a few centimetres in diameter is suspended under the hydro-dynamic pressure of molten lead coolant in vertical channels within the graphite moderator. Loss of main pump pressure, or a loss-of-coolant accident (LOCA), results in immediate removal of the fuel to rigid sieves below the core, with consequent subcriticality. Residual and decay heat are carried away by thermal conduction through the coolant or, in the case of a LOCA, by a combination of radiation and natural convection of cover gas or incoming air from the fuel to the reactor vessel and convection of air between the vessel and steel containment wall. All decay heat removal systems are passive, though actively initiated external spray cooling of the containment can be used to reduce wall temperature. This, however, is only necessary in the case of a LOCA and after a period of 24 h. (author)

  12. The Occupational Exposure Limit for Fluid Aerosol Generated in Metalworking Operations: Limitations and Recommendations

    Directory of Open Access Journals (Sweden)

    Donguk Park

    2012-03-01

    Full Text Available The aim of this review was to assess current knowledge related to the occupational exposure limit (OEL for fluid aerosols including either mineral or chemical oil that are generated in metalworking operations, and to discuss whether their OEL can be appropriately used to prevent several health risks that may vary among metalworking fluid (MWF types. The OEL (time-weighted average; 5 mg/m3, short-term exposure limit ; 15 mg/m3 has been applied to MWF aerosols without consideration of different fluid aerosol-size fractions. The OEL, is also based on the assumption that there are no significant differences in risk among fluid types, which may be contentious. Particularly, the health risks from exposure to water-soluble fluids may not have been sufficiently considered. Although adoption of The National Institute for Occupational Safety and Health's recommended exposure limit for MWF aerosol (0.5 mg/m3 would be an effective step towards minimizing and evaluating the upper respiratory irritation that may be caused by neat or diluted MWF, this would fail to address the hazards (e.g., asthma and hypersensitivity pneumonitis caused by microbial contaminants generated only by the use of water-soluble fluids. The absence of an OEL for the water-soluble fluids used in approximately 80-90 % of all applicants may result in limitations of the protection from health risks caused by exposure to those fluids.

  13. ICRP-recommendations on dose limits for workers

    International Nuclear Information System (INIS)

    Beninson, D.J.

    1976-01-01

    Dose limits proposed by the ICRP have been incorporated in most national and international standards and their respect has caused a distribution of doses with a average not exceeding 1/10 of the maximum permissible dose. This distribution corresponds to a risk which is well within the risks in 'safe industries'. There are at present some inconsistancies in the current system of recommended limits, for example having the same limit of 5 rem for the whole-body and also for some organs. Hopefully, this incosistancy will be removed in the next recommendation of the ICRP. But the whole-body limit of 5 rem in a year has been safe and there is little ground to reduce this limit on the basis of comparisons with 'safe industries'. (orig./HP) [de

  14. HiCAT Software Infrastructure: Safe hardware control with object oriented Python

    Science.gov (United States)

    Moriarty, Christopher; Brooks, Keira; Soummer, Remi

    2018-01-01

    High contrast imaging for Complex Aperture Telescopes (HiCAT) is a testbed designed to demonstrate coronagraphy and wavefront control for segmented on-axis space telescopes such as envisioned for LUVOIR. To limit the air movements in the testbed room, software interfaces for several different hardware components were developed to completely automate operations. When developing software interfaces for many different pieces of hardware, unhandled errors are commonplace and can prevent the software from properly closing a hardware resource. Some fragile components (e.g. deformable mirrors) can be permanently damaged because of this. We present an object oriented Python-based infrastructure to safely automate hardware control and optical experiments. Specifically, conducting high-contrast imaging experiments while monitoring humidity and power status along with graceful shutdown processes even for unexpected errors. Python contains a construct called a “context manager” that allows you define code to run when a resource is opened or closed. Context managers ensure that a resource is properly closed, even when unhandled errors occur. Harnessing the context manager design, we also use Python’s multiprocessing library to monitor humidity and power status without interrupting the experiment. Upon detecting a safety problem, the master process sends an event to the child process that triggers the context managers to gracefully close any open resources. This infrastructure allows us to queue up several experiments and safely operate the testbed without a human in the loop.

  15. Mathematical model for choosing the nuclear safe matrix compositions for fissile material immobilization

    International Nuclear Information System (INIS)

    Gorshtein, A.I.; Matyunin, Yu.I.; Poluehktov, P.P.

    2000-01-01

    A mathematical model is proposed for preliminary choice of the nuclear safe matrix compositions for fissile material immobilization. The IBM PC computer software for nuclear safe matrix composition calculations is developed. The limiting concentration of fissile materials in the some used and perspective nuclear safe matrix compositions for radioactive waste immobilization is calculated [ru

  16. Radiocarbon ages of ground water as a basis for the determination of safe limits of aquifer exploitation

    International Nuclear Information System (INIS)

    Tamers, M.A.; Stipp, J.J.; Weiner, R.

    1975-01-01

    Deep ground waters of the Biscayne aquifer of south Florida were studied with radiocarbon dating techniques. Dissolved carbonates served as the material for the age determinations. Limestone dilution corrections of the measured carbon-14 activities were made by comparison of the relative concentrations of bicarbonate and total carbonates. The deep well waters of the southern portion of the deposit have corrected radiocarbon contents indicating thermonuclear weapon testing contamination; they are, therefore, less than 20 years old. The ages of the ground waters generally increase in the northern direction. This is interpreted as due to the greater depth of the deposit of that region. A model is formulated for ground water movement in an unconfined producing hydrological unit and applied to the radiocarbon results of the most intensively exploited zone of the Biscayne aquifer. It is shown that the water which is extracted by the municipal wells in this area is limited to the bottom third of the deposit. The avoidance of pollution from the surrounding septic tanks in the shallower depths of the area is explained in this way. The model leads to an objective estimation of the safe limit for the ground water extraction rate in the zone. By application of radiocarbon dating, it is possible to obtain useful information without disturbing the water supply

  17. Improvement in operational characteristics of KEPCO’s line-commutation-type superconducting hybrid fault current limiter

    International Nuclear Information System (INIS)

    Yim, S.-W.; Park, B.-C.; Jeong, Y.-T.; Kim, Y.-J.; Yang, S.-E.; Kim, W.-S.; Kim, H.-R.; Du, H.-I.

    2013-01-01

    Highlights: ► A line-commutation type hybrid FCL was modified for 1st peak current limitation. ► A superconducting module of current limitation and fault detection was fabricated. ► The superconducting module was applied to a hybrid FCL system and tested. ► 7.4 kA p fault current was limited to 4.3 kA p at the first-half cycle by the FCL. -- Abstract: A 22.9 kV class hybrid fault current limiter (FCL) developed by Korea Electric Power Corporation and LS Industrial Systems in 2006 operates using the line commutation mechanism and begins to limit the fault current after the first half-cycle. The first peak of the fault current is available for protective coordination in the power system. However, it also produces a large electromagnetic force and imposes a huge stress on power facilities such as the main transformer and gas-insulated switchgear. In this study, we improved the operational characteristics of the hybrid FCL in order to reduce the first peak of the fault current. While maintaining the structure of the hybrid FCL system, we developed a superconducting module that detects and limits the fault current during the first half-cycle. To maintain the protective coordination capacity, the hybrid FCL was designed to reduce the first peak value of the fault current by up to approximately 30%. The superconducting module was also designed to produce a minimum AC loss, generating a small, uniform magnetic field distribution during normal operation. Performance tests confirmed that when applied to the hybrid FCL, the superconducting module showed successful current limiting operation without any damage

  18. Vapor-Compression Heat Pumps for Operation Aboard Spacecraft

    Science.gov (United States)

    Ruemmele, Warren; Ungar, Eugene; Cornwell, John

    2006-01-01

    Vapor-compression heat pumps (including both refrigerators and heat pumps) of a proposed type would be capable of operating in microgravity and would be safe to use in enclosed environments like those of spacecraft. The designs of these pumps would incorporate modifications of, and additions to, vapor-compression cycles of heat pumps now used in normal Earth gravitation, in order to ensure efficiency and reliability during all phases of operation, including startup, shutdown, nominal continuous operation, and peak operation. Features of such a design might include any or all of the following: (1) Configuring the compressor, condenser, evaporator, valves, capillary tubes (if any), and controls to function in microgravitation; (2) Selection of a working fluid that satisfies thermodynamic requirements and is safe to use in a closed crew compartment; (3) Incorporation of a solenoid valve and/or a check valve to prevent influx of liquid to the compressor upon startup (such influx could damage the compressor); (4) Use of a diode heat pipe between the cold volume and the evaporator to limit the influx of liquid to the compressor upon startup; and (5) Use of a heated block to vaporize any liquid that arrives at the compressor inlet.

  19. Dealing with a large installation of SRF cavities: Characterizing limitations and exploiting operational flexibility

    International Nuclear Information System (INIS)

    C. Reece; B. Madre; L. Doolittle; J. Delayen

    1999-01-01

    Linacs using a large number of SRF cavities can have an awkwardly large number of degrees of freedom for operational setup. The cost and robustness of operation as a function of operating gradient is a particular characteristic of each cavity system and the intended beamloading. A systematic characterization of these limitations has been developed which yields a valuable guide for development resource allocation. In addition, a software tool has been developed which enables the CEBAF machine operator to conveniently exploit the flexibility that results from the many degrees of freedom in response to changing programmatic needs. The two CEBAF SRF linacs each have about 160 independently-controlled SRF cavities. The software utility (LEM++) establishes the operationally optimum gradient in each cavity in response to the operator providing only three of the following four parameters: linac voltage, anticipated beam current, rf cryoheat load, and net rf trip rate. The utility is now fully operational at CEBAF. The methods employed and particular features useful for operations will be presented. The interactive process that has brought the software to its current form will also be discussed. The analysis scheme used to characterize the limitations of the ensemble of cavities will be presented as well

  20. 76 FR 12719 - Safe Schools/Healthy Students Program; Office of Safe and Drug-Free Schools; Safe Schools/Healthy...

    Science.gov (United States)

    2011-03-08

    ... DEPARTMENT OF EDUCATION Safe Schools/Healthy Students Program; Office of Safe and Drug- Free Schools; Safe Schools/Healthy Students Program; Catalog of Federal Domestic Assistance (CFDA) Numbers: 84... priorities, requirements, and definitions under the Safe Schools/Healthy Students (SS/HS) program. Since...

  1. 40 CFR 60.3052 - What else must I report if I have a deviation from the operating limits or the emission limitations?

    Science.gov (United States)

    2010-07-01

    ... control device was bypassed, or if a performance test was conducted that showed a deviation from any... deviation from the operating limits or the emission limitations? 60.3052 Section 60.3052 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) STANDARDS OF PERFORMANCE FOR...

  2. Fast current amplifier for background-limited operation of photovoltaic InSb detectors

    Energy Technology Data Exchange (ETDEWEB)

    Altmann, J; Koehler, S; Lahmann, W

    1981-01-01

    A fast current amplifier for use with photovoltaic indium antimonide detectors is described which was designed for detection of lidar return signals. Near background-limited operation was possible for bandwidths up to 0.8 MHz.

  3. Implications of inherent safe nuclear power system

    International Nuclear Information System (INIS)

    Song, Yo-Taik

    1987-01-01

    The safety of present day nuclear power reactors and research reactors depends on a combination of design features of passive and active systems, and the alert judgement of their operators. A few inherently safe designs of nuclear reactors for power plants are currently under development. In these designs, the passive systems are emphasized, and the active systems are minimized. Also efforts are made to eliminate the potential for human failures that initiate the series of accidents. If a major system fails in these designs, the core is flooded automatically with coolants that flow by gravity, not by mechanical pumps or electromagnetic actuators. Depending on the choice of the coolants--water, liquid metal and helium gas--there are three principal types of inherently safe reactors. In this paper, these inherently safe reactor designs are reviewed and their implications are discussed. Further, future perspectives of their acceptance by nuclear industries are discussed. (author)

  4. 40 CFR Table 4 to Subpart Xxxx of... - Operating Limits for Puncture Sealant Application Control Devices

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Operating Limits for Puncture Sealant Application Control Devices 4 Table 4 to Subpart XXXX of Part 63 Protection of Environment ENVIRONMENTAL... Manufacturing Pt. 63, Subpt. XXXX, Table 4 Table 4 to Subpart XXXX of Part 63—Operating Limits for Puncture...

  5. Inherently safe in situ uranium recovery

    Science.gov (United States)

    Krumhansl, James L; Brady, Patrick V

    2014-04-29

    An in situ recovery of uranium operation involves circulating reactive fluids through an underground uranium deposit. These fluids contain chemicals that dissolve the uranium ore. Uranium is recovered from the fluids after they are pumped back to the surface. Chemicals used to accomplish this include complexing agents that are organic, readily degradable, and/or have a predictable lifetime in an aquifer. Efficiency is increased through development of organic agents targeted to complexing tetravalent uranium rather than hexavalent uranium. The operation provides for in situ immobilization of some oxy-anion pollutants under oxidizing conditions as well as reducing conditions. The operation also artificially reestablishes reducing conditions on the aquifer after uranium recovery is completed. With the ability to have the impacted aquifer reliably remediated, the uranium recovery operation can be considered inherently safe.

  6. Determination of operating limits for radionuclides for a proposed landfill at Paducah Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    Wang, J.C.; Lee, D.W.; Ketelle, R.H.; Lee, R.R.; Kocher, D.C.

    1994-01-01

    The operating limits for radionuclides in sanitary and industrial wastes were determined for a proposed landfill at the Paducah Gaseous Diffusion Plant (PGDP), Kentucky. These limits, which may be very small but nonzero, are not mandated by law or regulation but are needed for rational operation. The approach was based on analyses of the potential contamination of groundwater at the plant boundary and the potential exposure to radioactivity of an intruder at the landfill after closure. The groundwater analysis includes (1) a source model describing the disposal of waste and the release of radionuclides from waste to the groundwater, (2) site-specific groundwater flow and contaminant transport calculations, and (3) calculations of operating limits from the dose limit and conversion factors. The intruder analysis includes pathways through ingestion of contaminated vegetables and soil, external exposure to contaminated soil, and inhalation of suspended activity from contaminated soil particles. In both analyses, a limit on annual effective dose equivalent of 4 mrem (0.04 mSv) was adopted. The intended application of the results is to refine the radiological monitoring standards employed by the PGDP Health Physics personnel to determine what constitutes radioactive wastes, with concurrence of the Commonwealth of Kentucky

  7. 75 FR 50936 - Loan Policies and Operations; Lending and Leasing Limits and Risk Management

    Science.gov (United States)

    2010-08-18

    ...-AC60 Loan Policies and Operations; Lending and Leasing Limits and Risk Management AGENCY: Farm Credit... sound operation of System institutions by strengthening their risk management practices and abilities to... the establishment of consistent, uniform and prudent concentration risk management policies by System...

  8. Improvement in operational characteristics of KEPCO’s line-commutation-type superconducting hybrid fault current limiter

    Science.gov (United States)

    Yim, S.-W.; Park, B.-C.; Jeong, Y.-T.; Kim, Y.-J.; Yang, S.-E.; Kim, W.-S.; Kim, H.-R.; Du, H.-I.

    2013-01-01

    A 22.9 kV class hybrid fault current limiter (FCL) developed by Korea Electric Power Corporation and LS Industrial Systems in 2006 operates using the line commutation mechanism and begins to limit the fault current after the first half-cycle. The first peak of the fault current is available for protective coordination in the power system. However, it also produces a large electromagnetic force and imposes a huge stress on power facilities such as the main transformer and gas-insulated switchgear. In this study, we improved the operational characteristics of the hybrid FCL in order to reduce the first peak of the fault current. While maintaining the structure of the hybrid FCL system, we developed a superconducting module that detects and limits the fault current during the first half-cycle. To maintain the protective coordination capacity, the hybrid FCL was designed to reduce the first peak value of the fault current by up to approximately 30%. The superconducting module was also designed to produce a minimum AC loss, generating a small, uniform magnetic field distribution during normal operation. Performance tests confirmed that when applied to the hybrid FCL, the superconducting module showed successful current limiting operation without any damage.

  9. Implementation of Safe-by-Design for Nanomaterial Development and Safe Innovation: Why We Need a Comprehensive Approach.

    Science.gov (United States)

    Kraegeloh, Annette; Suarez-Merino, Blanca; Sluijters, Teun; Micheletti, Christian

    2018-04-14

    Manufactured nanomaterials (MNMs) are regarded as key components of innovations in various fields with high potential impact (e.g., energy generation and storage, electronics, photonics, diagnostics, theranostics, or drug delivery agents). Widespread use of MNMs raises concerns about their safety for humans and the environment, possibly limiting the impact of the nanotechnology-based innovation. The development of safe MNMs and nanoproducts has to result in a safe as well as functional material or product. Its safe use, and disposal at the end of its life cycle must be taken into account too. However, not all MNMs are similarly useful for all applications, some might bear a higher hazard potential than others, and use scenarios could lead to different exposure probabilities. To improve both safety and efficacy of nanotechnology, we think that a new proactive approach is necessary, based on pre-regulatory safety assessment and dialogue between stakeholders. On the basis of the work carried out in different European Union (EU) initiatives, developing and integrating MNMs Safe-by-Design and Trusted Environments (NANoREG, ProSafe, and NanoReg2), we present our point of view here. This concept, when fully developed, will allow for cost effective industrial innovation, and an exchange of key information between regulators and innovators. Regulators are thus informed about incoming innovations in good time, supporting a proactive regulatory action. The final goal is to contribute to the nanotechnology governance, having faster, cheaper, effective, and safer nano-products on the market.

  10. TFTR tritium operations lessons learned

    International Nuclear Information System (INIS)

    Gentile, C.A.; Raftopoulos, S.; LaMarche, P.

    1996-01-01

    The Tokamak Fusion Test Reactor which is the progenitor for full D-T operating tokamaks has successfully processed > 81 grams of tritium in a safe and efficient fashion. Many of the fundamental operational techniques associated with the safe movement of tritium through the TFTR facility were developed over the course of many years of DOE tritium facilities (LANL, LLNL, SRS, Mound). In the mid 1980's The Tritium Systems Test Assembly (TSTA) at LANL began reporting operational techniques for the safe handling of tritium, and became a major conduit for the transfer of safe tritium handling technology from DOE weapons laboratories to non-weapon facilities. TFTR has built on many of the TSTA operational techniques and has had the opportunity of performing and enhancing these techniques at America's first operational D-T fusion reactor. This paper will discuss negative pressure employing 'elephant trunks' in the control and mitigation of tritium contamination at the TFTR facility, and the interaction between contaminated line operations and Δ pressure control. In addition the strategy employed in managing the movement of tritium through TFTR while maintaining an active tritium inventory of < 50,000 Ci will be discussed. 5 refs

  11. The End-To-End Safety Verification Process Implemented to Ensure Safe Operations of the Columbus Research Module

    Science.gov (United States)

    Arndt, J.; Kreimer, J.

    2010-09-01

    The European Space Laboratory COLUMBUS was launched in February 2008 with NASA Space Shuttle Atlantis. Since successful docking and activation this manned laboratory forms part of the International Space Station(ISS). Depending on the objectives of the Mission Increments the on-orbit configuration of the COLUMBUS Module varies with each increment. This paper describes the end-to-end verification which has been implemented to ensure safe operations under the condition of a changing on-orbit configuration. That verification process has to cover not only the configuration changes as foreseen by the Mission Increment planning but also those configuration changes on short notice which become necessary due to near real-time requests initiated by crew or Flight Control, and changes - most challenging since unpredictable - due to on-orbit anomalies. Subject of the safety verification is on one hand the on orbit configuration itself including the hardware and software products, on the other hand the related Ground facilities needed for commanding of and communication to the on-orbit System. But also the operational products, e.g. the procedures prepared for crew and ground control in accordance to increment planning, are subject of the overall safety verification. In order to analyse the on-orbit configuration for potential hazards and to verify the implementation of the related Safety required hazard controls, a hierarchical approach is applied. The key element of the analytical safety integration of the whole COLUMBUS Payload Complement including hardware owned by International Partners is the Integrated Experiment Hazard Assessment(IEHA). The IEHA especially identifies those hazardous scenarios which could potentially arise through physical and operational interaction of experiments. A major challenge is the implementation of a Safety process which owns quite some rigidity in order to provide reliable verification of on-board Safety and which likewise provides enough

  12. Conduct of Operations at Nuclear Power Plants. Safety Guide (Spanish Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This Safety Guide identifies the main responsibilities and practices of nuclear power plant (NPP) operations departments in relation to their responsibility for the safe functioning of the plant. The guide presents the factors to be considered in structuring the operations department of an NPP; setting high standards of performance; making safety related decisions in an effective manner; conducting control room and field activities in a thorough and professional manner; and maintaining an NPP within established operational limits and conditions. Contents: 1. Introduction; 2. Management and organization of plant operations; 3. Shift complement and functions; 4. Shift routines and operating practices; 5. Control of equipment and plant status; 6. Operations equipment and operator aids; 7. Work control and authorization.

  13. Cool and Safe: Multiplicity in Safe Innovation at Unilever

    Science.gov (United States)

    Penders, Bart

    2011-01-01

    This article presents the making of a safe innovation: the application of ice structuring protein (ISP) in edible ices. It argues that safety is not the absence of risk but is an active accomplishment; innovations are not "made safe afterward" but "safe innovations are made". Furthermore, there are multiple safeties to be accomplished in the…

  14. Solutions for Safe Hot Coil Evacuation and Coil Handling in Case of Thick and High Strength Steel

    Directory of Open Access Journals (Sweden)

    Sieberer Stefan

    2016-01-01

    Full Text Available Currently hot rolling plants are entering the market segment for thick gauges and high strength steel grades where the elastic bending property of the strip leads to internal forces in the coil during coiling operation. The strip tends to open. Primetals is investigating several possibilities to facilitate safe coil evacuation and coil handling under spring-back conditions. The contribution includes finite element models of such mechanical solutions. Results of parameter variation and stability limits of case studies are presented in the paper.

  15. Safe transport of radioactive material. 3. ed

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-12-01

    The IAEA has developed a standardized approach to transport safety training as a means of helping Member States to implement the Transport Regulations. The training manual is an anchor of this standardized approach to training: it contains all the topics presented in the sequential order recommended by the IAEA for the student to gain a thorough understanding of the body of knowledge that is needed to ensure that radioactive material ranked as Class 7 in the United Nations' nomenclature for dangerous goods - is transported safely. The explanations in the text refer, where needed, to the appropriate requirements in the IAEA's Transport Regulations; additional useful information is also provided. Thus, the training manual in addition to the Transport Regulations and their supporting documents is used by the IAEA as the basis for delivering all of its training courses on the safe transport of radioactive material. Enclosed with the training manual is a CD-ROM that contains the text of the manual as well as the visual aids that are used at the IAEA's training courses. The following topics are covered: review of radioactivity and radiation; review of radiation protection principles; regulatory terminology; basic safety concepts: materials and packages; activity limits and material restrictions; selection of optimal package type; test procedures: material and packages; requirements for transport; control of material in transport; fissile material: regulatory requirements and operational aspects; quality assurance; national competent authority; additional regulatory constraints for transport; international liability and insurance; emergency planning and preparedness; training; services provided by the IAEA.

  16. Safe transport of radioactive material. 3. ed

    International Nuclear Information System (INIS)

    2002-01-01

    The IAEA has developed a standardized approach to transport safety training as a means of helping Member States to implement the Transport Regulations. The training manual is an anchor of this standardized approach to training: it contains all the topics presented in the sequential order recommended by the IAEA for the student to gain a thorough understanding of the body of knowledge that is needed to ensure that radioactive material ranked as Class 7 in the United Nations' nomenclature for dangerous goods - is transported safely. The explanations in the text refer, where needed, to the appropriate requirements in the IAEA's Transport Regulations; additional useful information is also provided. Thus, the training manual in addition to the Transport Regulations and their supporting documents is used by the IAEA as the basis for delivering all of its training courses on the safe transport of radioactive material. Enclosed with the training manual is a CD-ROM that contains the text of the manual as well as the visual aids that are used at the IAEA's training courses. The following topics are covered: review of radioactivity and radiation; review of radiation protection principles; regulatory terminology; basic safety concepts: materials and packages; activity limits and material restrictions; selection of optimal package type; test procedures: material and packages; requirements for transport; control of material in transport; fissile material: regulatory requirements and operational aspects; quality assurance; national competent authority; additional regulatory constraints for transport; international liability and insurance; emergency planning and preparedness; training; services provided by the IAEA

  17. ETHEL's systems and facilities for safe management of tritiated wastes

    International Nuclear Information System (INIS)

    Mannone, F.; Dworschak, H.; Vassallo, G.

    1992-01-01

    The European Tritium Handling Experimental Laboratory (ETHEL) is a new tritium facility at the Commission of the European Community's Joint Research Centre, Ispra Site. The laboratory, destined to handle multigram amounts of tritium for safety related R and D purposes, is foreseen to start radioactive operations in late 1992. The general operation and maintenance of laboratory systems and future experiments will generate tritiated wastes in gaseous, liquid and solid forms. The management of such wastes under safe working conditions is a stringent laboratory requirement aimed at minimizing the risk of unacceptable tritium exposures to workers and the general public. This paper describes the main systems and facilities installed in ETHEL for the safe management of tritiated wastes

  18. AECL's support to operating plants world wide

    International Nuclear Information System (INIS)

    Azeez, S.; Kakaria, B.K.; Hinchley, E.M.

    1998-01-01

    Through their operating records, CANDU reactors have established themselves as a successful and cost-effective source of electricity in Canada and abroad. They have proven to be safe, reliable and economical. A variety of factors have contributed to the enviable CANDU record, such as a sound design based on proven principles supported by effective development programs, along with dedicated plant owners committed to excellence in safely maintaining and operating their plants. Atomic Energy of Canada Limited (AECL), the CANDU designer, has continuously maintained a close relationship with owners/operators of the plants in Canada, Argentina, Romania and South Korea. AECL and the plant operators have all benefited from this strengthening relationship by sharing experience and information. CANDU plant operators have been required to respond decisively to the economic realities of downward cost pressures and deregulation. Operating, Maintenance and Administration (OM and A) costs are being given a new focus as plant owners review each cost element to improve the economic returns from their investments. Amongst the three main OM and A constituents, plant maintenance costs are the most variable and have the largest influence on effective plant operations. The correlation between effective plant maintenance and high capacity factors shows clearly the importance of proactive maintenance planning to reduce the frequency and duration of forced plant outages and their negative impacts on plant economics. This paper describes the management processes and organizational structures m AECL that support plant operations and maintenance in operating CANDU plants with cost effective products and services. (author)

  19. Safety Analysis For Evaluating (SAFE) sUAS, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — NASA's Unmanned Aircraft Systems Integration in the NAS (UAS in the NAS) project is aimed at developing new technologies to enable safe operations of UAS in the NAS....

  20. Method for the determination of technical specifications limiting temperature in EBR-II operation

    International Nuclear Information System (INIS)

    Chang, L.K.; Hill, D.J.; Ku, J.Y.

    1994-01-01

    The methodology and analysis procedure to qualify the Mark-V and Mark-VA fuels for the Experimental Breeder Reactor II are summarized in this paper. Fuel performance data and design safety criteria are essential for thermal-hydraulic analysis and safety evaluations. Normal and off-normal operation duty cycles and transient classifications are required for the safety assessment of the fuels. The temperature limits of subassemblies were first determined by a steady-state thermal-structural and fuel damage analysis, in which a trial-and-error approach was used to predict the maximum allowable fuel pin temperature that satisfies the design criteria for steady-state normal operation. The steady-state temperature limits were used as the basis of the off-normal transient analysis to assess the safety performance of the fuel for anticipated, unlikely and extremely unlikely events. If the design criteria for the off-normal events are not satisfied, then the subassembly temperature limit is reduced and an iterative procedure is employed until all design criteria are met

  1. MHD stability limits to the operation parameters of the FT tokamak

    International Nuclear Information System (INIS)

    Alladio, F.; Bardotti, G.; Bartiromo, R.

    1986-01-01

    A systematic study of the macroscopic instabilities limiting the accessible operation parameters has been performed on the Ohmic discharges of the FT tokamak at Bsub(T)=40 and 60 kG. The MHD fluctuation behaviour and the modifications of the profiles associated with the precursor of the disruption are discussed in detail for the cases of breaking through qsub(L)=3, low-qsub(L) operation, disruptions at the high-density limit and disruptions following the disappearance of the sawtooth activity. In all these cases the power balance terms that appear associated with the development of the MHD instabilities are dominant either in the centre or at the edge of the discharge and so transport in the intermediate confinement zone does not seem to be affected during the precursor of the disruption. The loop voltage negative spike of the disruption itself is found to be associated with the appearance of a burst of m=3, n=2 modes in the presence of m=2, n=1 precursor activity. (author)

  2. 40 CFR 63.5698 - What emission limit must I meet for open molding resin and gel coat operations?

    Science.gov (United States)

    2010-07-01

    ... open molding resin and gel coat operations? 63.5698 Section 63.5698 Protection of Environment... Manufacturing Standards for Open Molding Resin and Gel Coat Operations § 63.5698 What emission limit must I meet for open molding resin and gel coat operations? (a) You must limit organic HAP emissions from the five...

  3. Worcester 1 Inch Solenoid-Actuated Gas Operated SCHe System Valves

    International Nuclear Information System (INIS)

    VAN KATWIJK, C.

    2000-01-01

    1 inch Gas-operated full-port ball valves incorporate a solenoid and limit switches as integral parts of the actuator. These valves are normally open and fail safe to the open position (GOV-1*02 and 1*06 fail closed) to provide a flow path of helium gas to the MCO under helium purge and off-normal conditions when the MCO is isolated

  4. 76 FR 81904 - Solicitation of New Safe Harbors and Special Fraud Alerts

    Science.gov (United States)

    2011-12-29

    ... Medicaid Patient and Program Protection Act of 1987, Public Law 100-93 Sec. 14, the Act, Sec. 1128B(b), 42...-called ``safe harbor'' provisions, specifying various payment and business practices that, although... basis for administrative sanctions. OIG safe harbor provisions have been developed ``to limit the reach...

  5. SafeNet: a methodology for integrating general-purpose unsafe devices in safe-robot rehabilitation systems.

    Science.gov (United States)

    Vicentini, Federico; Pedrocchi, Nicola; Malosio, Matteo; Molinari Tosatti, Lorenzo

    2014-09-01

    Robot-assisted neurorehabilitation often involves networked systems of sensors ("sensory rooms") and powerful devices in physical interaction with weak users. Safety is unquestionably a primary concern. Some lightweight robot platforms and devices designed on purpose include safety properties using redundant sensors or intrinsic safety design (e.g. compliance and backdrivability, limited exchange of energy). Nonetheless, the entire "sensory room" shall be required to be fail-safe and safely monitored as a system at large. Yet, sensor capabilities and control algorithms used in functional therapies require, in general, frequent updates or re-configurations, making a safety-grade release of such devices hardly sustainable in cost-effectiveness and development time. As such, promising integrated platforms for human-in-the-loop therapies could not find clinical application and manufacturing support because of lacking in the maintenance of global fail-safe properties. Under the general context of cross-machinery safety standards, the paper presents a methodology called SafeNet for helping in extending the safety rate of Human Robot Interaction (HRI) systems using unsafe components, including sensors and controllers. SafeNet considers, in fact, the robotic system as a device at large and applies the principles of functional safety (as in ISO 13489-1) through a set of architectural procedures and implementation rules. The enabled capability of monitoring a network of unsafe devices through redundant computational nodes, allows the usage of any custom sensors and algorithms, usually planned and assembled at therapy planning-time rather than at platform design-time. A case study is presented with an actual implementation of the proposed methodology. A specific architectural solution is applied to an example of robot-assisted upper-limb rehabilitation with online motion tracking. Copyright © 2014 Elsevier Ireland Ltd. All rights reserved.

  6. Training aids: the motor operator valve trainer

    International Nuclear Information System (INIS)

    McCulloch, B.

    1987-01-01

    The spectrum of training aids used in the nuclear industry runs the gamut from the very basic (i.e., valve training aids - gate, globe, check) to the highly complex (i.e., nuclear full scope simulator). Designing and purchasing the best training aids take much time, detailed investigation, and good understanding of plant operations. The training aid that has given the New York Power Authority the best results has been the motor operator valve (MOV) trainer. Some of the items that make the MOV trainer a good choice are: (1) large number of MOVs in the plant, (2) importance of MOVs to safe plant operation, (3) detailed MOV procedures used by the plant, (4) history of MOV problems, and (5) ability to demonstrate important concepts and operation - hammer blow effect, torque and limit switch adjustment and functions, and actual sequence of operation of the limitorque valve operator

  7. 40 CFR 63.3967 - How do I establish the emission capture system and add-on control device operating limits during...

    Science.gov (United States)

    2010-07-01

    ... system and add-on control device operating limits during the performance test? 63.3967 Section 63.3967... capture system and add-on control device operating limits during the performance test? During the... the operating limits required by § 63.3892 according to this section, unless you have received...

  8. Recommendations of the NUSS programme to achieve safe operation

    International Nuclear Information System (INIS)

    Bertini, A.

    1985-01-01

    The paper exposes essentially the spirit of the Code of Practice and of the Safety Guides on Operation. Emphasis is put on the fact that safety operation is the outcome of a mental habit which must permeate all levels of the operating organization, rather than just being due to the effect of specific rules, which, like safety factors in design, ensure achievement of the safety goals. The paper, starting from what is written in the NUSS documents, deals with what is not actually written in these, because a mental habit cannot be codified and a safety-minded organization cannot be created by a law or by a regulation. The paper underlines the necessity for all problems connected with nuclear operation to be tackled without prejudices, without reference to irrelevant precedents or practices, in the exclusive interest of safety. (author)

  9. Plant life time management for safe long term operation

    International Nuclear Information System (INIS)

    Burket, Danes

    2010-01-01

    The topics discussed include LTO (long-term operation) and licensing procedure in general and specifically for the Dukovany NPP, components of an LTO programme, the PLIM (plant life management) concept for Dukovany and Temelin, the LTO implementation project for Dukovany, LTO strategy, LTO risk study, international verification. The Conclusions include the following items: (i) Technical-economic study of Dukovany NPP LTO demonstrates technical feasibility and economic profitability of Dukovany NPP LTO with perspective for up to 60 years of operation. (ii) Safety part of Program for assurance of Dukovany NPP LTO complies with IAEA SALTO recommendations. (iii) Dukovany NPP LTO programme incorporated IAEA SALTO Peer Review Mission recommendations. (iv) LTO Implementation Project for 2009-2015 was approved with major targets to renew operational permission and prepare NPP for operation up to 60 years. (v) Preparation of Temelin NPP LTO programme has been started. (P.A.)

  10. Launch and recovery of ROV: Investigation of operational limit from DNV Recommended Practices and time domain simulations in SIMO

    OpenAIRE

    Valen, Magnus

    2010-01-01

    Offshore contractors seek to operate their remotely operated vehicles for the widest range of sea conditions where particularly launch and recovery through splash zone are critical phases in the offshore operation. The analytical methods for calculation of operational limit proposed by guidelines from DNV Recommended Practices may lead to an over-estimation of the hydrodynamic forces and consequently to an unduly restrictive operational limit. Accurate predictions of the hydrodynamic forces a...

  11. High beta tokamak operation in DIII-D limited at low density/collisionality by resistive tearing modes

    International Nuclear Information System (INIS)

    La Haye, R.J.; Lao, L.L.; Strait, E.J.; Taylor, T.S.

    1997-01-01

    The maximum operational high beta in single-null divertor (SND) long pulse tokamak discharges in the DIII-D tokamak with a cross-sectional shape similar to the proposed International Thermonuclear Experimental Reactor (ITER) device is found to be limited by the onset of resistive instabilities that have the characteristics of neoclassically destabilized tearing modes. There is a soft limit due to the onset of an m/n=3/2 rotating tearing mode that saturates at low amplitude and a hard limit at slightly higher beta due to the onset of an m/n=2/1 rotating tearing mode that grows, slows down and locks. By operating at higher density and thus collisionality, the practical beta limit due to resistive tearing modes approaches the ideal magnetohydrodynamic (MHD) limit. (author). 15 refs, 4 figs

  12. 40 CFR Table 30 to Subpart Uuu of... - Operating Limits for HAP Emissions From Sulfur Recovery Units

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Operating Limits for HAP Emissions From Sulfur Recovery Units 30 Table 30 to Subpart UUU of Part 63 Protection of Environment ENVIRONMENTAL..., Table 30 Table 30 to Subpart UUU of Part 63—Operating Limits for HAP Emissions From Sulfur Recovery...

  13. CDX-U Operation with a Large Area Liquid Lithium Limiter

    International Nuclear Information System (INIS)

    R. Majeski; M. Boaz; D. Hoffman; B. Jones; R. Kaita; H. Kugel; T. Munsat; J. Spaleta; V. Soukhanovskii; J. Timberlake; L. Zakharov; G. Antar; R. Doerner; S. Luckhardt; R.W. Conn; M. Finkenthal; D. Stutman; R. Maingi; M. Ulrickson

    2002-01-01

    The Current Drive experiment-Upgrade (CDX-U) at the Princeton Plasma Physics Laboratory has begun experiments with a fully toroidal liquid lithium limiter. CDX-U is a compact [R = 34 cm, a = 22 cm, B(subscript)toroidal = 2 kG, I(subscript)P = 100 kA, T(subscript)e(0) ∼ 100 eV, n(subscript)e(0) ∼ 5 x 10 19 m -3 ] short-pulse (<25 msec) spherical torus with extensive diagnostics. The limiter, which consists of a shallow circular stainless steel tray of radius 34 cm and width 10 cm, can be filled with lithium to a depth of a few millimeters, and forms the lower limiting surface for the discharge. Heating elements beneath the tray are used to liquefy the lithium prior to the experiment. Surface coatings are evident on part of the lithium. Despite the surface coatings, tokamak discharges operated in contact with the lithium-filled tray show evidence of reduced impurities and recycling. The reduction in recycling is largest when the lithium is liquefied by heating to 250 degrees Celsius

  14. A Safe Cooperative Framework for Atmospheric Science Missions with Multiple Heterogeneous UAS using Piecewise Bezier Curves

    Science.gov (United States)

    Mehdi, S. Bilal; Puig-Navarro, Javier; Choe, Ronald; Cichella, Venanzio; Hovakimyan, Naira; Chandarana, Meghan; Trujillo, Anna; Rothhaar, Paul M.; Tran, Loc; Neilan, James H.; hide

    2016-01-01

    Autonomous operation of UAS holds promise for greater productivity of atmospheric science missions. However, several challenges need to be overcome before such missions can be made autonomous. This paper presents a framework for safe autonomous operations of multiple vehicles, particularly suited for atmospheric science missions. The framework revolves around the use of piecewise Bezier curves for trajectory representation, which in conjunction with path-following and time-coordination algorithms, allows for safe coordinated operations of multiple vehicles.

  15. The role of safe practices in hospitals’ total factor productivity

    Directory of Open Access Journals (Sweden)

    Timothy R Huerta

    2011-01-01

    Full Text Available Timothy R Huerta1, Mark A Thompson2, Eric W Ford31Center for Health Innovation, Education, and Research, 2Rawls College of Business, Texas Tech University, Lubbock, TX, USA; 3Forsyth Medical Center Distinguished Professor of Health Care, The University of North Carolina Greensboro, Greensboro, NC, USAAbstract: The dual aims of improving safety and productivity are a major part of the health care reform movement hospital leaders must manage. Studies exploring the two phenomena conjointly and over time are critical to understanding how change in one dimension influences the other over time. A Malmquist approach is used to assess hospitals’ relative productivity levels over time. Analysis of variance (ANOVA algorithms were executed to assess whether or not the Malmquist Indices (MIs correlate with the safe practices measure. The American Hospital Association’s annual survey and the Centers for Medicare and Medicaid Services’ Case Mix Index for fiscal years 2002–2006, along with Leapfrog Group’s annual survey for 2006 were used for this study. Leapfrog Group respondents have significantly higher technological change (TC and total factor productivity (TFP than nonrespondents without sacrificing technical efficiency changes. Of the three MIs, TC (P < 0.10 and TFP (P < 0.05 had significant relationships with the National Quality Forum’s Safe Practices score. The ANOVA also indicates that the mean differences of TFP measures progressed in a monotonic fashion up the Safe Practices scale. Adherence to the National Quality Forum’s Safe Practices recommendations had a major impact on hospitals’ operating processes and productivity. Specifically, there is evidence that hospitals reporting higher Safe Practices scores had above average levels of TC and TFP gains over the period assessed. Leaders should strive for increased transparency to promote both quality improvement and increased productivity.Keywords: safety, productivity, quality, safe

  16. Safety training and safe operating procedures written for PBFA (Particle Beam Fusion Accelerator) II and applicable to other pulsed power facilities

    Energy Technology Data Exchange (ETDEWEB)

    Donovan, G.L.; Goldstein, S.A.

    1986-12-01

    To ensure that work in advancing pulsed power technology is performed with an acceptably low risk, pulsed power research facilities at Sandia National Laboratories must satisfy general safety guidelines established by the Department of Energy, policies and formats of the Environment, Safety, and Health (ES and H) Department, and detailed procedures formulated by the Pulsed Power Sciences Directorate. The approach to safety training and to writing safe operating procedures, and the procedures presented here are specific to the Particle Beam Fusion Accelerator II (PBFA II) Facility but are applicable as guidelines to other research and development facilities which have similar hazards.

  17. Safety training and safe operating procedures written for PBFA [Particle Beam Fusion Accelerator] II and applicable to other pulsed power facilities

    International Nuclear Information System (INIS)

    Donovan, G.L.; Goldstein, S.A.

    1986-12-01

    To ensure that work in advancing pulsed power technology is performed with an acceptably low risk, pulsed power research facilities at Sandia National Laboratories must satisfy general safety guidelines established by the Department of Energy, policies and formats of the Environment, Safety, and Health (ES and H) Department, and detailed procedures formulated by the Pulsed Power Sciences Directorate. The approach to safety training and to writing safe operating procedures, and the procedures presented here are specific to the Particle Beam Fusion Accelerator II (PBFA II) Facility but are applicable as guidelines to other research and development facilities which have similar hazards

  18. Application of digital solutions to help the safe and efficient operation of nuclear power plants; Aplicacion de soluciones digitales para la ayuda a la operacion segura y eficiente de las centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Ortega P, F.; Fernandez F, S., E-mail: fortega@tecnatom.es [Tecnatom S. A., Av. Montes de Oca 1, 28703 San Sebastian de los Reyes, Madrid (Spain)

    2017-09-15

    In the search for excellence, the emergence of solutions to digitize nuclear power plants is an opportunity to optimize the operation and safety of them. The new technologies available today in the market, applied under a global vision of the operation, can contribute to the excellent operation of nuclear power plants in terms of efficiency and effectiveness. Tecnatom has a long experience in various areas related to the operation of the plants, giving the aforementioned global vision, essential to develop global solutions that pursue the safe and efficient operation of the operation. (Author)

  19. Eye safe laser range finders

    International Nuclear Information System (INIS)

    Snir, M.; Margaliot, M.; Amitzi, A.

    2004-01-01

    During the 1970's, Ruby (Q switched) laser based range finders with a wavelength of 694nm were first used. These lasers operated in a pulse mode within the visible light range and produced a risk for the eye retina. The laser beam striking the macula could damage the eye and might cause blindness. Over the years, Nd:YAG (Q switched) lasers were developed (operating at 1064nm) for range finding and designation uses. The wavelength of these lasers, operating in the near Infra-Red range (invisible), is also focused tightly on the retina. The human eye does not respond to the invisible light so there is no natural protection (eye blink reflex) as in the visible light. The operation of these lasers worldwide, especially when the laser beam is exposed, causes occasional eye accidents. Another risk is stemming from the use of observation systems with a high optical gain, in the laser operation areas, which enlarge the range of risk quite significantly. Therefore, research and development efforts were invested in order to introduce eye safe lasers. One of the solutions for this problem is presented in following document

  20. 40 CFR 63.1344 - Operating limits for kilns and in-line kiln/raw mills.

    Science.gov (United States)

    2010-07-01

    ... kiln/raw mills. 63.1344 Section 63.1344 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY... mills. (a) The owner or operator of a kiln subject to a D/F emission limitation under § 63.1343 must... specified in paragraph (b) of this section. The owner or operator of an in-line kiln/raw mill subject to a D...

  1. The importance of human performance and procedures in limiting severe accident risks

    International Nuclear Information System (INIS)

    Higgins, J.C.

    1990-01-01

    Due to the defense in depth concept and redundancy in safety systems utilized, complex industrial plants, such as nuclear power plants (NPPs) can be operated safely. This capability has been demonstrated by many years of safe operation by numerous NPPs in the US and abroad. However, the occurrence of severe accidents has also demonstrated that constant vigilance in a number of areas is necessary to ensure continued safe operation. The areas noted as particularly important are Design, Organization and Management, Maintenance, and Operations (Human Performance). 18 refs

  2. ALPS - advanced limiter-divertor plasma-facing systems

    International Nuclear Information System (INIS)

    Allain, J. P.; Bastasz, R.; Brooks, J. N.; Evans, T.; Hassanein, A.; Luckhardt, S.; Maingi, R.; Mattas, R. F.; McCarthy, K.; Mioduszewski, P.; Mogahed, E.; Moir, R.; Molokov, S.; Morely, N.; Nygren, R.; Reed, C.; Rognlien, T.; Ruzic, D.; Sviatoslavsky, I.; Sze, D.; Tillack, M.; Ulrickson, M.; Wade, P. M.; Wong, C.; Wooley, R.

    1999-01-01

    The Advanced Limiter-divertor Plasma-facing Systems (ALPS) program was initiated in order to evaluate the potential for improved performance and lifetime for plasma-facing systems. The main goal of the program is to demonstrate the advantages of advanced limiter/divertor systems over conventional systems in terms of power density capability, component lifetime, and power conversion efficiency, while providing for safe operation and minimizing impurity concerns for the plasma. Most of the work to date has been applied to free surface liquids. A multi-disciplinary team from several institutions has been organized to address the key issues associated with these systems. The main performance goals for advanced limiters and diverters are a peak heat flux of >50 MW/m 2 ,elimination of a lifetime limit for erosion, and the ability to extract useful heat at high power conversion efficiency (approximately40%). The evaluation of various options is being conducted through a combination of laboratory experiments, modeling of key processes, and conceptual design studies. The current emphasis for the work is on the effects of free surface liquids on plasma edge performance

  3. Method for the determination of technical specifications limiting temperature in EBR-II operation

    International Nuclear Information System (INIS)

    Chang, L.K.; Hill, D.J.; Ku, J.Y.

    2004-01-01

    The methodology and analysis procedure to qualify the Mark-V and Mark-VA fuels for the Experimental Breeder Reactor II are summarized in this paper. Fuel performance data and design safety criteria are essential for thermal-hydraulic analyses and safety evaluations. Normal and off-normal operation duty cycles and transient classifications are required for the safety assessment of the fuels. Design safety criteria for steady-state normal and transient off-normal operations were developed to ensure structural integrity of the fuel pin. The maximum allowable coolant outlet temperatures and powers of subassemblies for steady-state normal operation conditions were first determined in a row-by-row basis by a thermal-hydraulic and fuel damage analysis, in which a trial-and-error approach was used to predict the maximum subassembly coolant outlet temperatures and powers that satisfy the design safety criteria for steady-state normal operation conditions. The limiting steady-state temperature and power were then used as the initial subassembly thermal conditions for the off-normal transient analysis to assess the safety performance of the fuel pin for anticipated, unlikely and extremely unlikely events. If the design safety criteria for the off-normal events are not satisfied, then the initial steady-state subassembly temperatures and/or powers are reduced and an iterative procedure is employed until the design safety criteria for off-normal conditions are satisfied, and the initial subassembly outlet coolant temperature and power are the technical specification limits for reactor operation. (author)

  4. Fuel supply shutdown facility interim operational safety requirements

    International Nuclear Information System (INIS)

    Besser, R.L.; Brehm, J.R.; Benecke, M.W.; Remaize, J.A.

    1995-01-01

    These Interim Operational Safety Requirements (IOSR) for the Fuel Supply Shutdown (FSS) facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls to ensure safe operation. The IOSRs apply to the fuel material storage buildings in various modes (operation, storage, surveillance)

  5. The SafeCOP ECSEL Project: Safe Cooperating Cyber-Physical Systems Using Wireless Communication

    DEFF Research Database (Denmark)

    Pop, Paul; Scholle, Detlef; Hansson, Hans

    2016-01-01

    This paper presents an overview of the ECSEL project entitled "Safe Cooperating Cyber-Physical Systems using Wireless Communication" (SafeCOP), which runs during the period 2016 -- 2019. SafeCOP targets safety-related Cooperating Cyber-Physical Systems (CO-CPS) characterised by use of wireless...... detection of abnormal behaviour, triggering if needed a safe degraded mode. SafeCOP will also develop methods and tools, which will be used to produce safety assurance evidence needed to certify cooperative functions. SafeCOP will extend current wireless technologies to ensure safe and secure cooperation...

  6. Working safely with electronics racks

    CERN Document Server

    Simon Baird, HSE Unit Head

    2016-01-01

    Think of CERN and you’ll probably think of particle accelerators and detectors. These are the tools of the trade in particle physics, but behind them are the racks of electronics that include power supplies, control systems and data acquisition networks.   Inside an electronics rack: danger could be lurking if the rack is not powered off. In routine operation, these are no more harmful than the home entertainment system in your living room. But unscrew the cover and it’s a different matter. Even after following appropriate training, and with formal authorisation from your group leader or equivalent to carry out electrical work or any work in the vicinity of electrical hazards, and even with extensive experience of carrying out such operations, it’s important to incorporate safe working practices into your routine. At CERN, before the racks of electronics reach their operational configurations for the accelerators and detectors, they play a vital role in test set-ups ...

  7. Is safe surgery possible when resources are scarce?

    Science.gov (United States)

    O'Hara, Nathan N

    2015-07-01

    The greatest burden of surgical disease exists in low- and middle-income countries, where the quality and safety of surgical treatment cause major challenges. Securing necessary and appropriate medical supplies and infrastructure remains a significant and under-recognised limitation to providing safe and high-quality surgical care in these settings. The majority of surgical instruments are sold in high-income countries. Limited market pressures lead to superfluous designs and inflated costs for these devices. This context creates an opportunity for frugal innovation-the search for designs that will enable low-cost care without compromising quality. Although progressive examples of frugal surgical innovations exist, policy innovation is required to augment design pathways while fostering appropriate safety controls for prospective devices. Many low-cost, high-quality medical technologies will increase access to safe surgical care in low-income countries and have widespread applicability as all countries look to reduce the cost of providing care, without compromising quality. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

  8. Principal trends in ensuring safety in nuclear power plant operation in the CSSR

    International Nuclear Information System (INIS)

    Beranek, J.; Kriz, Z.; Kovar, P.; Macoun, J.

    1984-01-01

    At present two reactor units of the VVER-440 type industrial nuclear power plant are in operation in Czechoslovakia and another ten units are planned to be commissioned and put in operation by 1990. The operation of these units is carried out in compliance with licences and regulations issued by the State Regulatory Body for Nuclear Safety, a body established within the framework of the Czechoslovak Atomic Energy Commission. Operational nuclear safety assurance is based primarily on compliance with the basic safety concept as conceived in the plant design and on compliance with the requirements and terms stipulated in the course of the licensing process. On this basis, the State supervisory activity concentrates on the quality assurance of components and installations important for nuclear safety, on the quality of operating personnel and on compliance with limits and conditions for safe operation. The paper presents the main requirements stipulated in Regulation No.5 on quality assurance issued by the Czechoslovak Atomic Energy Commission and shows how the regulation is being applied. The conditions and modes of proving compliance with quality assurance programmes during plant implementation (design, fabrication, assembly, commissioning) and plant operation are described. The qualification prerequisites and capability requirements for selected categories of operating personnel as stipulated in the existing regulations are outlined. The experience accumulated by the regulatory body in preparing, examining and supervising the activity of the personnel is described. Consideration is given to the question of operational management, with the emphasis on compliance with the limits and conditions for safe operation and on the procedures for their alteration and for reporting infringements. (author)

  9. Fuel Supply Shutdown Facility Interim Operational Safety Requirements

    International Nuclear Information System (INIS)

    BENECKE, M.W.

    2000-01-01

    The Interim Operational Safety Requirements for the Fuel Supply Shutdown (FSS) Facility define acceptable conditions, safe boundaries, bases thereof, and management of administrative controls to ensure safe operation of the facility

  10. Safe operation of power plants. Pt. 1

    International Nuclear Information System (INIS)

    Freymeyer, P.

    1977-01-01

    Electrotechniques were given a dominating role in the construction of nuclear power plants. The operation of power plants - particularly nuclear power plants - is impossible without the use of electrotechnical and control means. Despite of all reserve in the development and despite of the conservative attitude it is necessary to use the newest results of development and to incite the development ot new electronic systems for the solution of these tasks. (orig.) [de

  11. A completely automatic operation type super-safe fast reactor, RAPID. Its application to dispersion source on lunar and earth surfaces

    International Nuclear Information System (INIS)

    Kanbe, Mitsuru; Tsunoda, Hirokazu; Mishima, Kaichiro; Kawasaki, Akira; Iwamura, Takamichi

    2002-01-01

    At a viewpoint of flexible measures to future electric power demands, expectation onto a small-scale reactor for dispersion source is increasing gradually. This is thought to increase its importance not only for a source at proximity of its market in advanced nations but also for the one in developing nations. A study on development of the completely automatic operation type super-safe fast reactor, RAPID (refueling by all pins integrated design) has been carried out as a part of the nuclear energy basic research promoting system under three years project since 1999 by a trust of the Japan Atomic Energy Research Institute to a group of the Central Research Institute of Electric Power Industry (CRIEPI) and so on. As the reactor is a lithium cooled fast reactor with 200 Kw of electric output supposing to use at lunar surface, it can be applied to a super-small scale nuclear reactor on the earth, and has feasibility to become a new option of future nuclear power generation. On the other hand, CRIEPI has investigated on various types of fast reactors (RAPID series) for fast reactor for dispersion source on the earth. Here was introduced on such super-safe fast reactors at a center of RAPID-L. (G.K.)

  12. Flow reversal power limit for the HFBR

    International Nuclear Information System (INIS)

    Cheng, L.Y.; Tichler, P.R.

    1997-01-01

    The High Flux Beam Reactor (HFBR) is a pressurized heavy water moderated and cooled research reactor that began operation at 40 MW. The reactor was subsequently upgraded to 60 MW and operated at that level for several years. The reactor undergoes a buoyancy-driven reversal of flow in the reactor core following certain postulated accidents. Questions which were raised about the afterheat removal capability during the flow reversal transition led to a reactor shutdown and subsequent resumption of operation at a reduced power of 30 MW. An experimental and analytical program to address these questions is described in this report. The experiments were single channel flow reversal tests under a range of conditions. The analytical phase involved simulations of the tests to benchmark the physical models and development of a criterion for dryout. The criterion is then used in simulations of reactor accidents to determine a safe operating power level. It is concluded that the limit on the HFBR operating power with respect to the issue of flow reversal is in excess of 60 MW. Direct use of the experimental results and an understanding of the governing phenomenology supports this conclusion

  13. High Blood Pressure and Cold Remedies: Which Are Safe?

    Science.gov (United States)

    ... counter cold remedies safe for people who have high blood pressure? Answers from Sheldon G. Sheps, M.D. Over- ... remedies aren't off-limits if you have high blood pressure, but it's important to make careful choices. Among ...

  14. The operation and maintenance manual

    International Nuclear Information System (INIS)

    Stoll, A.; Krotil, H.; Klein, W.

    1976-01-01

    The operating manual is one of many technical documents which the nuclear power plant operator needs for ensuring safe operation. For the operating staff, however, there is only one document, namely the operating manual. The operating manual is an essential element in bringing man and machine in harmony. This is necessary for safe and, as far as possible, uninterrupted operation of the power plant. The operating manual is the only document containing binding instructions for plant operation. All the tasks of plant operation which are carried out by plant staff are described in the operating manual in a form which is as clear and comprehensible as possible. A considerable number of these tasks can only be carried out by man, namely: 1) tasks concerning operational organization, 2) all non-automated areas of plant operation. (orig./TK) [de

  15. Road Map for Ageing Management and Safe Long Term Operation of Light Water Reactors in Japan

    International Nuclear Information System (INIS)

    Kanno, M.; Sakamoto, H.; Sekimura, N.

    2012-01-01

    The Nuclear Regulatory Authority (tentativename) will be established under the Ministry of Environment, aiming at independent regulatory decision making. Limit of operation to 40 years will be regulated. As an exception, extension of a certain period (<20 years) will be approved only one time when compliance with the regulatory standards is confirmed. It is necessary on a technical information basis to check and evaluate the utilities' activities of the ageing management technical evaluation by the new regulatory organization. Technical information and knowledge-bases for the design, construction, operation and maintenance of nuclear power plants should be utilized comprehensively not only for utilities but also for the regulatory orgnazation. Obsolesce of codes and standards may bring weakness in defense in depth, or higher core damage frequency. Investigation of the aged and thermal material is effective for proactive management and sophistication of codes and standards for ageing managementoflong term operation. (author)

  16. Safe Kids Worldwide

    Science.gov (United States)

    ... Blog Videos Newsletter facebook twitter instagram pinterest gplus youtube Search Menu Why It Matters Who We Are What We Do Find Your Safe Kids Safe Kids Day Main menu Keeping All Kids Safe Safety Tips Get Involved 4 Star Charity Donate Text Burns and Scalds 4 tips ...

  17. The limitations in implementing and operating a rapid response system.

    Science.gov (United States)

    Subramaniam, A; Botha, J; Tiruvoipati, R

    2016-10-01

    Despite the widespread introduction of rapid response systems (RRS)/medical emergency teams (MET), there is still controversy regarding how effective they are. While there are some observational studies showing improved outcomes with RRS, there are no data from randomised controlled trials to support the effectiveness. Nevertheless, the MET system has become a standard of care in many healthcare organisations. In this review, we present an overview of the limitations in implementing and operating a RRS in modern healthcare. © 2016 Royal Australasian College of Physicians.

  18. Safe pill-dispensing.

    Science.gov (United States)

    Testa, Massimiliano; Pollard, John

    2007-01-01

    Each patient is supplied with a smart-card containing a Radio Frequency IDentification (RFID) chip storing a unique identification code. The patient places the Smart-card on a pill-dispenser unit containing an RFID reader. The RFID chip is read and the code sent to a Base-station via a wireless Bluetooth link. A database containing both patient details and treatment information is queried at the Base-station using the RFID as the search key. The patient's treatment data (i.e., drug names, quantities, time, etc.) are retrieved and sent back to the pill-dispenser unit via Bluetooth. Appropriate quantities of the required medications are automatically dispensed, unless the patient has already taken his/her daily dose. Safe, confidential communication and operation is ensured.

  19. 46 CFR 117.205 - Survival craft-vessels operating on limited coastwise routes.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Survival craft-vessels operating on limited coastwise... PASSENGERS LIFESAVING EQUIPMENT AND ARRANGEMENTS Number and Type of Survival Craft § 117.205 Survival craft... the survival craft required by §§ 117.204 (a) through (d) of this part, as applicable. (b) Each vessel...

  20. A discussion on turbine design for safe operation

    International Nuclear Information System (INIS)

    Brekke, H

    2012-01-01

    The paper gives a brief description of the hydraulic design of Francis and Pelton runners. The dynamic behaviour at part load has been a major problem for low head and medium head Francis turbines. The main reason for this has been inter blade separation and unstable swirl flow in the draft tube. A description is given on the hydraulic design of X-BLADE runners to obtain stable operation on the whole range of operation by reducing the cross flow. A classical theoretical analysis is also given on the dynamic hydraulic load on Pelton buckets. Several CFD analyses of this non stationary flow have been presented during the last decade, but the velocity distribution in the jets have not been correct. Experimental research work is presented on the complexity of this problem.

  1. A discussion on turbine design for safe operation

    Science.gov (United States)

    Brekke, H.

    2012-11-01

    The paper gives a brief description of the hydraulic design of Francis and Pelton runners. The dynamic behaviour at part load has been a major problem for low head and medium head Francis turbines. The main reason for this has been inter blade separation and unstable swirl flow in the draft tube. A description is given on the hydraulic design of X-BLADE runners to obtain stable operation on the whole range of operation by reducing the cross flow. A classical theoretical analysis is also given on the dynamic hydraulic load on Pelton buckets. Several CFD analyses of this non stationary flow have been presented during the last decade, but the velocity distribution in the jets have not been correct. Experimental research work is presented on the complexity of this problem.

  2. Market potential of superconductor current limiters; Marktpotential von supraleitenden Strombegrenzern

    Energy Technology Data Exchange (ETDEWEB)

    Lakner, M.; Braun, D. [ABB Schweiz AG, Corporate Research, Baden-Daettwil (Switzerland); Schnyder, G.; Mauchle, P. [Schnyder Ingenieure AG, Huenenberg (Switzerland)

    2003-07-01

    This final report for the Swiss Federal Office of Energy describes the two concepts - 'resistive' and 'inductive' - used for Superconducting Fault Current Limiters (SCFCL) that utilise the transition from zero to finite resistance to limit short-circuit currents. The main advantages of SCFCL are compared to other current-limiting technologies: They can limit any type of prospective fault current, operate fail-safe, be self-triggered and self-restoring. Their main disadvantage - the cooling effort necessary - is also discussed. The application possibilities of SCFCL were investigated by simulating the impact on utility and industrial grids. Applications of SCFCL such as the coupling of medium-voltage grids and their use in series with a circuit-breaker on the secondary side of a substation transformer are discussed. It is also shown that, by using fault current limiters, considerable cost savings can be made, especially in connection with new installations or the extension of existing plants.

  3. Methods to assess bioavailability of hydrophobic organic contaminants: Principles, operations, and limitations

    International Nuclear Information System (INIS)

    Cui Xinyi; Mayer, Philipp; Gan, Jay

    2013-01-01

    Many important environmental contaminants are hydrophobic organic contaminants (HOCs), which include PCBs, PAHs, PBDEs, DDT and other chlorinated insecticides, among others. Owing to their strong hydrophobicity, HOCs have their final destination in soil or sediment, where their ecotoxicological effects are closely regulated by sorption and thus bioavailability. The last two decades have seen a dramatic increase in research efforts in developing and applying partitioning based methods and biomimetic extractions for measuring HOC bioavailability. However, the many variations of both analytical methods and associated measurement endpoints are often a source of confusion for users. In this review, we distinguish the most commonly used analytical approaches based on their measurement objectives, and illustrate their practical operational steps, strengths and limitations using simple flowcharts. This review may serve as guidance for new users on the selection and use of established methods, and a reference for experienced investigators to identify potential topics for further research. - This review summarizes the principles and operations of bioavailability prediction methods, discusses their strengths and limitations, and highlights issues for future research.

  4. Analytical and experimental justification of safe operation of fuel loads of VVER reactors at Rovno NPP

    International Nuclear Information System (INIS)

    Andrianov, A.; Zagrebelny, L.

    2011-01-01

    The main task during the nuclear fuel operation us ensuring of the larger fuel burnup and as a result - reduction of the fuel constituent in the electricity production cost. The neutron-physic calculations are performed using the qualified codes BIPR-7A and PERMAK developed by Kurchatov Institute. The limits for calculated parameters are set by the Ukrainian regulations. Calculation results are documented in reports subject for independent expert review requested by the regulatory authority. In this report the following item have presented: 1) metrological check and calibration of measuring channels; 2) fuel cycles at Rivne NPP; 3) determination of experimental values of thermal-physic and neutron-physic parameters; 4) ICIS equipment check, execution of the program confirming correct connection of the temperature and neutron flux monitoring sensors; 5) monitoring of the core TPh and NPh parameters in all operating modes; 6) monitoring of the fuel condition in the core and 7) FE leak tightness monitoring at the operating reactor

  5. Final hazard classification and auditable safety analysis for the 105-C Reactor Interim Safe Storage Project

    International Nuclear Information System (INIS)

    Rodovsky, T.J.; Larson, A.R.; Dexheimer, D.

    1996-12-01

    This document summarizes the inventories of radioactive and hazardous materials present in the 105-C Reactor Facility and the operations associated with the Interim Safe Storage Project which includes decontamination and demolition and interim safe storage of the remaining facility. This document also establishes a final hazard classification and verifies that appropriate and adequate safety functions and controls are in place to reduce or mitigate the risk associated with those operations

  6. Seismic-safe conditions of blasting near pressure pipe-lines during power installation construction

    International Nuclear Information System (INIS)

    Smolij, N.I.; Nikitin, A.S.

    1980-01-01

    Seismic-safe conditions for performing drill-blasting operations in the vicinity of underground gas pipelines when constructing thermal- or nuclear power plants are discussed. It is shown that, for the determination of seismic-safe parameters, of drill-blasting operations, the maximum permissible level of seismic loads should be specified taking into account the mechanical properties of the pipeline.metal, structural parameters of the gas pipeline and the pressure of the medium transported. Besides, the seismic effect of the blast should be considered with regard to particular conditions of blasting and rock properties. The equations and diagrams used in the calculation are given

  7. The Cost of SOx Limits to Marine Operators; Results from Exploring Marine Fuel Prices

    Directory of Open Access Journals (Sweden)

    Orestis Schinas

    2013-06-01

    Full Text Available Marine operators are confronted with the new air emissions regulations that determine the limits of sulfur content in marine fuels. The low-sulfur (LS marine fuels have a higher price, and their fluctuation is almost similar to the fluctuation of high-sulfur (HS fuels. The price difference between HS and LS might also determine the decision of operators for alternative technical means, such as scrubbers, in order to comply with the new limits. This paper aims to provide a thorough statistical analysis of the currently available LS and HS marine fuels time series, as well as to present the analysis of the differential of the HS and LS fuel prices. The paper concludes with suggestions for further research.

  8. Cost-competitive, inherently safe LFMBR pool plant

    International Nuclear Information System (INIS)

    McDonald, J.S.; Brunings, J.E.; Chang, Y.I.; Hren, R.R.; Seidensticker, R.W.

    1984-01-01

    The Cost-Competitive, Inherently Safe LMFBR Pool Plant design was prepared in GFY 1983 under a DOE-sponsored program. This plant design was developed as a joint effort by Rockwell International and the Argonne National Laboratory with major contributions from the Bechtel Group, Inc.; Combustion engineering, Inc.; the Chicago Bridge and Iron Company; and the General Electric Company. Using current LMFBR technology, many innovative features were developed and incorporated into the design to meet the ultimate objectives of the Breeder Program, i.e., energy costs competitive with LWRs and inherent safety features to maintain the plant in a safe condition following assumed accidents without requiring operator action. This paper provides a description of the principal features that were incorporated into the design to achieve low cost and inherent safety

  9. Supplement analysis for the proposed upgrades to the tank farm ventilation, instrumentation, and electrical systems under Project W-314 in support of tank farm restoration and safe operations

    International Nuclear Information System (INIS)

    1997-05-01

    The mission of the TWRS program is to store, treat, and immobilize highly radioactive tank waste in an environmentally sound, safe, and cost-effective manner. Within this program, Project W-314, Tank Farm Restoration and Safe Operations, has been established to provide upgrades in the areas of instrumentation and control, tank ventilation, waste transfer, and electrical distribution for existing tank farm facilities. Requirements for tank farm infrastructure upgrades to support safe storage were being developed under Project W-314 at the same time that the TWRS EIS alternative analysis was being performed. Project W-314 provides essential tank farm infrastructure upgrades to support continued safe storage of existing tank wastes until the wastes can be retrieved and disposed of through follow-on TWRS program efforts. Section4.0 provides a description of actions associated with Project W-314. The TWRS EIS analyzes the environmental consequences form the entire TWRS program, including actions similar to those described for Project W-314 as a part of continued tank farm operations. The TWRS EIS preferred alternative was developed to a conceptual level of detail to assess bounding impact areas. For this Supplement Analysis, in each of the potential impact areas for Project W-314, the proposed action was evaluated and compared to the TWRS EIS evaluation of the preferred alternative (Section 5.0). Qualitative and/or quantitative comparisons are then provided in this Supplement Analysis to support a determination on the need for additional National Environmental Policy Act (NEPA) analysis. Based on this Supplement Analysis, the potential impacts for Project W-314 would be small in comparison to and are bounded by the impacts assessed for the TWRS EIS preferred alternative, and therefore no additional NEPA analysis is required (Section 7.0)

  10. Project management plan for Reactor 105-C Interim Safe Storage project

    International Nuclear Information System (INIS)

    Plagge, H.A.

    1996-09-01

    Reactor 105-C (located on the Hanford Site in Richland, Washington) will be placed into an interim safe storage condition such that (1) interim inspection can be limited to a 5-year frequency; (2) containment ensures that releases to the environmental are not credible under design basis conditions; and (3) final safe storage configuration shall not preclude or significantly increase the cost for any decommissioning alternatives for the reactor assembly.This project management plan establishes plans, organizational responsibilities, control systems, and procedures for managing the execution of Reactor 105-C interim safe storage activities to meet programmatic requirements within authorized funding and approved schedules

  11. "Same Room, Safe Place".

    Science.gov (United States)

    Keene Woods, Nikki

    2017-04-01

    There are many different professional stances on safe sleep and then there is the reality of caring for a newborn. There is a debate among professionals regarding safe sleep recommendations. The continum of recommendations vary from the American Academy of Pediatrics (AAP) Safe Sleep Guidelines to the bed-sharing recommendations from the Mother-Baby Behavioral Sleep Laboratory. The lack of consistent and uniform safe sleep recommendations from health professionals has been confusing for families but has more recently raised a real professional ethical dilemma. Despite years of focused safe sleep community education and interventions, sleep-related infant deaths are on the rise in many communities. This commentary calls for a united safe sleep message from all health professionals to improve health for mothers and infants most at-risk, "Same Room, Safe Place."

  12. Unsupervised laparoscopic appendicectomy by surgical trainees is safe and time-effective.

    Science.gov (United States)

    Wong, Kenneth; Duncan, Tristram; Pearson, Andrew

    2007-07-01

    Open appendicectomy is the traditional standard treatment for appendicitis. Laparoscopic appendicectomy is perceived as a procedure with greater potential for complications and longer operative times. This paper examines the hypothesis that unsupervised laparoscopic appendicectomy by surgical trainees is a safe and time-effective valid alternative. Medical records, operating theatre records and histopathology reports of all patients undergoing laparoscopic and open appendicectomy over a 15-month period in two hospitals within an area health service were retrospectively reviewed. Data were analysed to compare patient features, pathology findings, operative times, complications, readmissions and mortality between laparoscopic and open groups and between unsupervised surgical trainee operators versus consultant surgeon operators. A total of 143 laparoscopic and 222 open appendicectomies were reviewed. Unsupervised trainees performed 64% of the laparoscopic appendicectomies and 55% of the open appendicectomies. There were no significant differences in complication rates, readmissions, mortality and length of stay between laparoscopic and open appendicectomy groups or between trainee and consultant surgeon operators. Conversion rates (laparoscopic to open approach) were similar for trainees and consultants. Unsupervised senior surgical trainees did not take significantly longer to perform laparoscopic appendicectomy when compared to unsupervised trainee-performed open appendicectomy. Unsupervised laparoscopic appendicectomy by surgical trainees is safe and time-effective.

  13. Designing visual displays and system models for safe reactor operations

    Energy Technology Data Exchange (ETDEWEB)

    Brown-VanHoozer, S.A.

    1995-12-31

    The material presented in this paper is based on two studies involving the design of visual displays and the user`s prospective model of a system. The studies involve a methodology known as Neuro-Linguistic Programming and its use in expanding design choices from the operator`s perspective image. The contents of this paper focuses on the studies and how they are applicable to the safety of operating reactors.

  14. Bisexual Safe Space(s) on the Internet: Analysis of an Online Forum for Bisexuals

    NARCIS (Netherlands)

    Maliepaard, E.M.

    2017-01-01

    Discussions on bisexual safe space(s) and online bisexual spaces are limited. This paper explores the potential of an online forum for bisexuals, their partners, and people who are interested in bisexuality to function as an online safe space. To understand whether the analysed forum is successful

  15. An analysis of the proposed MITR-III core to establish thermal-hydraulic limits at 10 MW. Final report

    International Nuclear Information System (INIS)

    Harling, O.K.; Lanning, D.D.; Bernard, J.A.; Meyer, J.E.; Henry, A.F.

    1997-01-01

    The 5 MW Massachusetts Institute of Technology Research Reactor (MITR-II) is expected to operate under a new license beginning in 1999. Among the options being considered is an upgrade in the heat removal system to allow operation at 10 MW. The purpose of this study is to predict the Limiting Safety System Settings and Safety Limits for the upgraded reactor (MITR-III). The MITR Multi-Channel Analysis Code was written to analyze the response of the MITR system to a series of anticipated transients in order to determine the Limiting Safety System Settings and Safety Limits under various operating conditions. The MIT Multi-Channel Analysis Code models the primary and secondary systems, with special emphasis placed on analyzing the thermal-hydraulic conditions in the core. The code models each MITR fuel element explicitly in order to predict the behavior of the system during flow instabilities. The results of the code are compared to experimental data from MITR-II and other sources. New definitions are suggested for the Limiting Safety System Settings and Safety Limits. MITR Limit Diagrams are included for three different heat removal system configurations. It is concluded that safe, year-round operating at 10 MW is possible, given that the primary and secondary flow rates are both increased by approximately 40%

  16. 40 CFR Table 9 to Subpart Uuu of... - Operating Limits for Organic HAP Emissions From Catalytic Cracking Units

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Operating Limits for Organic HAP Emissions From Catalytic Cracking Units 9 Table 9 to Subpart UUU of Part 63 Protection of Environment..., Subpt. UUU, Table 9 Table 9 to Subpart UUU of Part 63—Operating Limits for Organic HAP Emissions From...

  17. 40 CFR Table 16 to Subpart Uuu of... - Operating Limits for Organic HAP Emissions From Catalytic Reforming Units

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Operating Limits for Organic HAP Emissions From Catalytic Reforming Units 16 Table 16 to Subpart UUU of Part 63 Protection of Environment..., Subpt. UUU, Table 16 Table 16 to Subpart UUU of Part 63—Operating Limits for Organic HAP Emissions From...

  18. Safe Driving After Propofol Sedation.

    Science.gov (United States)

    Summerlin-Grady, Lee; Austin, Paul N; Gabaldon, Dion A

    2017-10-01

    Propofol is a short-acting medication with fast cognitive and psychomotor recovery. However, patients are usually instructed not to drive a motor vehicle for 24 hours after receiving propofol. The purpose of this article was to review the evidence examining when it is safe to drive after receiving propofol for sedation for diagnostic and surgical procedures. This is a systematic review of the literature. A search of the literature was conducted using Google Scholar, PubMed, and the Cochrane Library for the time period 1990 to 2015. Two randomized controlled trials and two observational studies met the inclusion criteria. Using a simulator, investigators examined driving ability of subjects who received modest doses (about 100 mg) of propofol for endoscopic procedures and surveyed subjects who drove immediately after discharge. There were methodological concerns with the studies such as small sample sizes, modest doses of propofol, and three of the four studies were done in Japan by the same group of investigators limiting generalizability. This limited research suggests that it may be safe for patients to drive sooner than 24 hours after receiving propofol. However, large multicenter trials using heterogenous samples using a range of propofol doses are needed to support an evidence-based revision to the current discharge guidelines for patients receiving propofol. Copyright © 2016 American Society of PeriAnesthesia Nurses. Published by Elsevier Inc. All rights reserved.

  19. Quality assurance for the safe transport of radioactive material

    International Nuclear Information System (INIS)

    1994-01-01

    All activities related to the safe transport of radioactive material should be covered by a quality assurance programme. This publication recognizes that a single transport operation often involves several different organizations, each having specific responsibilities. Hence, it is unlikely that the operation will be covered by a single quality assurance programme. Each quality assurance programme should be tailored to the specific organizational structure for which the programme is prepared, with account taken of the particular transport activities of that organization and the interfaces with other organizations. The aim of this publication is to give a detailed interpretation of what must be done by whom to produce a quality assurance programme for radioactive material transport. This publication provides guidance on methods and practical examples to develop QA programmes for the safe transport of radioactive material. It provides information on how to develop the programme, the standards and the common features of a QA programme

  20. 40 CFR 63.9324 - How do I establish the emission capture system and add-on control device operating limits during...

    Science.gov (United States)

    2010-07-01

    ... capture system and add-on control device operating limits during the performance test? 63.9324 Section 63... Requirements § 63.9324 How do I establish the emission capture system and add-on control device operating... the operating limits required by § 63.9302 according to this section, unless you have received...

  1. Safe and Automatic Live Update for Operating Systems

    NARCIS (Netherlands)

    Giuffrida, C.; Kuijsten, A.; Tanenbaum, A.S.

    2013-01-01

    Increasingly many systems have to run all the time with no downtime allowed. Consider, for example, systems controlling electric power plants and e-banking servers. Nevertheless, security patches and a constant stream of new operating system versions need to be deployed without stopping running

  2. Continuum limit of overlap valence quarks on a twisted mass sea

    International Nuclear Information System (INIS)

    Cichy, Krzysztof; Herdoiza, Gregorio; Univ. Autonoma de Madrid; Jansen, Karl

    2010-12-01

    We study a lattice QCD mixed action with overlap valence quarks on two flavours of Wilson maximally twisted mass sea quarks. Employing three different matching conditions to relate both actions to each other, we investigate the continuum limit by using three values of the lattice spacing ranging from a∼0.05 fm to 0.08 fm. A particular emphasis is put on the effect on physical observables of the topological zero modes appearing in the valence overlap operator. We estimate the region of parameter space where the contribution from these zero modes is sufficiently small such that their effects can be safely controlled and a restoration of unitarity of the mixed action in the continuum limit is reached. (orig.)

  3. Limited field investigation report for the 100-KR-4 Operable Unit

    International Nuclear Information System (INIS)

    1994-07-01

    This limited field investigation (LFI) was conducted to optimize the use of interim remedial measures (IRM) for expediting clean up while maintaining a technically sound and cost-effective program. The 100-KR-4 Operable Unit is one of four operable units associated with the 100 K Area. Operable units KR-1, KR-2 and KR-3 address contaminant sources while 100-KR-4 addresses contamination present in the underlying groundwater. The IRM decision process for groundwater operable units is based on three aspects: (1) Is the concentration greater than Hanford background? (2) Does the concentration present a medium or high human-health risk? (3) Does the concentration exceed an ecologically based applicable, relevant and appropriate requirements (ARAR) or present an environmental hazard quotient > I? The primary methods of investigation used during this LFI were the installation of monitoring wells and sampling of groundwater. The samples collected from the groundwater and soils were submitted for laboratory analysis. Boreholes were surveyed for radiological contamination using downhole geophysical techniques to further delineate the location and degree of contamination. All soil samples were screened to ascertain the presence of volatile organic compounds and radionuclides. Analytical data were subjected to validation; all first round and a minimum of 10% of subsequent round data were validated

  4. Limited field investigation report for the 100-DR-1 Operable Unit

    International Nuclear Information System (INIS)

    1994-06-01

    This limited field investigation (LFI) report summarizes the data collection and analysis activities conducted during the 100-DR-1 Source Operable Unite LFI and the associated qualitative risk assessment (QRA), and makes recommendations on the continued candidacy of high-priority sites for interim remedial measures (IRM). The results and recommendations presented in this report are generally independent of future land use scenarios. The 100-DR-1 Operable Unit is one of four operable units associated with the 100 D/DR Area at the Hanford Site. The 100-DR-1 Operable Unit encompasses approximately 1.5 km 2 (0.59 mi 2 ) and is located immediately adjacent to the Columbia River shoreline. In general, it contains waste facilities associated with the original plant facilities constructed to support D Reactor facilities, as well as cooling water retention basin systems for both D and DR Reactors. The 100-DR-1 LFI began the investigative phase of the remedial investigation for a select number of high-priority sites. The LFI was performed to provide additional data needed to support selection, design and implementation of IRM, if needed. The LFI included data compilation, nonintrusive investigations, intrusive investigations, summarization of 100 Area aggregate studies, and data evaluation

  5. original article predictors of safe delivery service utilization in arsi

    African Journals Online (AJOL)

    Abrham

    There is limited information on the mothers' use of skilled delivery services in the ... edited, cleaned, and entered into a computer and analyzed using SPSS for ... education and communication on safe delivery service utilization, expansion of ...

  6. Operation of multiple superconducting energy doubler magnets in series

    International Nuclear Information System (INIS)

    Kalbfleisch, G.; Limon, P.J.; Rode, C.

    1977-01-01

    In order to understand the operational characteristics of the Energy Doubler, a series of experiments were begun which were designed to be a practical test of running superconducting accelerator magnets in series. Two separate tests in which two Energy Doubler dipoles were powered in series are described. Of particular interest are the static losses of the cryostats and the behavior of the coils and cryostats during quenches. The results of the tests show that Energy Doubler magnets can be safely operated near their short sample limit, and that the various safety devices used are adequate to protect the coils and the cryostats from damage

  7. Operational characteristics of nuclear power plants - modelling of operational safety; Pogonske karakteristike nuklearnih elektrana - modelsko izucavanje pogonske sigurnosti

    Energy Technology Data Exchange (ETDEWEB)

    Studovic, M [Masinski fakultet, Beograd (Yugoslavia)

    1984-07-01

    By operational experience of nuclear power plants and realize dlevel of availability of plant, systems and componenst reliabiliuty, operational safety and public protection, as a source on nature of distrurbances in power plant systems and lessons drawn by the TMI-2, in th epaper are discussed: examination of design safety for ultimate ensuring of safe operational conditions of the nuclear power plant; significance of the adequate action for keeping proess parameters in prescribed limits and reactor cooling rquirements; developed systems for measurements detection and monitoring all critical parameters in the nuclear steam supply system; contents of theoretical investigation and mathematical modeling of the physical phenomena and process in nuclear power plant system and components as software, supporting for ensuring of operational safety and new access in staff education process; program and progress of the investigation of some physical phenomena and mathematical modeling of nuclear plant transients, prepared at faculty of mechanical Engineering in Belgrade. (author)

  8. Beznau II nuclear power plant: Expertise on NOK's request for the removal of the time limitation for the operation licence; KKW Beznau II: Gutachten zum Gesuch der NOK um Aufhebung der Befristung der Betriebsbewilligung

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-03-15

    The Federal Agency for the Safety of Nuclear Installations (HSK) is the Swiss authority responsible for nuclear safety and protection against radioactivity in nuclear power plants. It has to examine the request of the North-East Swiss Power Corporation (NOK) concerning the removal of the operational time limitation for the Beznau-II reactor (KKB-II). In the present report HSK reviews the enterprise management and the safety of KKB-II on the basis of the results of the Periodic Safety Review. The Beznau nuclear power plant exhibits a very high degree of technical and organisational safety. During the past 10 years the plant has been operated in a safe manner. At the same time the plant has been improved and this guarantees that the mechanisms of ageing degradation are systematically identified and that measures can be taken that are possibly necessary. Under such conditions, the safety of KKB-II can be guarantied at all times. As a result of the management of quality, environmental and working safety conditions, the correct application and the continuous improvement of all processes important to safety are ensured. With these measures KKB has shown that safety is given priority over and against all other working goals. The examination by HSK of the Periodic Safety Review has shown that, in the past, KKB has applied modernisation measures independent of the licensing situation of the two reactor blocks. These modernisation measures largely contribute to the fact that the HSK examination did not reveal any significant safety deficiencies. Other improvement measures allow risk reduction or can bee seen as an adaptation to experience gained and to the state of the technological art. In conclusion, HSK states that no safety-relevant facts have been found which could prevent the removal of the time limitation on the operational licence for KKB-II. From the point of view of HSK, KKB-II fulfils the conditions for the safe continuation of operation

  9. Operating limits on commutator dc machines used as electromechanical capacitors

    International Nuclear Information System (INIS)

    Thullen, P.

    1981-01-01

    This paper presents data gathered in testing 28 rebuilt motors and discusses the impact of possible variation of characteristics among the machines of the operation of the facility. It also discusses commutation limits and their relationship to the economics and reliability of the system. When installed, the system will consist of 30 motors and will have a rating of 50 kA, 1.68 kV corresponding to 84 MVA at a peak power of 42 MW. The cost of this supply will be near $6/kVA which continues to compare favorably with the present $30/kVA cost of alternators

  10. Conduct of operations: establishing operational focus and setting operational standards

    International Nuclear Information System (INIS)

    Lane, L.; McGuigan, K.

    1998-01-01

    Due to the nature of our business, we have often tended to focus on the technological aspects of the nuclear industry. The focus of this paper is directed towards the importance of addressing the people skills, attitudes, and 'culture' within, and surrounding, our facilities as key areas of improvement. Within Ontario Hydro Nuclear (OLIN) we have developed the terminology 'event free' operation and 'event free' culture. 'Event Free' recognizes errors as a part of human performance. 'Event Free' takes into account human weaknesses, and provides tools (such as standards) to manage, control, and mitigate errors. In essence, 'Event Free' encompasses two concepts: 1. Prevent errors from occurring; 2. If an error is made, catch it before it can affect safe operation of the facility, learn from the error, and ensure that it does not happen again. In addressing these business realities, Ontario Hydro has identified a number of key support mechanisms and corresponding performance standards that are essential for achieving operating excellence and an 'event free' business culture. This paper will discuss two operational aspects of an 'event free' culture, the first being a set of expectations to enhance the culture, and the second an example of cultural change: 1. Operating Standards - establishing clear expectations for human performance in operating staff; 2. Operational Focus - the understanding that, as a nuclear worker, you should consider every task, activity, in fact everything you do in this business, for the potential to affect safe and reliable operation of a nuclear facility. Note that although the term 'Operational' appears in the title, this concept applies to every individual in the nuclear business, from the cleaner, to the Board of Directors, to the external supplier. (author)

  11. Concept of passive safe small reactor for distributed energy supply system

    International Nuclear Information System (INIS)

    Ishida, Toshihisa; Nakajima, Nobuya; Sawada, Ken-ichi; Yoritsune, Tsutomu; Shimada, Shoichiro; Nakano, Yoshihiro; Yonomoto, Taisuke; Takahashi, Hiroki

    2003-01-01

    This paper presents a concept of a Passive Safe Small Reactor for Distributed energy supply system (PSRD). The PSRD is an integrated-type PWR with reactor thermal power of 100 to 300 MW aimed at supplying electricity, district heating, etc. In design of the PSRD, high priority is laid on enhancement of safety as well as improvement of economy. Safety is enhanced by the following means: i) Extreme reduction of pipes penetrating the reactor vessel, by limiting to only those of the steam, the feed water and the safety valves, ii) Adoption of the water filled containment and the passive safety systems with fluid driven by natural circulation force, and iii) Adoption of the in-vessel type control rod drive mechanism, accompanying a passive reactor shut-down. To comply with a severe operation condition of PSRD, material of the ball bearing with graphite retainer has been selected by test. For improvement of economy, simplification of the reactor system and long operation of the core are achieved. Optimization of core design concerning the burnable poison ensures the burn-up of 28 GWd/t for low enriched UO 2 fuel rods. (author)

  12. Safe management of sealed radioactive sources at Karachi nuclear power complex

    International Nuclear Information System (INIS)

    Tahir, T.B.; Qamar, A.

    2000-01-01

    This paper describes the conditioning of sealed radioactive sources, carried out at the Karachi Nuclear Power Complex (KNPC) in co-operation with the IAEA. The radioactive sources were radium needles of various size, used by various radiotherapy units in different hospitals throughout the country. For some time the use of radium needles had been abandoned and they were stored in hospitals awaiting proper disposal. Since their storage conditions were not ideal and there was a potential of leakage of radioactive material into the environment, it was decided to condition and store them safely. A significant logistic effort was required to identify these sources, bring them to a central facility and condition them according to current international standards. Various steps were involved in conditioning the sources: place it in a stainless steel capsule, weld the capsule, test it for a leak, place the capsule in a lead shielded package, put and seal the shielded package in a concrete-lined steel drum and finally store it at the waste storage facility. A total amount of about 1500 mg of Radium needles were conditioned. Radiation exposure during the entire operation was within acceptable limits. (author)

  13. Regional training course on safe transport of radioactive material. Folder documentation

    International Nuclear Information System (INIS)

    1999-01-01

    Folder including documentation distributed to the participants to the International Atomic Energy Agency (IAEA) Regional Training Course on Safe Transport of Radioactive Material organised by the IAEA in co-operation with the Government of Argentina through the Nuclear Regulatory Authority, held in Buenos Aires, Argentina, 13 September -1 October 1999. The course was intended to people from IAEA Member States in the Latin American and Caribbean region. The instruction language was spanish and some lectures was delivered in english. The documentation was Spanish and some lectures was delivered in English. The documentation was in Spanish and included: copies of transparencies used during lectures, exercises of application, main training document (introduction; shipments of radioactive material; applicable regulations; basic principles; scope and objective of the IAEA Transport Regulations; package design requirements; type of packages and their contents limits; Q system; special form radioactive material requirements; radiation protection requirements; fissile material transport requirements; controls, contamination, radiation level, transport index; operational and administrative requirements; consignors' responsibilities; approval certificates, transport under special arrangements; emergency planning and procedures; physical protection aspects during transport. Guidelines for consignors, radiation detectors, complement to the training manual on main changes included in the 1996 Edition of IAEA Transport Regulations

  14. Determination of rod insertion limits of the AP600'S M-shim bank at low power operating mode

    International Nuclear Information System (INIS)

    Sutondo, Tegas

    2002-01-01

    A series of calculation works had been conducted to determine the AP00's M-shim bank insertion limits during low-power operating mode. This activity was a part of the preliminary studies toward the plan on implementation a Rapid Power Reduction System (RPRS) in AP00's control / operating system, that enable it to operate under low power level (below 50% RTP). The calculations were performed for cycle 1 and equilibrium cycle as function of power levels and the fraction of AO-bank insertion. The results show that the M-shim insertion limits for both cycle 1 and equilibrium cycle were determined based on the limiting conditions at low-burn-up level (BOL), and high burn-up level (EOL) respectively

  15. Validation of pig operations through pipelines

    Energy Technology Data Exchange (ETDEWEB)

    Tolmasquim, Sueli Tiomno [TRANSPETRO - PETROBRAS Transporte S.A., Rio de Janeiro, RJ (Brazil); Nieckele, Angela O. [Pontificia Univ. Catolica do Rio de Janeiro, RJ (Brazil). Dept. de Engenharia Mecanica

    2005-07-01

    In the oil industry, pigging operations in pipelines have been largely applied for different purposes: pipe cleaning, inspection, liquid removal and product separation, among others. An efficient and safe pigging operation requires that a number of operational parameters, such as maximum and minimum pressures in the pipeline and pig velocity, to be well evaluated during the planning stage and maintained within stipulated limits while the operation is accomplished. With the objective of providing an efficient tool to assist in the control and design of pig operations through pipelines, a numerical code was developed, based on a finite difference scheme, which allows the simulation of two fluid transient flow, like liquid-liquid, gas-gas or liquid-gas products in the pipeline. Modules to automatically control process variables were included to employ different strategies to reach an efficient operation. Different test cases were investigated, to corroborate the robustness of the methodology. To validate the methodology, the results obtained with the code were compared with a real liquid displacement operation of a section of the OSPAR oil pipeline, belonging to PETROBRAS, with 30'' diameter and 60 km length, presenting good agreement. (author)

  16. DroidSafe

    Science.gov (United States)

    2016-12-01

    Massachusetts Avenue, Build E19-750 Cambridge , MA 02139-4307 8. PERFORMING ORGANIZATION REPORT NUMBER 9. SPONSORING/MONITORING AGENCY NAME(S) AND ADDRESS...Activity objects illustrating the challenges of points-to and information flow analysis...measure how many malicious flows Droid- Safe was able to detect). As these results illustrate , DroidSafe implements an analysis of unprece- dented

  17. VCSELs in short-pulse operation for time-of-flight applications

    Science.gov (United States)

    Moench, Holger; Gronenborn, Stephan; Gu, Xi; Gudde, Ralph; Herper, Markus; Kolb, Johanna; Miller, Michael; Smeets, Michael; Weigl, Alexander

    2018-02-01

    VCSEL arrays are the ideal light source for 3D imaging applications. The narrow emission spectrum and the ability for short pulses make them superior to LEDs. Combined with fast photodiodes or special camera chips spatial information can be obtained which is needed in diverse applications like camera autofocus, indoor navigation, 3D-object recognition, augmented reality or autonomously driving vehicles. Pulse operation at the ns scale and at low duty cycle can work with significantly higher current than traditionally used for VCSELs in continuous wave operation. With reduced thermal limitations at low average heat dissipation very high currents become feasible and tens of Watts output power have been realized with small VCSEL chips. The optical emission pattern of VCSELs can be tailored to the desired field of view using beam shaping elements. Such optical elements also enable laser safe class 1 products. A detailed analysis of the complete system and the operation mode is required to calculate the maximum permitted power for a safe system. The good VCSEL properties like robustness, stability over temperature and the potential for integrated solutions open a huge potential for VCSELs in new mass applications in the consumer and automotive markets.

  18. Safe havens in Europe

    DEFF Research Database (Denmark)

    Paldam, Martin

    2013-01-01

    Eleven safe havens exist in Europe providing offshore banking and low taxes. Ten of these states are very small while Switzerland is moderately small. All 11 countries are richer than their large neighbors. It is shown that causality is from small to safe haven to wealth, and that theoretically...... equilibriums are likely to exist where a certain regulation is substantially lower in a small country than in its big neighbor. This generates a large capital inflow to the safe havens. The pool of funds that may reach the safe havens is shown to be huge. It is far in excess of the absorptive capacity...... of the safe havens, but it still explains, why they are rich. Microstates offer a veil of anonymity to funds passing through, and Switzerland offers safe storage of funds....

  19. Traveling Safely with Medicines

    Science.gov (United States)

    ... Medications Safely My Medicine List How to Administer Traveling Safely with Medicines Planes, trains, cars – even boats ... your trip, ask your pharmacist about how to travel safely with your medicines. Make sure that you ...

  20. Tritium Systems Test Assembly operator training program

    International Nuclear Information System (INIS)

    Kerstiens, F.L.

    1985-01-01

    Proper operator training is needed to help ensure the safe operation of fusion facilities by personnel who are qualified to carry out their assigned responsibilities. Operators control and monitor the Tritium Systems Test Assembly (TSTA) during normal, emergency, and maintenance phases. Their performance is critical both to operational safety, assuring no release of tritium to the atmosphere, and to the successful simulation of the fusion reaction progress. Through proper training we are helping assure that TSTA facility operators perform their assignments in a safe and efficient manner and that the operators maintain high levels of operational proficiency through continuing training, retraining, requalification, and recertification

  1. Simulation study on detection performance of eye-safe coherent Doppler wind lidar operating near 1.6 μm

    Science.gov (United States)

    Ma, Han; Wang, Qing; Na, Quanxin; Gao, Mingwei

    2018-01-01

    Coherent Doppler wind lidars (CDWL) are widely used in aerospace, atmospheric monitoring and other fields. The parameters of laser source such as the wavelength, pulse energy, pulse duration and pulse repetition rate (PRR) have significant influences on the detection performance of wind lidar. We established a simulation model which takes into account the effects of atmospheric transmission, backscatter, atmospheric turbulence and parameters of laser source. The maximum detection range is also calculated under the condition that the velocity estimation accuracy is 0.1 m/s by using this model. We analyzed the differences of the detection performance between two operation systems, which show the high pulse energy-low pulse repetition rate (HPE-LPRR) and low pulse energy-high repetition rate (LPE-HPRR), respectively. We proved our simulation model reliable by using the parameters of two commercial lidar products. This research has important theoretical and practical values for the design of eye-safe coherent Doppler wind lidar.

  2. The time optimal trajectory planning with limitation of operating task for the Tokamak inspecting manipulator

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Hesheng; Lai, Yinping [Department of Automation,Shanghai Jiao Tong University, Shanghai (China); Key Laboratory of System Control and Information Processing, Ministry of Education of China (China); Chen, Weidong, E-mail: wdchen@sjtu.edu.cn [Department of Automation,Shanghai Jiao Tong University, Shanghai (China); Key Laboratory of System Control and Information Processing, Ministry of Education of China (China)

    2016-12-15

    In this paper, a new optimization model of time optimal trajectory planning with limitation of operating task for the Tokamak inspecting manipulator is designed. The task of this manipulator is to inspect the components of Tokamak, the inspecting velocity of manipulator must be limited in the operating space in order to get the clear pictures. With the limitation of joint velocity, acceleration and jerk, this optimization model can not only get the minimum working time along a specific path, but also ensure the imaging quality of camera through the constraint of inspecting velocity. The upper bound of the scanning speed is not a constant but changes according to the observation distance of camera in real time. The relation between scanning velocity and observation distance is estimated by curve-fitting. Experiment has been carried out to verify the feasibility of optimization model, moreover, the Laplace image sharpness evaluation method is adopted to evaluate the quality of images obtained by the proposed method.

  3. The time optimal trajectory planning with limitation of operating task for the Tokamak inspecting manipulator

    International Nuclear Information System (INIS)

    Wang, Hesheng; Lai, Yinping; Chen, Weidong

    2016-01-01

    In this paper, a new optimization model of time optimal trajectory planning with limitation of operating task for the Tokamak inspecting manipulator is designed. The task of this manipulator is to inspect the components of Tokamak, the inspecting velocity of manipulator must be limited in the operating space in order to get the clear pictures. With the limitation of joint velocity, acceleration and jerk, this optimization model can not only get the minimum working time along a specific path, but also ensure the imaging quality of camera through the constraint of inspecting velocity. The upper bound of the scanning speed is not a constant but changes according to the observation distance of camera in real time. The relation between scanning velocity and observation distance is estimated by curve-fitting. Experiment has been carried out to verify the feasibility of optimization model, moreover, the Laplace image sharpness evaluation method is adopted to evaluate the quality of images obtained by the proposed method.

  4. 40 CFR Table 1 to Subpart Ssss of... - Operating Limits if Using Add-on Control Devices and Capture System

    Science.gov (United States)

    2010-07-01

    ... Using Add-on Control Devices and Capture System If you are required to comply with operating limits by... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Operating Limits if Using Add-on Control Devices and Capture System 1 Table 1 to Subpart SSSS of Part 63 Protection of Environment...

  5. 40 CFR Table 1 to Subpart Jjjj of... - Operating Limits if Using Add-On Control Devices and Capture System

    Science.gov (United States)

    2010-07-01

    ... Limits if Using Add-On Control Devices and Capture System If you are required to comply with operating... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Operating Limits if Using Add-On Control Devices and Capture System 1 Table 1 to Subpart JJJJ of Part 63 Protection of Environment...

  6. 40 CFR Table 2 to Subpart Oooo of... - Operating Limits if Using Add-On Control Devices and Capture System

    Science.gov (United States)

    2010-07-01

    ... OOOO of Part 63—Operating Limits if Using Add-On Control Devices and Capture System If you are required... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Operating Limits if Using Add-On Control Devices and Capture System 2 Table 2 to Subpart OOOO of Part 63 Protection of Environment...

  7. Implementation of superconducting fault current limiter for flexible operation in the power substation

    Energy Technology Data Exchange (ETDEWEB)

    Song, Chong Suk, E-mail: chong_suk@korea.ac.kr [School of Electrical Engineering, Korea University, Anam dong, Seonbukgu, Seoul 136-713 (Korea, Republic of); Lee, Hansang [School of Railway and Electrical Engineering, Kyungil University, Hayang-eup, Gyeongsan-si, Gyeongsangbuk-do 712-701 (Korea, Republic of); Cho, Yoon-sung [Department of Electric and Energy Engineering, Catholic University of Daegu, Hayang-eup, Gyeongsan-si, Gyeongsangbuk-do 712-702 (Korea, Republic of); Suh, Jaewan [School of Electrical Engineering, Korea University, Anam dong, Seonbukgu, Seoul 136-713 (Korea, Republic of); Jang, Gilsoo, E-mail: gjang@korea.ac.kr [School of Electrical Engineering, Korea University, Anam dong, Seonbukgu, Seoul 136-713 (Korea, Republic of)

    2014-09-15

    Highlights: • The power load concentrated in load centers results in high levels of fault current. • This paper introduces a fault current reduction scheme using SFCLs in substations. • The SFCL is connected in parallel to the bus tie between the two busbars. • The fault current mitigation using SFCLs is verified through PSS/e simulations. - Abstract: The concentration of large-scale power loads located in the metropolitan areas have resulted in high fault current levels during a fault thereby requiring the substation to operate in the double busbar configuration mode. However, the double busbar configuration mode results in deterioration of power system reliability and unbalanced power flow in the adjacent transmission lines which may result in issues such as overloading of lines. This paper proposes the implementation of the superconducting fault current limiter (SFCL) to be installed between the two substation busbars for a more efficient and flexible operation of the substation enabling both single and double busbar configurations depending on the system conditions for guaranteeing power system reliability as well as fault current limitations. Case studies are being performed for the effectiveness of the SFCL installation and results are compared for the cases where the substation is operating in single and double busbar mode and with and without the installation of the SFCL for fault current mitigation.

  8. 78 FR 57925 - Ferroequus Railway Company Limited and Railstuff, LLC-Lease and Operation Exemption-City of...

    Science.gov (United States)

    2013-09-20

    ... Company Limited and Railstuff, LLC--Lease and Operation Exemption--City of Tacoma, d/b/a Tacoma Rail... City of Tacoma, d/b/a Tacoma Rail Mountain Division (TRMD), and to operate, pursuant to a lease... state that the line connects with a TRMD line over which TMRD provides common carrier service between...

  9. Continuum limit of overlap valence quarks on a twisted mass sea

    Energy Technology Data Exchange (ETDEWEB)

    Cichy, Krzysztof [Adam Mickiewicz Univ., Poznan (Poland). Faculty of Physics; Herdoiza, Gregorio [DESY, Zeuthen (Germany). John von Neumann-Institut fuer Computing NIC; Univ. Autonoma de Madrid (Spain). Dept. de Fisica Teorica; Jansen, Karl [DESY, Zeuthen (Germany). John von Neumann-Institut fuer Computing NIC

    2010-12-15

    We study a lattice QCD mixed action with overlap valence quarks on two flavours of Wilson maximally twisted mass sea quarks. Employing three different matching conditions to relate both actions to each other, we investigate the continuum limit by using three values of the lattice spacing ranging from a{approx}0.05 fm to 0.08 fm. A particular emphasis is put on the effect on physical observables of the topological zero modes appearing in the valence overlap operator. We estimate the region of parameter space where the contribution from these zero modes is sufficiently small such that their effects can be safely controlled and a restoration of unitarity of the mixed action in the continuum limit is reached. (orig.)

  10. Organizational environment and operator culture

    International Nuclear Information System (INIS)

    Morisseau, D.S.; Schoenfeld, I.E.

    1988-01-01

    The Nuclear Regulatory Commission has historically reviewed corporate and plant level management and organization against the criteria of NUREG-0800, The Standard Review Plan. These criteria address the organizational structure, management control, lines of authority and communication, the range and level of experience, and the availability of manpower to effectively and safely operate the facility. Now that most nuclear power plants have received their operating licenses, the emphasis for review has shifted to the day-to-day operation of the facilities. Along with this has come greater recognition that hardware and engineering systems, through vitally important, are not the only components needed for safe operation of power plants. The people who run and operate these plants are a vitally important component and are an integral part of the entire system, i.e., machinery does not operate in isolation

  11. Use of operator-provided, installed C/S equipment in IAEA safeguards

    International Nuclear Information System (INIS)

    Shea, T.; Rundquist, D.; Gaertner, K.; Yellin, E.

    1987-01-01

    Developing solutions for complex safe guards problems in close cooperation with Operators is becoming more common, especially as the IAEA continues to operate under zero-growth limitations. This has in practice taken on various forms; from the extreme case of very specific equipment developed and constructed by the State/Operator for use in only one facility, to the more normal case where only the development is carried out by the State/Operator. This practice has advantages and disadvantages. For example, to ensure that Agency inspections will be carried out in a predictable manner, it will be in the Operator's interest to ensure that any equipment he provides is of the highest quality, meets all national safety requirements, and is installed and maintained in such a manner that it will provide years of service. Agency equipment performs its intended function in a reliable manner, but with very specific, limited applications in mind, improvements in reliability over that obtained with normal Agency equipment are to be expected. Also, the authors experience is that reaching acceptable arrangements for the use of State- of Operator-supplied equipment is often far more straightforward than when arranging to apply Agency equipment

  12. Power operation, measurement and methods of calculation of power distribution

    International Nuclear Information System (INIS)

    Lindahl, S.O.; Bernander, O.; Olsson, S.

    1982-01-01

    During the initial fuel loading of a BWR core, extensive checks and measurements of the fuel are performed. The measurements are designed to verify that the reactor can always be safely operated in compliance with the regulatory constraints. The power distribution within the reactor core is evaluated by means of instrumentation and elaborate computer calculations. The power distribution forms the basis for the evaluation of thermal limits. The behaviour of the reactor during the ordinary modes of operation as well as during transients shall be well understood and such that the integrity of the fuel and the reactor systems is always well preserved. (author)

  13. Light water ultra-safe plant concept: First annual report

    International Nuclear Information System (INIS)

    Klevans, E.

    1987-01-01

    Since the accident at Three Mile Island (TMI) Penn State Nuclear Engineering Department Faculty and Staff have considered various methods to improve already safe reactor designs and public perception of the safety of Nuclear Power. During the last year, the Department of Energy funded the study of a plant reconfiguration originally proposed by M.A. Shultz. This report presents the status of the project at the end of the first year. A broad set of specifications to improve safety and public perception were set forth and the realization of these goals is achieved in a plant design named, ''The Light Water Ultra-Safe Plant Concept.'' The most significant goals of the concept address the station black-out problem and simplification of required operator actions during abnormal situations. These goals are achieved in the Ultra-Safe Concept by addition of an in-containment atmospheric tank containing a large quantity of cool water, replacement of the conventional PWR pressurizer system with a pressurizing pump, internal emergency power generation, and arrangement of components to utilize natural circulation at shut-down. The first year effort included an evaluation of the normal operation characteristics of the primary system pressurizing concept, evaluating parameters and modeling for analysis of the shutdown scenario, design of a low power density core, design of a low-pressure waste handling system, arrangement of a drainage system for pipe break considerations, and failure modes and effects analysis

  14. Safe Human-Robot Cooperation in an Industrial Environment

    Directory of Open Access Journals (Sweden)

    Nicola Pedrocchi

    2013-01-01

    Full Text Available The standard EN ISO10218 is fostering the implementation of hybrid production systems, i.e., production systems characterized by a close relationship among human operators and robots in cooperative tasks. Human-robot hybrid systems could have a big economic benefit in small and medium sized production, even if this new paradigm introduces mandatory, challenging safety aspects. Among various requirements for collaborative workspaces, safety-assurance involves two different application layers; the algorithms enabling safe space-sharing between humans and robots and the enabling technologies allowing acquisition data from sensor fusion and environmental data analysing. This paper addresses both the problems: a collision avoidance strategy allowing on-line re-planning of robot motion and a safe network of unsafe devices as a suggested infrastructure for functional safety achievement.

  15. The concept of the conservative operating policy

    International Nuclear Information System (INIS)

    Idita, S.A.

    1997-01-01

    In the context of the nuclear operating environment, the conservative operating policy is one that promotes a culture of moderation and caution. This policy requires compliance with the intent of the Reactor Operation Licence (ROL) and adherence with the limitations stipulated in the facility Operating Policies and Principles (OPP). While ROL is the document prescribing the laws governing the operation and maintenance the OPP are the statements defining the boundaries within which the facility will be operated. A conservative operating policy, that is well understood by all plant facility personnel provides assurance that plant operation and maintenance will be carried out in compliance with approved operating and maintenance procedures. In an abnormal plant operating situation where OPP's may be challenged, the provision of 'Abnormal Plant Operating Procedures' (APOP's) will stipulate actions designed to return the plant to a condition where normal procedures can be followed i.e. acceptably within OPP limitations. When in a NPP an operating scenario will develop where the the situation is not covered by normal approved operating procedures a conservative operating policy will empower the duty Shift Supervisor (SS) to initiate actions that will move the plant in the 'safe direction'. The paper enumerates the decisions which the SS has to make in order to ensure that the reactor power is correctly controlled, the reactor fuel remains cooled and the radioactivity remains contained. It is stressed that a corporate operating policy will be of little use if its existence is known only by corporate management. To be effective, and to be instrumental in the promotion of a facility safety culture, the conservative operating philosophy must be known about and fully understood by all personnel working at a nuclear facility. It is up to management to 'get the word out' and lead by example. (author)

  16. Two simple techniques for the safe Sarcoptes collection and individual mite DNA extraction.

    Science.gov (United States)

    Soglia, Dominga; Rambozzi, Luisa; Maione, Sandra; Spalenza, Veronica; Sartore, Stefano; Alasaad, Samer; Sacchi, Paola; Rossi, Luca

    2009-10-01

    Availability of mites is a recognized limiting factor of biological and genetic investigations of the genus Sarcoptes. Current methods of deoxyribonucleic acid (DNA) extraction from individual mites also need substantial improvement in efficiency and operator friendliness. We have first developed a technique for efficient and safe extraction of living mites from scabietic skin samples (crusts or deep skin scrapings). Its core device is a large plastic syringe connected with a 1.5-ml Eppendorf tube. The source material is introduced in the syringe and the device in a shoe box with the tip half of the tube emerging. Mites migrate towards a heat source during a minimum of 36 h. Then, the tube is detached and the mites utilized without risks for the operators. A second technique allows operator-friendly manipulation of individual mites for DNA extraction. Fixed mites are isolated by adhesion to a small strip of polyvinyl chloride (PVC) adhesive tape operated with tweezers. Then, mite and strip are plunged in the lyses buffer and the sample twice submitted to thermal shock for disruption of the chitinous exoskeleton. Data show that the tape does not interfere with successive DNA extraction with a commercial kit. The corresponding protocol, that we briefly name "PVC adhesive tape + thermal shock + kit DNA extraction," compares favorably with the available ones.

  17. Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-10-15

    conventions. The standards are also applied by regulatory bodies and operators around the world to enhance safety in nuclear power generation and in nuclear applications in medicine, industry, agriculture and research. Safety is not an end in itself but a prerequisite for the purpose of the protection of people in all States and of the environment - now and in the future. The risks associated with ionizing radiation must be assessed and controlled without unduly limiting the contribution of nuclear energy to equitable and sustainable development. Governments, regulatory bodies and operators everywhere must ensure that nuclear material and radiation sources are used beneficially, safely and ethically. The IAEA safety standards are designed to facilitate this, and I encourage all Member States to make use of them.

  18. Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements

    International Nuclear Information System (INIS)

    2012-01-01

    conventions. The standards are also applied by regulatory bodies and operators around the world to enhance safety in nuclear power generation and in nuclear applications in medicine, industry, agriculture and research. Safety is not an end in itself but a prerequisite for the purpose of the protection of people in all States and of the environment - now and in the future. The risks associated with ionizing radiation must be assessed and controlled without unduly limiting the contribution of nuclear energy to equitable and sustainable development. Governments, regulatory bodies and operators everywhere must ensure that nuclear material and radiation sources are used beneficially, safely and ethically. The IAEA safety standards are designed to facilitate this, and I encourage all Member States to make use of them.

  19. Materials for passively safe reactors

    International Nuclear Information System (INIS)

    Simnad, T.

    1993-01-01

    Future nuclear power capacity will be based on reactor designs that include passive safety features if recent progress in advanced nuclear power developments is realized. There is a high potential for nuclear systems that are smaller and easier to operate than the current generation of reactors, especially when passive or intrinsic characteristics are applied to provide inherent stability of the chain reaction and to minimize the burden on equipment and operating personnel. Taylor, has listed the following common generic technical features as the most important goals for the principal reactor development systems: passive stability, simplification, ruggedness, case of operation, and modularity. Economic competitiveness also depends on standardization and assurance of licensing. The performance of passively safe reactors will be greatly influenced by the successful development of advanced fuels and materials that will provide lower fuel-cycle costs. A dozen new designs of advanced power reactors have been described recently, covering a wide spectrum of reactor types, including pressurized water reactors, boiling water reactors, heavy-water reactors, modular high-temperature gas-cooled reactors (MHTGRs), and fast breeder reactors. These new designs address the need for passive safety features as well as the requirement of economic competitiveness

  20. Topology of sustainable management of dynamical systems with desirable states: from defining planetary boundaries to safe operating spaces in the Earth System

    Science.gov (United States)

    Heitzig, Jobst; Kittel, Tim; Donges, Jonathan; Molkenthin, Nora

    2016-04-01

    To keep the Earth System in a desirable region of its state space, such as defined by the recently suggested "tolerable environment and development window", "guardrails", "planetary boundaries", or "safe (and just) operating space for humanity", one not only needs to understand the quantitative internal dynamics of the system and the available options for influencing it (management), but also the structure of the system's state space with regard to certain qualitative differences. Important questions are: Which state space regions can be reached from which others with or without leaving the desirable region? Which regions are in a variety of senses "safe" to stay in when management options might break away, and which qualitative decision problems may occur as a consequence of this topological structure? In this work, we develop a mathematical theory of the qualitative topology of the state space of a dynamical system with management options and desirable states, as a complement to the existing literature on optimal control which is more focussed on quantitative optimization and is much applied in both the engineering and the integrated assessment literature. We suggest a certain terminology for the various resulting regions of the state space and perform a detailed formal classification of the possible states with respect to the possibility of avoiding or leaving the undesired region. Our results indicate that before performing some form of quantitative optimization such as of indicators of human well-being for achieving certain sustainable development goals, a sustainable and resilient management of the Earth System may require decisions of a more discrete type that come in the form of several dilemmas, e.g., choosing between eventual safety and uninterrupted desirability, or between uninterrupted safety and larger flexibility. We illustrate the concepts and dilemmas drawing on conceptual models from climate science, ecology, coevolutionary Earth System modeling

  1. Operating experience and procedures at the tritium systems test assembly

    International Nuclear Information System (INIS)

    Carlson, R.V.; Binning, K.E.; Cole, S.P.; Jenkins, E.M.; Wilhelm, R.C.; Cole, S.P.

    1988-01-01

    Operating procedures are important for the safe and efficient operation of the Tritium Systems Test Assembly (TSTA). TSTA has been operating for four years with tritium in a safe and efficient manner. The inventory of tritium in the process loop is 100 grams and several milestone runs have been completed. This paper describes the methods used to operate TSTA. 3 refs., 1 fig

  2. Space Toxicology: Human Health during Space Operations

    Science.gov (United States)

    Khan-Mayberry, Noreen; James, John T.; Tyl, ROchelle; Lam, Chiu-Wing

    2010-01-01

    Space Toxicology is a unique and targeted discipline for spaceflight, space habitation and occupation of celestial bodies including planets, moons and asteroids. Astronaut explorers face distinctive health challenges and limited resources for rescue and medical care during space operation. A central goal of space toxicology is to protect the health of the astronaut by assessing potential chemical exposures during spaceflight and setting safe limits that will protect the astronaut against chemical exposures, in a physiologically altered state. In order to maintain sustained occupation in space on the International Space Station (ISS), toxicological risks must be assessed and managed within the context of isolation continuous exposures, reuse of air and water, limited rescue options, and the need to use highly toxic compounds for propulsion. As we begin to explore other celestial bodies in situ toxicological risks, such as inhalation of reactive mineral dusts, must also be managed.

  3. Target Trailing With Safe Navigation With Colregs for Maritime Autonomous Surface Vehicles

    Science.gov (United States)

    Kuwata, Yoshiaki (Inventor); Wolf, Michael T. (Inventor); Zarzhitsky, Dimitri V. (Inventor); Aghazarian, Hrand (Inventor); Huntsberger, Terrance L. (Inventor); Howard, Andrew B. (Inventor)

    2014-01-01

    Systems and methods for operating autonomous waterborne vessels in a safe manner. The systems include hardware for identifying the locations and motions of other vessels, as well as the locations of stationary objects that represent navigation hazards. By applying a computational method that uses a maritime navigation algorithm for avoiding hazards and obeying COLREGS using Velocity Obstacles to the data obtained, the autonomous vessel computes a safe and effective path to be followed in order to accomplish a desired navigational end result, while operating in a manner so as to avoid hazards and to maintain compliance with standard navigational procedures defined by international agreement. The systems and methods have been successfully demonstrated on water with radar and stereo cameras as the perception sensors, and integrated with a higher level planner for trailing a maneuvering target.

  4. Designing visual displays and system models for safe reactor operations

    International Nuclear Information System (INIS)

    Brown-VanHoozer, S.A.

    1995-01-01

    The material presented in this paper is based on two studies involving the design of visual displays and the user's prospective model of a system. The studies involve a methodology known as Neuro-Linguistic Programming and its use in expanding design choices from the operator's perspective image. The contents of this paper focuses on the studies and how they are applicable to the safety of operating reactors

  5. Prediction of knock limited operating conditions of a natural gas engine

    International Nuclear Information System (INIS)

    Soylu, Seref

    2005-01-01

    Computer models of engine processes are valuable tools for predicting and analyzing engine performance and allow exploration of many engine design alternatives in an inexpensive fashion. In the present work, a zero-dimensional, two zone thermodynamic model was used to determine the knock limited operating conditions of a natural gas engine. Experimentally based burning rate models were used for flame initiation and propagation calculations. A knock model was incorporated with the zero-dimensional model. Comparison of the measured and calculated cylinder pressure data indicated that the model is able to match the measured cylinder pressure data with less than 8% error in magnitudes if the computations are started at the experimental spark timing. The knock predictions agreed with the measurements also. With the established knock model, it is possible not only to investigate whether knock is observed with changing operating and design parameters, but also to evaluate their effects on the maximum possible knock intensity

  6. Safe limit of arsenic in soil in relation to dietary exposure of arsenicosis patients from Malda district, West Bengal- A case study.

    Science.gov (United States)

    Golui, Debasis; Guha Mazumder, D N; Sanyal, S K; Datta, S P; Ray, P; Patra, P K; Sarkar, S; Bhattacharya, K

    2017-10-01

    Safe limit of arsenic in soil in relation to dietary exposure of arsenicosis patients was established in Malda district of West Bengal. Out of 182 participants examined, 80 (43.9%) participants showed clinical features of arsenicosis, characterized by arsenical skin lesion (pigmentation and keratosis), while 102 participants did not have any such lesion (control). Experimental results of the twenty eight soils (own field) of the participants showed the mean Olsen extractable and total arsenic concentration of 0.206 and 6.70mgkg -1 , respectively. Arsenic concentration in rice grain ranged from 2.00 to 1260μgkg -1 with the mean value of 146μgkg -1 . The hazard quotient (HQ) for intake of As by human through consumption of rice varied from 0.03 to 3.52. HQ exceeds 1.0 for drinking water and rice grain grown in the study area in many cases. As high as 77.6% variation in As content in rice grain could be explained by the solubility-free ion activity model. Toxic limit of extractable As in soil for rice in relation to soil properties and human health hazard, associated with consumption of rice grain by human, was established. For example, the permissible limit of Olsen extractable As in soil would be 0.43mgkg -1 for rice cultivation, if soil pH and organic carbon content were 7.5% and 0.50%, respectively. However, the critical limit of Olsen extractable As in soil would be 0.54mgkg -1 , if soil pH and organic carbon were 8.5% and 0.75%, respectively. The conceptual framework of fixing the toxic limit of arsenic in soils with respect to soil properties and human health under modeling-framework was established. Copyright © 2017 Elsevier Inc. All rights reserved.

  7. The Conceptual Design of Innovative Safe PWR

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Han-Gon [Centural Research Institute, Daejeon (Korea, Republic of); Heo, Sun [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

    2016-10-15

    Most of countries operating NPPs have been performed post-Fukushima improvements as short-term countermeasure to enhance the safety of operating NPPs. Separately, vendors have made efforts on developing passive safety systems as long-term and ultimate countermeasures. AP1000 designed by Westinghouse Electric Company has passive safety systems including the passive emergency core cooling system (PECCS), the passive residual heat removal system (PRHRS), and the passive containment cooling system (PCCS). ESBWR designed by GE-Hitachi also has passive safety systems consisting of the isolation condenser system, the gravity driven cooling system and the PCCS. Other countries including China and Russia have made efforts on developing passive safety systems for enhancing the safety of their plants. In this paper, we summarize the design goals and main design feature of innovative safe PWR, iPOWER which is standing for Innovative Passive Optimized World-wide Economical Reactor, and show the developing status and results of research projects. To mitigate an accident without electric power and enhance the safety level of PWR, the conceptual designs of passive safety system and innovative safe PWR have been performed. It includes the PECCS for core cooling and the PCCS for containment cooling. Now we are performing the small scale and separate effect tests for the PECCS and the PCCS and preparing the integral effect test for the PECCS and real scale test for the PCCS.

  8. A Green, Safe, Multi-Pulse Solid Motor (MPM) for CubeSats, Phase II

    Data.gov (United States)

    National Aeronautics and Space Administration — Today's CubeSats lack storable, green, safe propulsion options for complex science missions that may involve large Delta-V changes, proximity operations, and...

  9. Organising a safe space for navigating social-ecological transformations to sustainability

    NARCIS (Netherlands)

    L. Pereira (Laura); T. Karpouzoglou (Timothy); S. Doshi (Samir); N. Frantzeskaki (Niki)

    2015-01-01

    textabstractThe need for developing socially just living conditions for the world’s growing population whilst keeping human societies within a ‘safe operating space’ has become a modern imperative. This requires transformative changes in the dominant social norms, behaviours, governance and

  10. Organising a safe space for navigating social-ecological transformations to sustainability

    NARCIS (Netherlands)

    Pereira, L.; Karpouzoglou, T.D.; Doshi, S.; Frantzeskaki, N.

    2015-01-01

    The need for developing socially just living conditions for the world’s growing population whilst keeping human societies within a ‘safe operating space’ has become a modern imperative. This requires transformative changes in the dominant social norms, behaviours, governance and management regimes

  11. 40 CFR 63.4567 - How do I establish the emission capture system and add-on control device operating limits during...

    Science.gov (United States)

    2010-07-01

    ... system and add-on control device operating limits during the performance test? 63.4567 Section 63.4567... Emission Rate with Add-on Controls Option § 63.4567 How do I establish the emission capture system and add-on control device operating limits during the performance test? During the performance test required...

  12. The recommended Threshold Limit Values for heat exposure fail to maintain body core temperature within safe limits in older working adults.

    Science.gov (United States)

    Lamarche, Dallon T; Meade, Robert D; D'Souza, Andrew W; Flouris, Andreas D; Hardcastle, Stephen G; Sigal, Ronald J; Boulay, Pierre; Kenny, Glen P

    2017-09-01

    temperature from exceeding 38°C in older workers. Furthermore, a stable core temperature was not achieved within safe limits (i.e., ≤38°C) indicating that the TLV® guidelines may not adequately protect all individuals during work in hot conditions.

  13. Real-time protection of the Ohmic heating coil force limits in DIII-D

    International Nuclear Information System (INIS)

    Broesch, J.D.; Scoville, J.T.; Hyatt, A.W.; Coon, R.M.

    1997-11-01

    The maximum safe operating limits of the DIII-D tokamak are determined by the force produced in the ohmic heating coil and the toroidal field coil during a plasma pulse. This force is directly proportional to the product of the current in the coils. Historically, the current limits for each coil were set statically before each pulse without regard for the time varying nature of the currents. In order to allow the full time-dependent capability of the ohmic coil to be used, a system was developed for monitoring the product of the currents dynamically and making appropriate adjustments in real time. This paper discusses the purpose, implementation, and results of this work

  14. Parallel operation of primary sodium pumps in FBTR

    International Nuclear Information System (INIS)

    Athmalingam, S.; Ellappan, T.R.; Vaidyanathan, G.; Chetal, S.C.; Bhoje, S.B.

    1994-01-01

    Sodium pumps used in the primary main circuit of Fast Breeder Test Reactor (FBTR) are centrifugal pumps. These pumps have a free level of sodium with a cover gas above it to simplify the pump seal arrangement. The sodium level in the pumps will vary based on the flow. The minimum level is governed by consideration of gas entrainment and net positive suction head (NPSH) to the pump while the maximum level is limited by sodium entering the pump tank gas line. There is a special feature in these pumps in that a small portion of the pump outlet sodium flow is led back into the suction chamber to maintain level and avoid gas entrainment. A control valve in this line helps in controlling the level at the desired value. With parallel operation of two sodium pumps a study was conducted to find the regions of safe operation of the two pumps. The purpose of this paper is to give the various design features and methodology of the analysis to arrive at the limiting condition of operation for the different operating states of the two pumps and the effect of pump speed variations on the fluctuations in sodium flows. (author). 6 figs

  15. SAFE Newsletter

    OpenAIRE

    2013-01-01

    The Center of Excellence SAFE – “Sustainable Architecture for Finance in Europe” – is a cooperation of the Center for Financial Studies and Goethe University Frankfurt. It is funded by the LOEWE initiative of the State of Hessen (Landes-Offensive zur Entwicklung wissenschaftlich-ökonomischer Exzellenz). SAFE brings together more than 40 professors and just as many junior researchers who are all dedicated to conducting research in support of a sustainable financial architecture. The Center has...

  16. Hybrid neural network for density limit disruption prediction and avoidance on J-TEXT tokamak

    Science.gov (United States)

    Zheng, W.; Hu, F. R.; Zhang, M.; Chen, Z. Y.; Zhao, X. Q.; Wang, X. L.; Shi, P.; Zhang, X. L.; Zhang, X. Q.; Zhou, Y. N.; Wei, Y. N.; Pan, Y.; J-TEXT team

    2018-05-01

    Increasing the plasma density is one of the key methods in achieving an efficient fusion reaction. High-density operation is one of the hot topics in tokamak plasmas. Density limit disruptions remain an important issue for safe operation. An effective density limit disruption prediction and avoidance system is the key to avoid density limit disruptions for long pulse steady state operations. An artificial neural network has been developed for the prediction of density limit disruptions on the J-TEXT tokamak. The neural network has been improved from a simple multi-layer design to a hybrid two-stage structure. The first stage is a custom network which uses time series diagnostics as inputs to predict plasma density, and the second stage is a three-layer feedforward neural network to predict the probability of density limit disruptions. It is found that hybrid neural network structure, combined with radiation profile information as an input can significantly improve the prediction performance, especially the average warning time ({{T}warn} ). In particular, the {{T}warn} is eight times better than that in previous work (Wang et al 2016 Plasma Phys. Control. Fusion 58 055014) (from 5 ms to 40 ms). The success rate for density limit disruptive shots is above 90%, while, the false alarm rate for other shots is below 10%. Based on the density limit disruption prediction system and the real-time density feedback control system, the on-line density limit disruption avoidance system has been implemented on the J-TEXT tokamak.

  17. SYBR safeTM efficiently replaces ethidium bromide in Aspergillus fumigatus gene disruption.

    Science.gov (United States)

    Canela, H M S; Takami, L A; Ferreira, M E S

    2017-02-08

    Invasive aspergillosis is a disease responsible for high mortality rates, caused mainly by Aspergillus fumigatus. The available drugs are limited and this disease continues to occur at an unacceptable frequency. Gene disruption is essential in the search for new drug targets. An efficient protocol for A. fumigatus gene disruption was described but it requires ethidium bromide, a genotoxic agent, for DNA staining. Therefore, the present study tested SYBR safe TM , a non-genotoxic DNA stain, in A. fumigatus gene disruption protocol. The chosen gene was cipC, which has already been disrupted successfully in our laboratory. A deletion cassette was constructed in Saccharomyces cerevisiae and used in A. fumigatus transformation. There was no statistical difference between the tested DNA stains. The success rate of S. cerevisiae transformation was 63.3% for ethidium bromide and 70% for SYBR safe TM . For A. fumigatus gene disruption, the success rate for ethidium bromide was 100 and 97% for SYBR safe TM . In conclusion, SYBR safe TM efficiently replaced ethidium bromide, making this dye a safe and efficient alternative for DNA staining in A. fumigatus gene disruption.

  18. 40 CFR 63.4767 - How do I establish the emission capture system and add-on control device operating limits during...

    Science.gov (United States)

    2010-07-01

    ... system and add-on control device operating limits during the performance test? 63.4767 Section 63.4767... Rate with Add-on Controls Option § 63.4767 How do I establish the emission capture system and add-on control device operating limits during the performance test? During the performance test required by § 63...

  19. 40 CFR 63.4167 - How do I establish the emission capture system and add-on control device operating limits during...

    Science.gov (United States)

    2010-07-01

    ... system and add-on control device operating limits during the performance test? 63.4167 Section 63.4167... with Add-on Controls Option § 63.4167 How do I establish the emission capture system and add-on control device operating limits during the performance test? During the performance test required by § 63.4160...

  20. 40 CFR 63.4966 - How do I establish the emission capture system and add-on control device operating limits during...

    Science.gov (United States)

    2010-07-01

    ... system and add-on control device operating limits during the performance test? 63.4966 Section 63.4966... outlet gas temperature is the maximum operating limit for your condenser. (e) Emission capture system... with Add-on Controls Option § 63.4966 How do I establish the emission capture system and add-on control...

  1. Do Leadership Style, Unit Climate, and Safety Climate Contribute to Safe Medication Practices?

    Science.gov (United States)

    Farag, Amany; Tullai-McGuinness, Susan; Anthony, Mary K; Burant, Christopher

    2017-01-01

    This study aims at: examining if leadership style and unit climate predict safety climate; and testing the direct, indirect, and total effect of leadership style, unit climate, and safety climate on nurses' safe medication practices. The Institute of Medicine and nursing scholars propose that safety climate is a prerequisite to safety practices. However, there is limited empirical evidence about factors contributing to the development of safety climate and about the association with nurses' safe medication practices. This cross-sectional study used survey data from 246 RNs working in a Magnet® hospital. Leadership style and unit climate predicted 20% to 50% of variance on all safety climate dimensions. Model testing revealed the indirect impact of leadership style and unit climate on nurses' safe medication practices. Our hypothesized model explained small amount of the variance on nurses' safe medication practices. This finding suggests that nurses' safe medication practices are influenced by multiple contextual and personal factors that should be further examined.

  2. Intelligent Multisensor Prodder for Training Operators in Humanitarian Demining

    Directory of Open Access Journals (Sweden)

    Roemi Fernández

    2016-06-01

    Full Text Available Manual prodding is still one of the most utilized procedures for identifying buried landmines during humanitarian demining activities. However, due to the high number of accidents reported during its practice, it is considered an outmoded and risky procedure and there is a general consensus about the need of introducing upgrades for enhancing the safety of human operators. With the aim of contributing to reduce the number of demining accidents, this paper presents an intelligent multisensory system for training operators in the use of prodders. The proposed tool is able to provide to deminers useful information in two critical issues: (a the amount of force exerted on the target and if it is greater than the safe limit and, (b to alert them when the angle of insertion of the prodder is approaching or exceeding a certain dangerous limit. Results of preliminary tests show the feasibility and reliability of the proposed design and highlight the potential benefits of the tool.

  3. Analysis for the Effects of Grid Voltage Degradation on APR1400 Operation, Case Study for Egypt

    International Nuclear Information System (INIS)

    Hassan, Mostafa Ahmed Fouad; Koo, Chang Choong

    2015-01-01

    Egypt is one of the countries planning to introduce a NPP into its electrical power system. Although the Egyptian power system has sufficient capacity to integrate any commercially available nuclear unit as the total installed capacity of the power system is more than 32GWe, which is more than 10 times capacity of any nuclear unit in the range of 1000 to 1700MWe, the system is vulnerable to extreme voltage variations, especially voltage degradation during peak load conditions. These conditions can lead to voltage collapse if a counter measure, usually load shedding, is not taken in a proper time. Hence, it is necessary to analyze the effect of such conditions on the safe and economic operation of the NPP. In this paper we analyzed the effects of grid voltage degradation on the safe and economic operation of the Advanced Power Reactor (APR1400) to determine any adverse effects on the plant auxiliary loads while operating in the Egyptian power system. In this paper the effects of grid voltage degradation on the safe and economic operation of APR1400 were investigated taking into account, generator operating limits, plant safety requirements, operation modes and loading categories in order to determine any adverse effect on the plant auxiliary loads while operating in the Egyptian power system. The results of the load flow and motor starting analysis demonstrated that during normal operation the automatic voltage regulator and transformers OLTCs can mitigate the effect of grid voltage degradation without any detrimental effect on the plant auxiliary loads. During the highly unlikely LOCA condition if the grid voltage degraded below 95%, the degraded voltage relays at Class 1E 4.16 kV buses will trip the supply and load breakers and reconnect the required safety loads to the EDG after 4 minutes time delay. During this period the safety loads required for LOCA can be started and accelerated to their rated speed safely even in the worst case of expected degraded voltage

  4. Combustion Efficiency, Flameout Operability Limits and General Design Optimization for Integrated Ramjet-Scramjet Hypersonic Vehicles

    Science.gov (United States)

    Mbagwu, Chukwuka Chijindu

    High speed, air-breathing hypersonic vehicles encounter a varied range of engine and operating conditions traveling along cruise/ascent missions at high altitudes and dynamic pressures. Variations of ambient pressure, temperature, Mach number, and dynamic pressure can affect the combustion conditions in conflicting ways. Computations were performed to understand propulsion tradeoffs that occur when a hypersonic vehicle travels along an ascent trajectory. Proper Orthogonal Decomposition methods were applied for the reduction of flamelet chemistry data in an improved combustor model. Two operability limits are set by requirements that combustion efficiency exceed selected minima and flameout be avoided. A method for flameout prediction based on empirical Damkohler number measurements is presented. Operability limits are plotted that define allowable flight corridors on an altitude versus flight Mach number performance map; fixed-acceleration ascent trajectories were considered for this study. Several design rules are also presented for a hypersonic waverider with a dual-mode scramjet engine. Focus is placed on ''vehicle integration" design, differing from previous ''propulsion-oriented" design optimization. The well-designed waverider falls between that of an aircraft (high lift-to-drag ratio) and a rocket (high thrust-to-drag ratio). 84 variations of an X-43-like vehicle were run using the MASIV scramjet reduced order model to examine performance tradeoffs. Informed by the vehicle design study, variable-acceleration trajectory optimization was performed for three constant dynamic pressures ascents. Computed flameout operability limits were implemented as additional constraints to the optimization problem. The Michigan-AFRL Scramjet In-Vehicle (MASIV) waverider model includes finite-rate chemistry, applied scaling laws for 3-D turbulent mixing, ram-scram transition and an empirical value of the flameout Damkohler number. A reduced-order modeling approach is justified

  5. 75 FR 48329 - Tribal Drinking Water Operator Certification Program

    Science.gov (United States)

    2010-08-10

    ... operator has the skills, knowledge, education and experience necessary to deliver safe water supporting... demonstrates the operator has the skills, knowledge, education and experience necessary to deliver safe water... this program can be found at http://www.epa.gov/safewater/tribal.html . 2. Hard Copies. Hard copies of...

  6. WNA position statement on safe management of nuclear waste and used nuclear fuel

    International Nuclear Information System (INIS)

    Saint-Pierre, S.

    2006-01-01

    This World nuclear association (W.N.A.) Position Statement summarizes the worldwide nuclear industry's record, progress and plans in safely managing nuclear waste and used nuclear fuel. The global industry's safe waste management practices cover the entire nuclear fuel-cycle, from the mining of uranium to the long-term disposal of end products from nuclear power reactors. The Statement's aim is to provide, in clear and accurate terms, the nuclear industry's 'story' on a crucially important subject often clouded by misinformation. Inevitably, each country and each company employs a management strategy appropriate to a specific national and technical context. This Position Statement reflects a confident industry consensus that a common dedication to sound practices throughout the nuclear industry worldwide is continuing to enhance an already robust global record of safe management of nuclear waste and used nuclear fuel. This text focuses solely on modern civil programmes of nuclear-electricity generation. It does not deal with the substantial quantities of waste from military or early civil nuclear programmes. These wastes fall into the category of 'legacy activities' and are generally accepted as a responsibility of national governments. The clean-up of wastes resulting from 'legacy activities' should not be confused with the limited volume of end products that are routinely produced and safely managed by today's nuclear energy industry. On the significant subject of 'Decommissioning of Nuclear Facilities', which is integral to modern civil nuclear power programmes, the W.N.A. will offer a separate Position Statement covering the industry's safe management of nuclear waste in this context. The safe management of nuclear waste and used nuclear fuel is a widespread, well-demonstrated reality. This strong safety record reflects a high degree of nuclear industry expertise and of industry responsibility toward the well-being of current and future generations

  7. Differential operators associated with Gegenbauer polynomials - 2: The limit-point case

    International Nuclear Information System (INIS)

    Onyango Otieno, V.P.

    1987-10-01

    In this paper we study the limit-point case of the Gegenbauer differential equation -((1-x 2 ) υ+1/2 y'(x)) 1 +υ 2 (1-x 2 ) υ-1/2 y(x)=λ(1-x 2 ) υ-1/2 y(x), (x ε (-1,1), λ ε C) in both the so-called right-definite and left-definite cases based partially on a classical approach due to E.C. Titchmarsh. We then link the Titchmarsh approach with operator theoretic results in the spaces L 2 w (-1,1) and H 2 p,q (-1,1). (author). 19 refs

  8. Safe Handling of Radioisotopes

    International Nuclear Information System (INIS)

    1958-01-01

    Under its Statute the International Atomic Energy Agency is empowered to provide for the application of standards of safety for protection against radiation to its own operations and to operations making use of assistance provided by it or with which it is otherwise directly associated. To this end authorities receiving such assistance are required to observe relevant health and safety measures prescribed by the Agency. As a first step, it has been considered an urgent task to provide users of radioisotopes with a manual of practice for the safe handling of these substances. Such a manual is presented here and represents the first of a series of manuals and codes to be issued by the Agency. It has been prepared after careful consideration of existing national and international codes of radiation safety, by a group of international experts and in consultation with other international bodies. At the same time it is recommended that the manual be taken into account as a basic reference document by Member States of the Agency in the preparation of national health and safety documents covering the use of radioisotopes.

  9. On Formal and Informal Factors: Enabling Learning for Safe Offshore Drilling Operations

    Directory of Open Access Journals (Sweden)

    Trygve J. Steiro

    2017-12-01

    Full Text Available Traditional safety thinking has been concerned with investigating accident causations in order to learn from these. However, successful operations constitute the great majority of all the operations. It would thus be interesting to add a focus towards learning from operations that go well. The purpose of the current study is to identify factors that might contribute to successful operations in terms of safety. This purpose is approached by an empirical study consisting of 10 interviews with people who work on board a drilling rig currently operating in Norway. The informants who participated in the interviews hold different positions and come from different companies represented on board the rig. The findings in this study show that it can be difficult to characterize or define successful operations. The definition will be subjective; however, there are some common features of successful operations. Maintaining the life and health of people are the number one priority. A successful operation should also result in the intended product even though it might take some more time than planned. A successful operation is created by many factors and conditions. This study identified 27 factors that might contribute to successful operations in terms of safety. A lot of the theory explaining successful operations focuses on informal factors related to humans and their actions. However, the findings in this study implies that there must be both formal and informal factors present.

  10. Laparoscopic distal pancreatectomy for adenocarcinoma: safe and reasonable?

    Science.gov (United States)

    Postlewait, Lauren M.

    2015-01-01

    As a result of technological advances during the past two decades, surgeons now use minimally invasive surgery (MIS) approaches to pancreatic resection more frequently, yet the role of these approaches for pancreatic ductal adenocarcinoma resections remains uncertain, given the aggressive nature of this malignancy. Although there are no controlled trials comparing MIS technique to open surgical technique, laparoscopic distal pancreatectomy for pancreatic adenocarcinoma is performed with increasing frequency. Data from retrospective studies suggest that perioperative complication profiles between open and laparoscopic distal pancreatectomy are similar, with perhaps lower blood loss and fewer wound infections in the MIS group. Concerning oncologic outcomes, there appear to be no differences in the rate of achieving negative margins or in the number of lymph nodes (LNs) resected when compared to open surgery. There are limited recurrence and survival data on laparoscopic compared to open distal pancreatectomy for pancreatic adenocarcinoma, but in the few studies that assess long term outcomes, recurrence rates and survival outcomes appear similar. Recent studies show that though laparoscopic distal pancreatectomy entails a greater operative cost, the associated shorter length of hospital stay leads to decreased overall cost compared to open procedures. Multiple new technologies are emerging to improve resection of pancreatic cancer. Robotic pancreatectomy is feasible, but there are limited data on robotic resection of pancreatic adenocarcinoma, and outcomes appear similar to laparoscopic approaches. Additionally fluorescence-guided surgery represents a new technology on the horizon that could improve oncologic outcomes after resection of pancreatic adenocarcinoma, though published data thus far are limited to animal models. Overall, MIS distal pancreatectomy appears to be a safe and reasonable approach to treating selected patients with pancreatic ductal

  11. Preliminary Study of Ideal Operational MHD Beta Limit in HL-2A Tokamak Plasmas

    International Nuclear Information System (INIS)

    Shen Yong; Dong Jiaqi; He Hongda; Turnbull, A. D.

    2009-01-01

    Magnetohydrodynamic (MHD) n = 1 kink mode with n the toroidal mode number is studied and the operational beta limit, constrained by the mode, is calculated for the equilibrium of HL-2A by using the GATO code. Approximately the same beta limit is obtained for configurations with a value of the axial safety factor q 0 both larger and less than 1. Without the stabilization of the conducting wall, the beta limit is found to be 0.821% corresponding to a normalized beta value of β c N = 2.56 for a typical HL-2A discharge with a plasma current I p = 0.245 MA, and the scaling of β c N ∼constant is confirmed. (magnetically confined plasma)

  12. Limited field investigation report for the 100-HR-3 operable unit

    International Nuclear Information System (INIS)

    1994-09-01

    This limited field investigation (LFI) was conducted to assess the applicability of interim remedial measures (IRM) for reducing human health and environmental risks within the 100-HR-3 Groundwater Operable Unit. The 100-HR-3 Operable Unit is comprised of three subareas; the 100 D Area, the 100 H Area and those portions of the 600 Area between the two reactor areas. The operable unit is one of seven operable units associated with the 100 D and H Areas. Operable units 100-DR-1, 100-DR-2, 100-DR-3, 100-HR-1, 100-HR-2 and 100-IU-4 address contaminant sources while 100-HR-3 addresses contamination present in the underlying groundwater. The primary method of field investigation used during this LFI was the installation and sampling of monitoring wells. Samples were collected from the groundwater and soils, and submitted for laboratory analysis. Boreholes were surveyed for radiological contamination using downhole geophysical techniques to further delineate the locations and levels of contaminants. All samples were screened to ascertain the presence of volatile organic compounds and radionuclides. Analytical data were subjected to validation; all round one, two and three and a minimum of 10% of round four data associated with the LFI were validated. A screening method was used to identify contaminants of potential concern (COPC). This screening method eliminated from further consideration, constituents that were below background. Constituents which are considered non-toxic to humans were eliminated from the human health evaluation. Data consistency and blank contamination were also evaluated in the screening process. These COPC were then evaluated further in the qualitative risk assessment (QRA). A human health QRA was performed using conservative (maximum equilibrated contaminant levels from the LFI) analyses

  13. Behavior of an operating floor subjected to heavy load drops

    International Nuclear Information System (INIS)

    Levin, H.A.; Chugh, S.C.; Goodyear, W.D.; Hall, W.J.; Tracy, T.J.

    1984-01-01

    A structural evaluation of the behavior of a Boiling Water Reactor operating floor subjected to postulated heavy load impact is presented relative to the evaluation of nuclear industry requirements for addressing the safe handling of heavy loads. A methodology for evaluation of important modes of structural response is presented along with a specification of performance limits that are consistent with desired functional requirements of the operating floor system. Options for improving undesirable behavior are discussed based upon an understanding of the physical phenomena involved, ultimately factoring this into a modification program. Reference is made to recent test experience that is applicable to the improvement of structural performance in modes of high shear ductility. Other relevant information is referenced that is applicable to the overall structural evaluation of nuclear power plant heavy load handling operations

  14. Design review report: AN valve pit upgrades for Project W-314, tank farm restoration and safe operations

    International Nuclear Information System (INIS)

    Boes, K.A.

    1998-01-01

    This Design Review Report (DRR) documents the contractor design verification methodology and records associated with project W-314's AN Valve Pit Upgrades design package. The DRR includes the documented comments and their respective dispositions for this design. Acceptance of the comment dispositions and closure of the review comments is indicated by the signatures of the participating reviewers. Project W-314, Tank Farm Restoration and Safe Operations, is a project within the Tank Waste Remediation System (TWRS) Tank Waste Retrieval Program. This project provides capital upgrades for the existing Hanford tank farms' waste transfer, instrumentation, ventilation, and electrical infrastructure systems. To support established TWRS programmatic objectives, the project is organized into two distinct phases. The initial focus of the project (i.e., Phase 1) is on waste transfer system upgrades needed to support the TWRS Privatization waste feed delivery system. Phase 2 of the project will provide upgrades to support resolution of regulatory compliance issues, improve tank infrastructure reliability, and reduce overall plant operating/maintenance costs. Within Phase 1 of the W-314 project, the waste transfer system upgrades are further broken down into six major packages which align with the project's work breakdown structure. Each of these six sub-elements includes the design, procurement, and construction activities necessary to accomplish the specific tank farm upgrades contained within the package. The first package to be performed is the AN Valve Pit Upgrades package. The scope of the modifications includes new pit cover blocks, valve manifolds, leak detectors, transfer line connections (for future planned transfer lines), and special protective coating for the 241-AN-A and 241-AN-B valve pits

  15. 21 CFR 570.30 - Eligibility for classification as generally recognized as safe (GRAS).

    Science.gov (United States)

    2010-04-01

    ...), it may be used in food only within such limitation(s) (including the category of food(s), the... 21 Food and Drugs 6 2010-04-01 2010-04-01 false Eligibility for classification as generally recognized as safe (GRAS). 570.30 Section 570.30 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF...

  16. Determination of "safe" and "critical" nanoparticles exposure to welders in a workshop.

    Science.gov (United States)

    Gomes, J F; Miranda, R M

    2017-01-01

    The present study examined consequences of "safe" versus "critical" exposure to nanoparticles (NP) released during welding operations. With this aim in mind, a set of measurements regarding NP emissions was undertaken in a workshop during welding by metal active gas of carbon steel using different mixtures of argon (Ar) and carbon dioxide (CO 2 ) as well as different process parameters which might influence emission of (NP). If these measurements were conducted in several locations away from the welding sources, the graphical representation of the obtained observations with time enabled definition of "safe" and "critical" regions within a welding workshop in terms of welder's exposure. This information may be combined with the results of risk analysis derived by control banding and helps to categorize the sites where regulatory measures such as operation containment or dedicated exhaust ventilation need to be implemented.

  17. Safe semi-supervised learning based on weighted likelihood.

    Science.gov (United States)

    Kawakita, Masanori; Takeuchi, Jun'ichi

    2014-05-01

    We are interested in developing a safe semi-supervised learning that works in any situation. Semi-supervised learning postulates that n(') unlabeled data are available in addition to n labeled data. However, almost all of the previous semi-supervised methods require additional assumptions (not only unlabeled data) to make improvements on supervised learning. If such assumptions are not met, then the methods possibly perform worse than supervised learning. Sokolovska, Cappé, and Yvon (2008) proposed a semi-supervised method based on a weighted likelihood approach. They proved that this method asymptotically never performs worse than supervised learning (i.e., it is safe) without any assumption. Their method is attractive because it is easy to implement and is potentially general. Moreover, it is deeply related to a certain statistical paradox. However, the method of Sokolovska et al. (2008) assumes a very limited situation, i.e., classification, discrete covariates, n(')→∞ and a maximum likelihood estimator. In this paper, we extend their method by modifying the weight. We prove that our proposal is safe in a significantly wide range of situations as long as n≤n('). Further, we give a geometrical interpretation of the proof of safety through the relationship with the above-mentioned statistical paradox. Finally, we show that the above proposal is asymptotically safe even when n(')

  18. Handbook for the experimental open-pool irradiation facility of the Letaba Co-operative Limited, at Tzaneen

    International Nuclear Information System (INIS)

    Du Plessis, T.A.; Entwistle, B.; Gawn, P.D.

    1978-03-01

    A detailed technical description of the experimental food irradiator which was jointly established by the Atomic Energy Board and the Letaba Co-operative Limited at Tzaneen, is presented. The commissioning of the irradiator, the dosimetry and plant operating procedures are discussed. Attention is paid to the regulatory control of such an irradiator and a hazards evaluation and appropriate action to be taken is provided [af

  19. Critically safe volume vacuum pickup for use in wet or dry cleanup of radioactive enclosures

    International Nuclear Information System (INIS)

    Zeren, J.D.

    1993-01-01

    A physical compact vacuum pickup device of critically safe volume and geometric shape is provided for use in radioactive enclosures, such as a small glove box, to facilitate manual cleanup of either wet or dry radioactive material. The device is constructed and arranged so as to remain safe when filled to capacity with plutonium-239 oxide. Two fine mesh filter bags are supported on the exterior of a rigid fine mesh stainless steel cup. This assembly is sealed within, and spaced from, the interior walls of a stainless steel canister. An air inlet communicates with the interior of the canister. A modified conventional vacuum head is physically connected to, and associated with, the interior of the mesh cup. The volume of the canister, as defined by the space between the mesh cup and the interior walls of the canister, forms a critically safe volume and geometric shape for dry radioactive particles that are gathered within the canister. A critically safe liquid volume is maintained by operation of a suction terminating float valve, and/or by operation of redundant vacuum check/liquid drain valves and placement of the air inlet. 5 figures

  20. Children affected by HIV/AIDS: SAFE, a model for promoting their security, health, and development.

    Science.gov (United States)

    Betancourt, Theresa S; Fawzi, Mary K S; Bruderlein, Claude; Desmond, Chris; Kim, Jim Y

    2010-05-01

    A human security framework posits that individuals are the focus of strategies that protect the safety and integrity of people by proactively promoting children's well being, placing particular emphasis on prevention efforts and health promotion. This article applies this framework to a rights-based approach in order to examine the health and human rights of children affected by HIV/AIDS. The SAFE model describes sources of insecurity faced by children across four fundamental dimensions of child well-being and the survival strategies that children and families may employ in response. The SAFE model includes: Safety/protection; Access to health care and basic physiological needs; Family/connection to others; and Education/livelihoods. We argue that it is critical to examine the situation of children through an integrated lens that effectively looks at human security and children's rights through a holistic approach to treatment and care rather than artificially limiting our scope of work to survival-oriented interventions for children affected by HIV/AIDS. Interventions targeted narrowly at children, in isolation of their social and communal environment as outlined in the SAFE model, may in fact undermine protective resources in operation in families and communities and present additional threats to children's basic security. An integrated approach to the basic security and care of children has implications for the prospects of millions of children directly infected or indirectly affected by HIV/AIDS around the world. The survival strategies that young people and their families engage in must be recognized as a roadmap for improving their protection and promoting healthy development. Although applied to children affected by HIV/AIDS in the present analysis, the SAFE model has implications for guiding the care and protection of children and families facing adversity due to an array of circumstances from armed conflict and displacement to situations of extreme poverty.

  1. 40 CFR Table 9 to Subpart Eeee of... - Continuous Compliance With Operating Limits-High Throughput Transfer Racks

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Continuous Compliance With Operating Limits-High Throughput Transfer Racks 9 Table 9 to Subpart EEEE of Part 63 Protection of Environment...—Continuous Compliance With Operating Limits—High Throughput Transfer Racks As stated in §§ 63.2378(a) and (b...

  2. Determining Maximum Photovoltaic Penetration in a Distribution Grid considering Grid Operation Limits

    DEFF Research Database (Denmark)

    Kordheili, Reza Ahmadi; Bak-Jensen, Birgitte; Pillai, Jayakrishnan Radhakrishna

    2014-01-01

    High penetration of photovoltaic panels in distribution grid can bring the grid to its operation limits. The main focus of the paper is to determine maximum photovoltaic penetration level in the grid. Three main criteria were investigated for determining maximum penetration level of PV panels...... for this grid: even distribution of PV panels, aggregation of panels at the beginning of each feeder, and aggregation of panels at the end of each feeder. Load modeling is done using Velander formula. Since PV generation is highest in the summer due to irradiation, a summer day was chosen to determine maximum......; maximum voltage deviation of customers, cables current limits, and transformer nominal value. Voltage deviation of different buses was investigated for different penetration levels. The proposed model was simulated on a Danish distribution grid. Three different PV location scenarios were investigated...

  3. Safe Grid

    Science.gov (United States)

    Chow, Edward T.; Stewart, Helen; Korsmeyer, David (Technical Monitor)

    2003-01-01

    The biggest users of GRID technologies came from the science and technology communities. These consist of government, industry and academia (national and international). The NASA GRID is moving into a higher technology readiness level (TRL) today; and as a joint effort among these leaders within government, academia, and industry, the NASA GRID plans to extend availability to enable scientists and engineers across these geographical boundaries collaborate to solve important problems facing the world in the 21 st century. In order to enable NASA programs and missions to use IPG resources for program and mission design, the IPG capabilities needs to be accessible from inside the NASA center networks. However, because different NASA centers maintain different security domains, the GRID penetration across different firewalls is a concern for center security people. This is the reason why some IPG resources are been separated from the NASA center network. Also, because of the center network security and ITAR concerns, the NASA IPG resource owner may not have full control over who can access remotely from outside the NASA center. In order to obtain organizational approval for secured remote access, the IPG infrastructure needs to be adapted to work with the NASA business process. Improvements need to be made before the IPG can be used for NASA program and mission development. The Secured Advanced Federated Environment (SAFE) technology is designed to provide federated security across NASA center and NASA partner's security domains. Instead of one giant center firewall which can be difficult to modify for different GRID applications, the SAFE "micro security domain" provide large number of professionally managed "micro firewalls" that can allow NASA centers to accept remote IPG access without the worry of damaging other center resources. The SAFE policy-driven capability-based federated security mechanism can enable joint organizational and resource owner approved remote

  4. JET-ISX-B beryllium limiter experiment safety analysis report and operational safety requirements

    International Nuclear Information System (INIS)

    Edmonds, P.H.

    1985-09-01

    An experiment to evaluate the suitability of beryllium as a limiter material has been completed on the ISX-B tokamak. The experiment consisted of two phases: (1) the initial operation and characterization in the ISX experiment, and a period of continued operation to the specified surface fluence (10 22 atoms/cm 2 ) of hydrogen ions; and (2) the disassembly, decontamination, or disposal of the ISX facility. During these two phases of the project, the possibility existed for beryllium and/or beryllium oxide powder to be produced inside the vacuum vessel. Beryllium dust is a highly toxic material, and extensive precautions are required to prevent the release of the beryllium into the experimental work area and to prevent the contamination of personnel working on the device. Details of the health hazards associated with beryllium and the appropriate precautions are presented. Also described in appendixes to this report are the various operational safety requirements for the project

  5. High energy bursts from a solid state laser operated in the heat capacity limited regime

    Science.gov (United States)

    Albrecht, G.; George, E.V.; Krupke, W.F.; Sooy, W.; Sutton, S.B.

    1996-06-11

    High energy bursts are produced from a solid state laser operated in a heat capacity limited regime. Instead of cooling the laser, the active medium is thermally well isolated. As a result, the active medium will heat up until it reaches some maximum acceptable temperature. The waste heat is stored in the active medium itself. Therefore, the amount of energy the laser can put out during operation is proportional to its mass, the heat capacity of the active medium, and the temperature difference over which it is being operated. The high energy burst capacity of a heat capacity operated solid state laser, together with the absence of a heavy, power consuming steady state cooling system for the active medium, will make a variety of applications possible. Alternately, cooling takes place during a separate sequence when the laser is not operating. Industrial applications include new material working processes. 5 figs.

  6. Potential and limitations of radionuclide-based exercise testing before and after operation in the patient with coronary artery disease

    International Nuclear Information System (INIS)

    Borer, J.S.; Phillips, P.; Jacobstein, J.

    1982-01-01

    The authors assess the potential benefits and limitations of radionuclide cineangiography when used to select patients with ischemic heart disease for operation, to precisely plan the operation, and to assess the effects of such therapy. The results indicate that this technique provides potentially important benefits, but also several limitations. Additional studies are required to clarify the optimal role for this technique in the evaluation of the patient with coronary artery disease. (Auth.)

  7. Safe lifting in patients with chronic low back pain : Comparing FCE lifting task and NIOSH lifting guideline

    NARCIS (Netherlands)

    Kuijer, Wietske; Dijkstra, Pieter U.; Brouwer, Sandra; Reneman, Michiel F.; Groothoff, Johan W.; Geertzen, Jan H. B.

    2006-01-01

    Introduction: Both the floor-to-waist lifting task of the Isernhagen Work Systems Functional Capacity Evaluation (IWS FCE) and recommended weight limit (RWL) of the NIOSH produce safe lifting weights and are used world-wide nowadays. It is unknown whether they produce similar safe lifting weights.

  8. An approach to criteria, design limits and monitoring in nuclear fuel waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Simmons, G R; Baumgartner, P; Bird, G A; Davison, C C; Johnson, L H; Tamm, J A

    1994-12-01

    The Nuclear Fuel Waste Management Program has been established to develop and demonstrate the technology for safe geological disposal of nuclear fuel waste. One objective of the program is to show that a disposal system (i.e., a disposal centre and associated transportation system) can be designed and that it would be safe. Therefore the disposal system must be shown to comply with safety requirements specified in guidelines, standards, codes and regulations. The components of the disposal system must also be shown to operate within the limits specified in their design. Compliance and performance of the disposal system would be assessed on a site-specific basis by comparing estimates of the anticipated performance of the system and its components with compliance or performance criteria. A monitoring program would be developed to consider the effects of the disposal system on the environment and would include three types of monitoring: baseline monitoring, compliance monitoring, and performance monitoring. This report presents an approach to establishing compliance and performance criteria, limits for use in disposal system component design, and the main elements of a monitoring program for a nuclear fuel waste disposal system. (author). 70 refs., 9 tabs., 13 figs.

  9. An approach to criteria, design limits and monitoring in nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Simmons, G.R.; Baumgartner, P.; Bird, G.A.; Davison, C.C.; Johnson, L.H.; Tamm, J.A.

    1994-12-01

    The Nuclear Fuel Waste Management Program has been established to develop and demonstrate the technology for safe geological disposal of nuclear fuel waste. One objective of the program is to show that a disposal system (i.e., a disposal centre and associated transportation system) can be designed and that it would be safe. Therefore the disposal system must be shown to comply with safety requirements specified in guidelines, standards, codes and regulations. The components of the disposal system must also be shown to operate within the limits specified in their design. Compliance and performance of the disposal system would be assessed on a site-specific basis by comparing estimates of the anticipated performance of the system and its components with compliance or performance criteria. A monitoring program would be developed to consider the effects of the disposal system on the environment and would include three types of monitoring: baseline monitoring, compliance monitoring, and performance monitoring. This report presents an approach to establishing compliance and performance criteria, limits for use in disposal system component design, and the main elements of a monitoring program for a nuclear fuel waste disposal system. (author). 70 refs., 9 tabs., 13 figs

  10. Advanced operator interface design for CANDU-3 fuel handling system

    Energy Technology Data Exchange (ETDEWEB)

    Arapakota, D [Atomic Energy of Canada Ltd., Saskatoon, SK (Canada)

    1996-12-31

    The Operator Interface for the CANDU 3 Fuel Handling (F/H) System incorporates several improvements over the existing designs. A functionally independent sit-down CRT (cathode-ray tube) based Control Console is provided for the Fuel Handling Operator in the Main Control Room. The Display System makes use of current technology and provides a user friendly operator interface. Regular and emergency control operations can be carried out from this control console. A stand-up control panel is provided as a back-up with limited functionality adequate to put the F/H System in a safe state in case of an unlikely non-availability of the Plant Display System or the F/H Control System`. The system design philosophy, hardware configuration and the advanced display system features are described in this paper The F/H Operator Interface System developed for CANDU 3 can be adapted to CANDU 9 as well as to the existing stations. (author).

  11. Advanced operator interface design for CANDU-3 fuel handling system

    International Nuclear Information System (INIS)

    Arapakota, D.

    1995-01-01

    The Operator Interface for the CANDU 3 Fuel Handling (F/H) System incorporates several improvements over the existing designs. A functionally independent sit-down CRT (cathode-ray tube) based Control Console is provided for the Fuel Handling Operator in the Main Control Room. The Display System makes use of current technology and provides a user friendly operator interface. Regular and emergency control operations can be carried out from this control console. A stand-up control panel is provided as a back-up with limited functionality adequate to put the F/H System in a safe state in case of an unlikely non-availability of the Plant Display System or the F/H Control System'. The system design philosophy, hardware configuration and the advanced display system features are described in this paper The F/H Operator Interface System developed for CANDU 3 can be adapted to CANDU 9 as well as to the existing stations. (author)

  12. Estimate of safe human exposure levels for lunar dust based on comparative benchmark dose modeling.

    Science.gov (United States)

    James, John T; Lam, Chiu-Wing; Santana, Patricia A; Scully, Robert R

    2013-04-01

    Brief exposures of Apollo astronauts to lunar dust occasionally elicited upper respiratory irritation; however, no limits were ever set for prolonged exposure to lunar dust. The United States and other space faring nations intend to return to the moon for extensive exploration within a few decades. In the meantime, habitats for that exploration, whether mobile or fixed, must be designed to limit human exposure to lunar dust to safe levels. Herein we estimate safe exposure limits for lunar dust collected during the Apollo 14 mission. We instilled three respirable-sized (∼2 μ mass median diameter) lunar dusts (two ground and one unground) and two standard dusts of widely different toxicities (quartz and TiO₂) into the respiratory system of rats. Rats in groups of six were given 0, 1, 2.5 or 7.5 mg of the test dust in a saline-Survanta® vehicle, and biochemical and cellular biomarkers of toxicity in lung lavage fluid were assayed 1 week and one month after instillation. By comparing the dose--response curves of sensitive biomarkers, we estimated safe exposure levels for astronauts and concluded that unground lunar dust and dust ground by two different methods were not toxicologically distinguishable. The safe exposure estimates were 1.3 ± 0.4 mg/m³ (jet-milled dust), 1.0 ± 0.5 mg/m³ (ball-milled dust) and 0.9 ± 0.3 mg/m³ (unground, natural dust). We estimate that 0.5-1 mg/m³ of lunar dust is safe for periodic human exposures during long stays in habitats on the lunar surface.

  13. Engineering safe and secure cyber-physical systems the specification PEARL approach

    CERN Document Server

    Gumzej, Roman

    2016-01-01

    This book introduces the concept of holistic design and development of cyber physical systems to achieve their safe and secure operation. It shows that by following the standards for embedded system’s safety and using appropriate hardware and software components inherently safe system’s architectures can be devised and certified. While the standards already enable testing and certification of inherently safe and sound hardware, this is still not the case with software. The book demonstrates that Specification PEARL(SPEARL) addresses this issue and proposes appropriate solutions from the viewpoints of software engineering as well as concrete program components. By doing so it reduces the complexity of cyber physical systems design in an innovative way. Three ultimate goals are being followed in the course of defining this new PEARL standard, namely: 1. simplicity over complexity, 2. inherent real-time ability, and 3. conformity to safety integrity and security capability levels.

  14. The application of an event data store to safe operation

    International Nuclear Information System (INIS)

    Bowen, J.H.

    1977-01-01

    The problem has been considered of how those responsible in Industry could attempt to demonstrate the degree of safety which the First Report of the Major Hazard Committee in the U.K. indicated as a minimum for the public at large. Reliance on Codes of Practice appears inappropriate at this point in time. Documentary evidence on the lines of a Hazard Analysis, quantified with generalised failure data as obtainable from a Data Bank, is likewise rejected as not conveying sufficient confidence. The recommended approach would include Hazard Analysis as an essential feature; but would envisage a feedback of information from the early operations of the actual plant to update in Bayesian fashion the estimates, and to revise and review major assumptions about plant management and control, using techniques of multivariate analysis. Correlation of failure information from many 'similar' plants is recommended. The extension of Data Banks to include information of a more operational type is recommended; and, preferably in conjunction with this, techniques of operational research should be applied to test correct parametrization. Progress on all these aspects is reported. (orig.) [de

  15. On-state voltage drop based power limit detection of IGBT inverters

    DEFF Research Database (Denmark)

    Trintis, Ionut; Ghimire, Pramod; Munk-Nielsen, Stig

    2015-01-01

    Power density is a key performance factor in order to reduce the cost and size of a power converter. Because of the unknown junction temperature, today’s design margins are relatively high to ensure safe and a reliable operation. In this paper, the on-state voltage drop is measured online for all...... insulated gate bipolar transistors (IGBTs) in the inverter, using advanced gate driver. The die temperature is estimated and monitored on each device during power converter operation. Based on the monitored temperature in real time, the maximum power capability is detected. The output power is increased...... until a safe operating temperature of power modules. This enable a power density is increased by 11.16 kW/litre to 19.13 kW/litre in a low voltage power stack which is typically used in wind power converters. Experiment results are shown for safe operation of converter at around 1.2 MW, which is built...

  16. Workspace Safe Operation of a Force- or Impedance-Controlled Robot

    Science.gov (United States)

    Abdallah, Muhammad E. (Inventor); Hargrave, Brian (Inventor); Yamokoski, John D. (Inventor); Strawser, Philip A. (Inventor)

    2013-01-01

    A method of controlling a robotic manipulator of a force- or impedance-controlled robot within an unstructured workspace includes imposing a saturation limit on a static force applied by the manipulator to its surrounding environment, and may include determining a contact force between the manipulator and an object in the unstructured workspace, and executing a dynamic reflex when the contact force exceeds a threshold to thereby alleviate an inertial impulse not addressed by the saturation limited static force. The method may include calculating a required reflex torque to be imparted by a joint actuator to a robotic joint. A robotic system includes a robotic manipulator having an unstructured workspace and a controller that is electrically connected to the manipulator, and which controls the manipulator using force- or impedance-based commands. The controller, which is also disclosed herein, automatically imposes the saturation limit and may execute the dynamic reflex noted above.

  17. 40 CFR Table 14 to Subpart Uuu of... - Continuous Compliance With Operating Limits for Organic HAP Emissions From Catalytic Cracking Units

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Continuous Compliance With Operating Limits for Organic HAP Emissions From Catalytic Cracking Units 14 Table 14 to Subpart UUU of Part 63... Compliance With Operating Limits for Organic HAP Emissions From Catalytic Cracking Units As stated in § 63...

  18. 40 CFR Table 21 to Subpart Uuu of... - Continuous Compliance With Operating Limits for Organic HAP Emissions From Catalytic Reforming Units

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Continuous Compliance With Operating Limits for Organic HAP Emissions From Catalytic Reforming Units 21 Table 21 to Subpart UUU of Part 63... Compliance With Operating Limits for Organic HAP Emissions From Catalytic Reforming Units As stated in § 63...

  19. 14 CFR 101.25 - Operating limitations for Class 2-High Power Rockets and Class 3-Advanced High Power Rockets.

    Science.gov (United States)

    2010-01-01

    ... Power Rockets and Class 3-Advanced High Power Rockets. 101.25 Section 101.25 Aeronautics and Space... OPERATING RULES MOORED BALLOONS, KITES, AMATEUR ROCKETS AND UNMANNED FREE BALLOONS Amateur Rockets § 101.25 Operating limitations for Class 2-High Power Rockets and Class 3-Advanced High Power Rockets. When operating...

  20. Manpower development for safe operation of nuclear power plant. China. Steam generator maintenance, cleaning and repair. Activity: 3.1.8-Task-04. Technical report

    International Nuclear Information System (INIS)

    Esposito, J.N.

    1994-01-01

    The objective of this mission was to present detailed state-of-the-art information on steam generator design, operations and maintenance, to the management, engineers and operators of the Qinshan Nuclear Power Plants. In addition, some limited operation was presented by the Qinshan Nuclear Power Plant representatives in order to aid in focussing the presentations and promoting a high level of discussion

  1. Small nuclear reactor safety design requirements for autonomous operation

    International Nuclear Information System (INIS)

    Kozier, K.S.; Kupca, S.

    1997-01-01

    Small nuclear power reactors offer compelling safety advantages in terms of the limited consequences that can arise from major accident events and the enhanced ability to use reliable, passive means to eliminate their occurrence by design. Accordingly, for some small reactor designs featuring a high degree of safety autonomy, it may be-possible to delineate a ''safety envelope'' for a given set of reactor circumstances within which safe reactor operation can be guaranteed without outside intervention for time periods of practical significance (i.e., days or weeks). The capability to operate a small reactor without the need for highly skilled technical staff permanently present, but with continuous remote monitoring, would aid the economic case for small reactors, simplify their use in remote regions and enhance safety by limiting the potential for accidents initiated by inappropriate operator action. This paper considers some of the technical design options and issues associated with the use of small power reactors in an autonomous mode for limited periods. The focus is on systems that are suitable for a variety of applications, producing steam for electricity generation, district heating, water desalination and/or marine propulsion. Near-term prospects at low power levels favour the use of pressurized, light-water-cooled reactor designs, among which those having an integral core arrangement appear to offer cost and passive-safety advantages. Small integral pressurized water reactors have been studied in many countries, including the test operation of prototype systems. (author)

  2. High-gradient near-quench-limit operation of superconducting Tesla-type cavities in scope of the International Linear Collider

    Directory of Open Access Journals (Sweden)

    Mathieu Omet

    2014-07-01

    Full Text Available We report the successful demonstration of an ILC-like high-gradient near-quench-limit operation at the Superconducting RF Test Facility at the High Energy Accelerator Research Organization (KEK in Japan. Preparation procedures necessary for the accelerator operation were conducted, such as rf phase calibration, beam-based gradient calibration, and automated beam compensation. Test runs were performed successfully for nominal operation, high-loaded Q (Q_{L} operation, and automated P_{k}Q_{L} operation. The results are described in terms of the achieved precision and stabilities of gradients and phases.

  3. Identifying the limitations of conventional biofiltration of diffuse methane emissions at long-term operation.

    Science.gov (United States)

    Gómez-Cuervo, S; Hernández, J; Omil, F

    2016-08-01

    There is growing international concern about the increasing levels of greenhouse gases in the atmosphere, particularly CO2 and methane. The emissions of methane derived from human activities are associated with large flows and very low concentrations, such as those emitted from landfills and wastewater treatment plants, among others. The present work was focused on the biological methane degradation at diffuse concentrations (0.2% vv(-1)) in a conventional biofilter using a mixture of compost, perlite and bark chips as carrier. An extensive characterization of the process was carried out at long-term operation (250 days) in a fully monitored pilot plant, achieving stable conditions during the entire period. Operational parameters such as waterings, nitrogen addition and inlet loads and contact time influences were evaluated. Obtained results indicate that empty bed residence times within 4-8 min are crucial to maximize elimination rates. Waterings and the type of nitrogen supplied in the nutrient solution (ammonia or nitrate) have a strong impact on the biofilter performance. The better results compatible with a stable operation were achieved using nitrate, with elimination capacities up to 7.6 ± 1.1 g CH4 m(-3 )h(-1). The operation at low inlet concentrations (IC) implied that removal rates obtained were quite limited (ranging 3-8 g CH4 m(-3 )h(-1)); however, these results could be significantly increased (up to 20.6 g CH4 m(-3) h(-1)) at higher IC, which indicates that the mass transfer from the gas to the liquid layer surrounding the biofilm is a key limitation of the process.

  4. Nuclear operator liability amounts and financial security limits (Last updated: July 2014)

    International Nuclear Information System (INIS)

    2014-07-01

    This table aims to gather information on the amounts available to compensate potential victims of a nuclear incident in countries and economies having nuclear power plants and/or having ratified at least one of the international conventions on nuclear third party liability. In the table: - First tier corresponds to the liability amount imposed on the operator ('Operator's Liability Amount'). - Second tier corresponds to the amounts provided from public funds beyond the Operator's Liability Amount, to be made available by the State in whose territory the nuclear installation of the liable operator is situated ('Additional State Compensation'). - Third tier corresponds to public funds contributed jointly by all the States parties to the BSC or CSC according to a pre-determined formula ['Additional Compensation (International Arrangements)']. Please note that under Article V, subparagraph 1 of the Vienna Convention, 'The liability of the operator may be limited by the Installation State to not less than US $5 million for any one nuclear incident'. Subparagraph 3 of the same article further provides that 'The United States dollar referred to in this Convention is a unit of account equivalent to the value of the United States dollar in terms of gold on 29 April 1963, that is to say US $35 per one troy ounce of fine gold.' Therefore, in this table (1963: USD 5 million) means that a country applies the Operator's Liability Amount as provided under the Vienna Convention. SDR is a unit of account used by the International Monetary Fund and is based upon a basket of weighted currencies. The latest exchange rates of SDRs per currency units are available at http://www.imf.org/external/np/fin/data/rms_five.aspx

  5. 40 CFR Table 7 to Subpart Uuu of... - Continuous Compliance With Operating Limits for Metal HAP Emissions From Catalytic Cracking Units

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Continuous Compliance With Operating Limits for Metal HAP Emissions From Catalytic Cracking Units 7 Table 7 to Subpart UUU of Part 63... With Operating Limits for Metal HAP Emissions From Catalytic Cracking Units As stated in § 63.1564(c)(1...

  6. A safe inexpensive method to isolate high quality plant and fungal ...

    African Journals Online (AJOL)

    The most commonly used plant DNA isolation methods use toxic and hazardous chemicals (phenol, chloroform), which require special equipment to minimize exposure and may limit their use in certain environments. Commercial DNA extraction kits are convenient and usually safe, but their availability to certain developing ...

  7. Safe nuclear power for the Third World

    International Nuclear Information System (INIS)

    Johnson, W.R.; Lyon, C.F.; Redick, J.R.

    1989-01-01

    It is clear that using nuclear power for the generation of electricity is one way of reducing the emissions of CO 2 and other gases that contribute to the greenhouse effect. Equally clear is the fact that the reduction can be magnified by converting domestic, commercial, and industrial power-consuming activities from the direct use of fossil fuel sources to electrical energy. A major area for future progress in limiting CO 2 emissions is in the Third World, where population growth and expectations for a higher social and economic standard of living portend vast increases in future energy use. A number of problems come to mind as one contemplates the widespread expansion of nuclear energy use into the Third World. The authors propose a method involving the marriage of two currently evolving concepts by which nuclear electrical generation can be expanded throughout the world in a manner that will address these problems. The idea is to form multinational independent electric generating companies, or nuclear electric companies (NECs), that would design, build, operate, and service a standardized fleet of nuclear power plants. The plants would be of the Integral Fast Reactor (IFR) design, now under development at Argonne National Laboratory, and, in particular, a commercial conceptualization of the IFR sponsored by General Electric Company, the Power Reactor Inherently Safe Module (PRISM)

  8. Regulatory Considerations for the Long Term Cooling Safe Shutdown Requirements of the Passive Residual Heat Removal Systems in Advanced Reactors

    International Nuclear Information System (INIS)

    Sim, S. K.; Bae, S. H.; Kim, Y. S.; Hwang, Min Jeong; Bang, Young Seok; Hwang, Taesuk

    2016-01-01

    USNRC approved safe shutdown at 215.6 .deg. C for a safe and long term cooling state for the redundant passive RHRSs by SECY-94-084. USNRC issued COLA(Combined Construction and Operating License) for the Levy County NP Unit-1/2 for the AP1000 passive RHRSs in 2014. Korea Hydro and Nuclear Power(KHNP) is developing APR+ and adopted Passive Auxiliary Feedwater System(PAFS) as a new passive RHRS design. Korea Institute of Nuclear Safety(KINS) has been developing regulatory guides for the advanced safety design features of the advanced ALWRs which has plan to construct in near future in Korea[5]. Safety and regulatory issues as well as the safe shut down requirements of the passive RHRS are discussed and considerations in developing regulatory guides for the passive RHRS are presented herein. Passive RHRSs have been introduced as new safety design features for the advanced reactors under development in Korea. These passive RHRSs have potential advantages over existing active RHRS, however, their functions are limited due to inherent ability of passive heat removal processes. It is high time to evaluate the performance of the passive PRHRs and develop regulatory guides for the safety as well as the performance analyses of the passive RHRS

  9. Derivation of activity limits for the disposal of radioactive waste in near surface disposal facilities

    International Nuclear Information System (INIS)

    2003-12-01

    Radioactive waste must be managed safely, consistent with internationally agreed safety standards. The disposal method chosen for the waste should be commensurate with the hazard and longevity of the waste. Near surface disposal is an option used by many countries for the disposal of radioactive waste containing mainly short lived radionuclides and low concentrations of long lived radionuclides. The term 'near surface disposal' encompasses a wide range of design options, including disposal in engineered structures at or just below ground level, disposal in simple earthen trenches a few metres deep, disposal in engineered concrete vaults, and disposal in rock caverns several tens of metres below the surface. The use of a near surface disposal option requires design and operational measures to provide for the protection of human health and the environment, both during operation of the disposal facility and following its closure. To ensure the safety of both workers and the public (both in the short term and the long term), the operator is required to design a comprehensive waste management system for the safe operation and closure of a near surface disposal facility. Part of such a system is to establish criteria for accepting waste for disposal at the facility. The purpose of the criteria is to limit the consequences of events which could lead to radiation exposures and in addition, to prevent or limit hazards, which could arise from non-radiological causes. Waste acceptance criteria include limits on radionuclide content concentration in waste materials, and radionuclide amounts in packages and in the repository as a whole. They also include limits on quantity of free liquids, requirements for exclusion of chelating agents and pyrophoric materials, and specifications of the characteristics of the waste containers. Largely as a result of problems encountered at some disposal facilities operated in the past, in 1985 the IAEA published guidance on generic acceptance

  10. Switching speed limitations of high power IGBT modules

    DEFF Research Database (Denmark)

    Incau, Bogdan Ioan; Trintis, Ionut; Munk-Nielsen, Stig

    2015-01-01

    for the blocking dc-link voltage. Switching losses are analyzed upon a considerable variation of resistor value from turn-on gate driver side. Short circuit operations are investigated along with safe operating area for entire module to validate electrical capabilities under extreme conditions....

  11. New Developments in FPGA: SEUs and Fail-Safe Strategies from the NASA Goddard Perspective

    Science.gov (United States)

    Berg, Melanie D.; Label, Kenneth A.; Pellish, Jonathan

    2016-01-01

    It has been shown that, when exposed to radiation environments, each Field Programmable Gate Array (FPGA) device has unique error signatures. Subsequently, fail-safe and mitigation strategies will differ per FPGA type. In this session several design approaches for safe systems will be presented. It will also explore the benefits and limitations of several mitigation techniques. The intention of the presentation is to provide information regarding FPGA types, their susceptibilities, and proven fail-safe strategies; so that users can select appropriate mitigation and perform the required trade for system insertion. The presentation will describe three types of FPGA devices and their susceptibilities in radiation environments.

  12. Extension of operational limits on EAST

    International Nuclear Information System (INIS)

    Gao Xiang; Li Jiangang; Wan Baonian; Zhao Junyu; Hu Liqun; Liu Haiqing; Jie Yinxian; Xu Qiang; Wu Zhenwei; Yang Yu; Gong Xianzu; Shen Biao; Hu Jiansheng; Shi Yuejiang; Ling Bili; Wang Jun; Sajjad, S.; Zang Qing; Gao Wei; Zhang Tao; Yu Yaowei; Yang Yao; Han Xiaofeng; Shi Nan; Ming Tingfeng; Ti Ang; Zhang Wenyang; Xu Guosheng; Chen Junling; Luo Guangnan; Zhang Xiaodong; Mao Jianshan; Wan Yuanxi

    2007-01-01

    The first plasma has been achieved successfully in the Experimental Advanced Superconducting Tokamak (EAST). Boronization by the glow discharge (GDC) method was studied in experiments. The plasma performance was obviously improved by GDC boronization. Extension of the operational region and improvement in the plasma performance were obtained. Sawtooth discharges were observed by means of soft x-ray signals, electron cyclotron emission signals and line averaged electron density after boronization. Lower q a and more stable operation were also achieved following GDC boronization. The plasma current ramp-up rate was also improved as a result of decreased impurity content and low averaged loop voltage due to boronization

  13. Fail-safe first wall for preclusion of little leakage

    International Nuclear Information System (INIS)

    Shibui, Masanao; Nakahira, Masataka; Tada, Eisuke; Takatsu, Hideyuki

    1994-05-01

    Leakages although excluded by design measures would occur most probably in highly stressed areas, weldments and locations without possibility to classify the state by in-service inspection. In a water-cooled first wall, allowable leak rate of water is generally very small, and therefore, locating of the leak portion under highly activated environment will be very difficult and be time-consuming. The double-wall concept is promising for the ITER first wall, because it can be made fail-safe by the application of the leak-before-break and the multiple load path concepts, and because it has a potential capability to solve the little leak problem. When the fail safe strength is well defined, subcritical crack growth in the damaged wall can be permitted. This will enable to detect stable leakage of coolant without deteriorating plasma operation. The paper deals with the little leak problem and presents method for evaluating small leak rate of a liquid coolant from crack-like defects. The fail-safe first wall with the double-wall concept is also proposed for preclusion of little leakage and its fail-safety is discussed. (author)

  14. Maintaining the safe operation of U.S. nuclear power plants

    International Nuclear Information System (INIS)

    Skavdahl, R.E.

    1991-01-01

    The more than one hundred nuclear power plants in the U.S. are a vital resource that provides about 20% of the electrical power production. Although about half the plants are more than 15 years old, there is no evidence of age-related deterioration in any of the key indicators of industry performance; indeed, the continuing improvement in all these indicators shows the industry is maturing, not growing old. The Institute for Nuclear Power Operations's performance assessment and training programs have spurred a heavy industry-wide commitment to improved training. These efforts are the key to excellence in the performance of operations and maintenance personnel. The interface between the reactor and the operator has been improved through control room design reviews, the implementation of a Safety Parameter Display System, and emergency procedure guidelines. These improvements ensure that the operators will be able to perform their functions under any circumstances they may encounter. Led by NUMARC, the industry initiative to improve plant maintenance programs incorporates such elements as the INPO performance standards, enhanced monitoring through the use of the Nuclear Plant Reliability Data System, Reliability Centered Maintenance, and improvements in plant technical specifications. These elements bring the latest available technology to plant maintenance programs. Equipment replacements are frequently made to take advantage of improvements in technology. Aside from the performance enhancements they offer, such replacements also serve to keep the plants young. By leveraging their resources through the owners groups, utilities are able to quickly and efficiently solve problems together that they could not afford to attack individually. Even the highly unlikely hypothetical severe accidents are addressed in a systematic fashion through the application of Probabilistic Risk Assessments. 15 figs

  15. What Influences Youth to Operate All-Terrain Vehicles Safely?

    Science.gov (United States)

    Grummon, A. H.; Heaney, C. A.; Dellinger, W. A.; Wilkins, J. R., III

    2014-01-01

    The operation of all-terrain vehicles (ATVs) by youth has contributed to the incidence of serious and fatal injuries among children. This study explored factors related to the frequency with which youth wore a helmet and refrained from engaging in three risky driving behaviors (driving at risky speeds, on paved roads and on unfamiliar terrain)…

  16. Inherently safe high temperature gas-cooled reactor

    International Nuclear Information System (INIS)

    Yamada, Masao; Hayakawa, Hitoshi

    1987-01-01

    It is recognized in general that High Temperature Gas-cooled Reactors have remarkable characteristics in inherent safety and it is well known that credits of the time margin have been admitted for accident evaluation in the licensing of the currently operating prototype HTGRs (300 MWe class). Recently, more inherently safe HTGRs are being developed in various countries and drawing attention on their possibility for urban siting. The inherent safety characteristics of these HTRs differ each other depending on their design philosophy and on the features of the components/structures which constitute the plant. At first, the specific features/characteristics of the elemental components/structures of the HTRs are explained one by one and then the overall safety features/characteristics of these HTR plants are explained in connection with their design philosophy and combination of the elemental features. Taking the KWU/Interatom Modular Reactor System as an example, the particular design philosophy and safety characteristics of the inherently safe HTR are explained with a result of preliminary evaluation on the possibility of siting close to densely populated area. (author)

  17. In Situ Surgery: Is It Safe ? (Experience with 60 cases) | El Sadat ...

    African Journals Online (AJOL)

    Conclusion: NSU is a safe place for performing in-situ surgery (ISS) without increased risk of infection. Successful operative intervention within NSU requires good planning and cooperation between anesthesiologist, surgeons, neonatologist and nursing staff. Maximum benefit is observed in neonates who have definite risk ...

  18. Safe surgery: how accurate are we at predicting intra-operative blood loss?

    LENUS (Irish Health Repository)

    2012-02-01

    Introduction Preoperative estimation of intra-operative blood loss by both anaesthetist and operating surgeon is a criterion of the World Health Organization\\'s surgical safety checklist. The checklist requires specific preoperative planning when anticipated blood loss is greater than 500 mL. The aim of this study was to assess the accuracy of surgeons and anaesthetists at predicting intra-operative blood loss. Methods A 6-week prospective study of intermediate and major operations in an academic medical centre was performed. An independent observer interviewed surgical and anaesthetic consultants and registrars, preoperatively asking each to predict expected blood loss in millilitre. Intra-operative blood loss was measured and compared with these predictions. Parameters including the use of anticoagulation and anti-platelet therapy as well as intra-operative hypothermia and hypotension were recorded. Results One hundred sixty-eight operations were included in the study, including 142 elective and 26 emergency operations. Blood loss was predicted to within 500 mL of measured blood loss in 89% of cases. Consultant surgeons tended to underestimate blood loss, doing so in 43% of all cases, while consultant anaesthetists were more likely to overestimate (60% of all operations). Twelve patients (7%) had underestimation of blood loss of more than 500 mL by both surgeon and anaesthetist. Thirty per cent (n = 6\\/20) of patients requiring transfusion of a blood product within 24 hours of surgery had blood loss underestimated by more than 500 mL by both surgeon and anaesthetist. There was no significant difference in prediction between patients on anti-platelet or anticoagulation therapy preoperatively and those not on the said therapies. Conclusion Predicted intra-operative blood loss was within 500 mL of measured blood loss in 89% of operations. In 30% of patients who ultimately receive a blood transfusion, both the surgeon and anaesthetist significantly underestimate

  19. Operating results and experience and operating regimes in changing demands of energy world

    International Nuclear Information System (INIS)

    Hobza, L.

    2004-01-01

    In this paper, there are stated some operating results and experience obtained from trial operation of Temelin NPP. In Europe, Temelin NPP is presently one of the latest implemented projects of the series of VVER 1000 nuclear units with proven V-320 pressurized water reactor. The distinction between Temelin NPP and original project lays mainly in supply of nuclear fuel and in I and C systems delivered by Westinghouse Company. Temelin NPP has passed through commissioning period and trial operation. The main goal of the trial operation was to meet the requirements of section 2, par. 4, point b) of Decree No. 106/98 Sb. and verification of project parameters and stability of operation, and the situation leading to violation of safety functions fulfilment according to Pre-operational Safety Report should not occur. The integral part of trial operation assessment was also successful performing of determined monitoring programmes, first refuelling and performing of prescribed tests and operational inspections. Simultaneously, first experience was obtained with nuclear fuel; providing of ancillary services; reliability of important components; operation of turbine-generator 1000 MW; chemical regime; influence to environment; and quality of contractors. As safety is the most important indicator, it can be stated that: no facts which would lead to decreasing of safety systems operability have been detected; no facts which would lead to negative affecting of barriers against fading the radioactivity into both working areas and environment, have been detected; good condition of fire safety has been continuously documented; requirements of limits for releasing waste water into environment have been continuously complied with; requirements of limits for releasing radioactive substances (in gaseous and/or liquid state) into environment have been continuously complied with. From the operation regimes point of view is clear, that it would be suitable for the power plant if the

  20. Adoption of the B2SAFE EUDAT replication service by the EPOS community

    Science.gov (United States)

    Cacciari, Claudio; Fares, Massimo; Fiameni, Giuseppe; Michelini, Alberto; Danecek, Peter; Wittenburg, Peter

    2014-05-01

    B2SAFE is the EUDAT service for moving and replicating data between sites and storage systems for different purposes. The goal of B2SAFE is to keep the data from a repository safe by replicating it across different geographical and administrative zones according to a set of well-defined policies. It is also a way to store large volumes of data permanently at those sites which are providing powerful on-demand data analysis facilities. In particular, B2SAFE operates on the domain of registered data where data objects are referable via persistent identifiers (PIDs). B2SAFE is more than just copying data because the PIDs must be carefully managed when data objects are moved or replicated. The EUDAT B2SAFE Service offers functionality to replicate datasets across different data centres in a safe and efficient way while maintaining all information required to easily find and query information about the replica locations. The information about the replica locations and other important information is stored in PID records, each managed in separate administrative domains. The B2SAFE Service is implemented as an iRODS module providing a set of iRODS rules or policies to interface with the EPIC handle API and uses the iRODS middleware to replicate datasets from a source data (or community) centre to a destination data centre. The definition of the dataset(s) to replicate is flexible and up to the communities using the B2SAFE service. While the B2SAFE is internally using the EPIC handle API, communities have the choice to use any PID system they prefer to assign PIDs to their digital objects. A reference to one or more EUDAT B2SAFE PIDs is returned by the B2SAFE service when a dataset is replicated. The presentation will introduce the problem space of B2SAFE, presents the achievements that have been made during the last year for enabling communities to make use of the B2SAFE service, demonstrates a EPOS use cases, outlines the commonalities and differences between the policies

  1. A National Evaluation of Safe Schools/Healthy Students: Outcomes and Influences

    Science.gov (United States)

    Derzon, James H.; Yu, Ping; Ellis, Bruce; Xiong, Sharon; Arroyo, Carmen; Mannix, Danyelle; Wells, Michael E.; Hill, Gary; Rollison, Julia

    2012-01-01

    The Safe Schools/Healthy Students (SS/HS) Initiative has awarded over $2 billion in grants to more than 350 school districts in partnership with local mental health, law enforcement, and juvenile justice agencies. To estimate the impact of grantee characteristics, grant operations, and near-term outcomes in reducing violence and substance use,…

  2. Operational limits on WEST inertial divertor sector during the early phase experiment

    Science.gov (United States)

    Firdaouss, M.; Corre, Y.; Languille, P.; Greuner, H.; Autissier, E.; Desgranges, C.; Guilhem, D.; Gunn, J. P.; Lipa, M.; Missirlian, M.; Pascal, J.-Y.; Pocheau, C.; Richou, M.; Tsitrone, E.

    2016-02-01

    The primary goal of the WEST project is to be a test bed to characterize the fatigue and lifetime of ITER-like W divertor components subjected to relevant thermal loads. During the first phase of exploitation (S2 2016), these components (W monoblock plasma facing unit—W-PFU) will be installed in conjunction with graphite components (G-PFU). Since the G-PFU will not be actively cooled, it is necessary to ensure the expected pulse duration allows the W-PFU to reach its steady state without overheating the G-PFU assembly structure or the embedded stainless-steel diagnostics. High heat flux tests were performed at the GLADIS facility to assess the thermal behavior of the G-PFU. Some operational limits based on plasma parameters were determined. It was found that it is possible to operate at an injected power such that the maximal incident heat flux on the lower divertor is 10 MW m-2 for the required pulse length.

  3. Operational limits on WEST inertial divertor sector during the early phase experiment

    International Nuclear Information System (INIS)

    Firdaouss, M; Corre, Y; Languille, P; Autissier, E; Desgranges, C; Guilhem, D; Gunn, J P; Lipa, M; Missirlian, M; Pascal, J-Y; Pocheau, C; Richou, M; Tsitrone, E; Greuner, H

    2016-01-01

    The primary goal of the WEST project is to be a test bed to characterize the fatigue and lifetime of ITER-like W divertor components subjected to relevant thermal loads. During the first phase of exploitation (S2 2016), these components (W monoblock plasma facing unit—W-PFU) will be installed in conjunction with graphite components (G-PFU). Since the G-PFU will not be actively cooled, it is necessary to ensure the expected pulse duration allows the W-PFU to reach its steady state without overheating the G-PFU assembly structure or the embedded stainless-steel diagnostics. High heat flux tests were performed at the GLADIS facility to assess the thermal behavior of the G-PFU. Some operational limits based on plasma parameters were determined. It was found that it is possible to operate at an injected power such that the maximal incident heat flux on the lower divertor is 10 MW m −2 for the required pulse length. (paper)

  4. The use of service limits for efficient operation of multi-station single-medium communication systems

    NARCIS (Netherlands)

    Borst, S.C.; Boxma, O.J.; Levy, H.

    1995-01-01

    Time limits are the major mechanisms used for controlling a large variety of multistation single-medium computer-communication systems like the FDDI network and the IEEE 802.4 Token Bus. The proper use of these mechanisms is still not understood and rules for efficient system operation are not

  5. Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (Arabic Edition)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-07-01

    . The standards are also applied by regulatory bodies and operators around the world to enhance safety in nuclear power generation and in nuclear applications in medicine, industry, agriculture and research. Safety is not an end in itself but a prerequisite for the purpose of the protection of people in all States and of the environment - now and in the future. The risks associated with ionizing radiation must be assessed and controlled without unduly limiting the contribution of nuclear energy to equitable and sustainable development. Governments, regulatory bodies and operators everywhere must ensure that nuclear material and radiation sources are used beneficially, safely and ethically. The IAEA safety standards are designed to facilitate this, and I encourage all Member States to make use of them.

  6. Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (Chinese Edition)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-03-01

    . The standards are also applied by regulatory bodies and operators around the world to enhance safety in nuclear power generation and in nuclear applications in medicine, industry, agriculture and research. Safety is not an end in itself but a prerequisite for the purpose of the protection of people in all States and of the environment - now and in the future. The risks associated with ionizing radiation must be assessed and controlled without unduly limiting the contribution of nuclear energy to equitable and sustainable development. Governments, regulatory bodies and operators everywhere must ensure that nuclear material and radiation sources are used beneficially, safely and ethically. The IAEA safety standards are designed to facilitate this, and I encourage all Member States to make use of them.

  7. Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (French Edition)

    International Nuclear Information System (INIS)

    2013-01-01

    conventions. The standards are also applied by regulatory bodies and operators around the world to enhance safety in nuclear power generation and in nuclear applications in medicine, industry, agriculture and research. Safety is not an end in itself but a prerequisite for the purpose of the protection of people in all States and of the environment - now and in the future. The risks associated with ionizing radiation must be assessed and controlled without unduly limiting the contribution of nuclear energy to equitable and sustainable development. Governments, regulatory bodies and operators everywhere must ensure that nuclear material and radiation sources are used beneficially, safely and ethically. The IAEA safety standards are designed to facilitate this, and I encourage all Member States to make use of them.

  8. Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (Chinese Edition)

    International Nuclear Information System (INIS)

    2013-01-01

    . The standards are also applied by regulatory bodies and operators around the world to enhance safety in nuclear power generation and in nuclear applications in medicine, industry, agriculture and research. Safety is not an end in itself but a prerequisite for the purpose of the protection of people in all States and of the environment - now and in the future. The risks associated with ionizing radiation must be assessed and controlled without unduly limiting the contribution of nuclear energy to equitable and sustainable development. Governments, regulatory bodies and operators everywhere must ensure that nuclear material and radiation sources are used beneficially, safely and ethically. The IAEA safety standards are designed to facilitate this, and I encourage all Member States to make use of them.

  9. Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (Arabic Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    . The standards are also applied by regulatory bodies and operators around the world to enhance safety in nuclear power generation and in nuclear applications in medicine, industry, agriculture and research. Safety is not an end in itself but a prerequisite for the purpose of the protection of people in all States and of the environment - now and in the future. The risks associated with ionizing radiation must be assessed and controlled without unduly limiting the contribution of nuclear energy to equitable and sustainable development. Governments, regulatory bodies and operators everywhere must ensure that nuclear material and radiation sources are used beneficially, safely and ethically. The IAEA safety standards are designed to facilitate this, and I encourage all Member States to make use of them.

  10. Conduct of Operations at Nuclear Power Plants. Safety Guide (Spanish Edition); Realizacion de operaciones en centrales nucleares. Guia de seguridad

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-04-15

    This Safety Guide identifies the main responsibilities and practices of nuclear power plant (NPP) operations departments in relation to their responsibility for the safe functioning of the plant. The guide presents the factors to be considered in structuring the operations department of an NPP; setting high standards of performance; making safety related decisions in an effective manner; conducting control room and field activities in a thorough and professional manner; and maintaining an NPP within established operational limits and conditions. Contents: 1. Introduction; 2. Management and organization of plant operations; 3. Shift complement and functions; 4. Shift routines and operating practices; 5. Control of equipment and plant status; 6. Operations equipment and operator aids; 7. Work control and authorization.

  11. The safety approach in the operation of EDF power plants

    International Nuclear Information System (INIS)

    Bertron, L.; Mira, J.J.

    1988-01-01

    To get a view on what is involved in maintaining a high level of safety in the operation of EdF nuclear power plants, it may be recalled that in 1987, 76 % of the EdF production was nuclear. The nuclear plants include thirty-four standard PWR 900 plants, fourteen PWR 1300 plants, the 305 MW SENA PWR, the four 500 MW GCR: CHINON A3 plant, St-LAURENT A1 (390 MW), A2 (450 MW) and BUGEY 1 (540 MW), the 233 MW PHENIX fast breeder reactor and the CREYS-MALVILLE 1200 MW fast breeder reactor, now being prepared for a new startup after the 1987 incident. So the importance of a safe operation of this investment is considerable for EdF, which is the designer, owner, industrial architect and operator. According to the French regulations, EdF is responsible for the safe operation of its power plants. A considerable human component is also at stake, as the safe operation of plants implies all the personnel to varying degrees. There are 15,000 such employees, all of whom have to be trained, competent and motivated. The operation of this system for 340 reactor-years has to-date resulted in no incident of any significant impact on the environment. Right from the start, safety in operation has always been an essential and clearly stated priority. Among other lessons the Three-Mile Island and Chernobyl accidents have reinforced the conviction that the human factors, the man-machine interface, and the safety culture were determining elements. With forty-eigh PWR plants in service, the problem is to maintain safe operation of a system now running at cruising speed, but also including some units (particularly the GCRs) that must be prepared for decommissioning. In addition EDF has to demonstrate the safe operations of CREYS MALVILLE, fast breeder reactor

  12. The Pennsylvania State University Light Water Ultra-Safe Plant Concept: 3rd quarter progress report

    International Nuclear Information System (INIS)

    Klevans, E.

    1987-01-01

    Progress in the Ultra Safe study has substantially increased since the last report. The search for pressurizing pump turbine component information is now complete and a final plant layout for detailed evaluation has been chosen. Significant results for the normal operation performance of the Ultra Safe pressurizing technique are included. The plan of attack for the evaluation of the Ultra Safe shutdown scenario and natural circulation capability is discussed. This process is expected to be the next key area for analysis. The reactor design is complete including a change to alleviate the need for a soluble boron system. Material on the reactor building layout is also provided

  13. ALMA Array Operations Group process overview

    Science.gov (United States)

    Barrios, Emilio; Alarcon, Hector

    2016-07-01

    ALMA Science operations activities in Chile are responsibility of the Department of Science Operations, which consists of three groups, the Array Operations Group (AOG), the Program Management Group (PMG) and the Data Management Group (DMG). The AOG includes the Array Operators and have the mission to provide support for science observations, operating safely and efficiently the array. The poster describes the AOG process, management and operational tools.

  14. Selection/licensing of nuclear power plant operators

    International Nuclear Information System (INIS)

    Saari, L.M.

    1983-07-01

    An important aspect of nuclear power plant (NPP) safety is the reactor operator in the control room. The operators are the first individuals to deal with an emergency situation, and thus, effective performance on their part is essential for safe plant operations. Important issues pertaining to NPP reactor operators would fall within the personnel subsystem of our safety system analysis. While there are many potential aspects of the personnel subsystem, a key first step in this focus is the selection of individuals - attempting to choose individuals for the job of reactor operator who will safely perform the job. This requires a valid (job-related) selection process. Some background information on the Nuclear Regulatory Commission (NRC) licensing process used for selecting NPP reactor operators is briefly presented and a description of a research endeavor now underway at Battelle for developing a valid reactor operator licensing examination is included

  15. B cells in operational tolerance.

    Science.gov (United States)

    Chesneau, M; Danger, R; Soulillou, J-P; Brouard, S

    2018-02-16

    Transplantation is currently the therapy of choice for endstage organ failure even though it requires long-term immunosuppresive therapy, with its numerous side effects, for acceptance of the transplanted organ. In rare cases however, patients develop operational tolerance, that is, graft survival without immunosuppression. Studies conducted on these patients reveal genetic, phenotypic, and functional signatures. They provide a better understanding of the immunological mechanisms involved in operational tolerance and define biomarkers that could be used to adapt immunosuppressive treatment to the individual, safely reduce immunosuppression doses, and ideally and safely guide immunosuppression withdrawal. This review summarizes studies that suggest a role for B cells as biomarkers of operational tolerance and discusses the use of B cells as a predictive tool for immunologic risk. Copyright © 2018. Published by Elsevier Inc.

  16. The operation and maintenance manual

    International Nuclear Information System (INIS)

    Klein, W.; Krotil, H.; Stoll, A.

    1975-01-01

    The Operating Manual is one of many technical documents which the nuclear power plant operator needs for ensuring safe operation. For the operating staff, however, there is only one document, namely the Operating Manual. It contains, appropriately arranged, the necessary system and other diagrams, drawings, lists, licensing documents and similar material, which are necessary for understanding the design, for testing, for obtaining the operating licence and for the operation of individual systems and of the entire plant. (orig./RW) [de

  17. Building world-wide nuclear industry success stories - Safe management of nuclear waste and used nuclear fuel

    International Nuclear Information System (INIS)

    Saint-Pierre, S.

    2005-01-01

    Full text: This WNA Position Statement summarizes the worldwide nuclear industry's record, progress and plans in safely managing nuclear waste and used nuclear fuel. The global industry's safe waste management practices cover the entire nuclear fuel-cycle, from the mining of uranium to the long-term disposal of end products from nuclear power reactors. The Statement's aim is to provide, in clear and accurate terms, the nuclear industry's 'story' on a crucially important subject often clouded by misinformation. Inevitably, each country and each company employs a management strategy appropriate to a specific national and technical context. This Position Statement reflects a confident industry consensus that a common dedication to sound practices throughout the nuclear industry worldwide is continuing to enhance an already robust global record of safe management of nuclear waste and used nuclear fuel. This text focuses solely on modern civil programmes of nuclear-electricity generation. It does not deal with the substantial quantities of waste from military or early civil nuclear programmes. These wastes fall into the category of 'legacy activities' and are generally accepted as a responsibility of national governments. The clean-up of wastes resulting from 'legacy activities' should not be confused with the limited volume of end products that are routinely produced and safely managed by today's nuclear energy industry. On the significant subject of 'Decommissioning of Nuclear Facilities', which is integral to modern civil nuclear power programmes, the WNA will offer a separate Position Statement covering the industry's safe management of nuclear waste in this context. The safe management of nuclear waste and used nuclear fuel is a widespread, well-demonstrated reality. This strong safety record reflects a high degree of nuclear industry expertise and of industry responsibility toward the well-being of current and future generations. Accumulating experience and

  18. Are Detox Diets Safe?

    Science.gov (United States)

    ... Safe Videos for Educators Search English Español Are Detox Diets Safe? KidsHealth / For Teens / Are Detox Diets ... seguras las dietas de desintoxicación? What Is a Detox Diet? The name sounds reassuring — everyone knows that ...

  19. Safe operation of nuclear power plants - Is safety culture an adequate management method?

    International Nuclear Information System (INIS)

    Piirto, A.

    2012-01-01

    One of the characteristics of a good safety culture is a definable commitment to the improvement of safety behaviours and attitudes at all organisational levels. A second characteristic of an organisation with excellent safety culture is free and open communication. The general understanding has been that safety culture is a part of organisation culture. In addition to safety culture thinking, proactive programmes and displays of proactive work to improve safety are required. This work needs to include, qt a minimum, actions aiming at reducing human errors, the development of human error prevention tools, improvements in training, and the development of working methods and the organisation's activities. Safety depends not only on the technical systems, but also on the organisation. There is a need for better methods and tools for organisational assessment and development. Today there is universal acceptance of the significant impact that management and organisational factors have over the safety significance of complex industrial installations such as nuclear power plants. Many events with significant economic and public impact had causes that have been traced to management deficiencies. The objective of this study is development of new methods to increase safety of nuclear power plant operation. The research has been limited to commercial nuclear power plants that are intended for electrical power generation in Finland. Their production activities, especially operation and maintenance, are primarily reviewed from a safety point of view, as well as human performance and organisational factors perspective. This defines the scope and focus of the study. The research includes studies related to knowledge management and tacit knowledge in the project management context and specific studies related to transfer of tacit knowledge in the maintenance organization and transfer of tacit knowledge between workers of old generation and young generation. The empirical results

  20. Safe operation of nuclear power plants - Is safety culture an adequate management method?

    Energy Technology Data Exchange (ETDEWEB)

    Piirto, A.

    2012-07-01

    One of the characteristics of a good safety culture is a definable commitment to the improvement of safety behaviours and attitudes at all organisational levels. A second characteristic of an organisation with excellent safety culture is free and open communication. The general understanding has been that safety culture is a part of organisation culture. In addition to safety culture thinking, proactive programmes and displays of proactive work to improve safety are required. This work needs to include, qt a minimum, actions aiming at reducing human errors, the development of human error prevention tools, improvements in training, and the development of working methods and the organisation's activities. Safety depends not only on the technical systems, but also on the organisation. There is a need for better methods and tools for organisational assessment and development. Today there is universal acceptance of the significant impact that management and organisational factors have over the safety significance of complex industrial installations such as nuclear power plants. Many events with significant economic and public impact had causes that have been traced to management deficiencies. The objective of this study is development of new methods to increase safety of nuclear power plant operation. The research has been limited to commercial nuclear power plants that are intended for electrical power generation in Finland. Their production activities, especially operation and maintenance, are primarily reviewed from a safety point of view, as well as human performance and organisational factors perspective. This defines the scope and focus of the study. The research includes studies related to knowledge management and tacit knowledge in the project management context and specific studies related to transfer of tacit knowledge in the maintenance organization and transfer of tacit knowledge between workers of old generation and young generation. The empirical

  1. Load of Co-60 in large gamma irradiators: a safe proceeding

    International Nuclear Information System (INIS)

    Luca, Gilmara C.; Paquer, Daniela

    2011-01-01

    The inclusion of new Co-60 sources in industrial irradiators is an extra procedure to its operation and extremely critical. The operation requires planning, attention, responsibility and a well trained staff. Radiation level, package contamination and radioactive material escape evaluations are essential as measurement of pre-loading safety. The package transfer for the swimming pool i e the most critical moment of the operation. After sources transfer to the racks, it is necessary the monitoring of tools, package and sources through the scrubbing test. Notwithstanding to be a critical operation, the risk is minimized when it is performed according to safe rules and radiation protection, and in the process performed the individual accumulated doses does not exceed 50 to μSv

  2. Manual for the operation of research reactors

    International Nuclear Information System (INIS)

    1965-01-01

    The great majority of the research reactors in newly established centres are light-water cooled and are often also light-water moderated. Consequently, the IAEA has decided to publish in its Technical Reports Series a manual dealing with the technical and practical problems associated with the safe and efficient operation of this type of reactor. Even though this manual is limited to light-water reactors in its direct application and presents the practices and experience at one specific reactor centre, it may also be useful for other reactor types because of the general relevance of the problems discussed and the long experience upon which it is based. It has, naturally, no regulatory character but it is hoped that it will be found helpful by staff occupied in all phases of the practical operation of research reactors, and also by those responsible for planning their experimental use. 23 refs, tabs

  3. An overview of the regulation of the activities of Eldorado Nuclear Limited in Port Hope, Ontario

    International Nuclear Information System (INIS)

    Smythe, W.D.

    1980-09-01

    Eldorado Nuclear Limited's operations at Port Hope, Ontario include both chemical and metallurgical processes involved in processing uranium in various forms. The plant processes natural uranium for both the domestic and export markets, and processes enriched uranium for the fuel in Canada's research reactors and for booster fuel for Candu reactors. The plant receives wastes from fuel fabrication plants and recycles them to recover uranium, and also produces wastes of its own. The Atomic Energy Control Board (AECB) is involved at all stages of this operation, as the agency responsible for nuclear materials management, safeguards, occupational health and safety, and safe disposal of wastes in all Canada's nuclear facilities. The AECB has also been involved in the clean up of contamination from the early days of operations in Port Hope

  4. Safe Anesthesia For Every Tot

    DEFF Research Database (Denmark)

    Weiss, Markus; Vutskits, Laszlo; Hansen, Tom G

    2015-01-01

    PURPOSE OF REVIEW: The term 'safe use of anesthesia in children is ill-defined and requires definition of and focus on the 'safe conduct of pediatric anesthesia'. RECENT FINDINGS: The Safe Anesthesia For Every Tot initiative (www.safetots.org) has been set up during the last year to focus...... on the safe conduct of pediatric anesthesia. This initiative aims to provide guidance on markers of quality anesthesia care. The introduction and implementation of national regulations of 'who, where, when and how' are required and will result in an improved perioperative outcome in vulnerable children....... The improvement of teaching, training, education and supervision of the safe conduct of pediatric anesthesia are the main goals of the safetots.org initiative. SUMMARY: This initiative addresses the well known perioperative risks in young children, perioperative causes for cerebral morbidity as well as gaps...

  5. 40 CFR 63.3556 - How do I establish the emission capture system and add-on control device operating limits during...

    Science.gov (United States)

    2010-07-01

    ... system and add-on control device operating limits during the performance test? 63.3556 Section 63.3556... of key parameters of the valve operating system (e.g., solenoid valve operation, air pressure.../outlet Concentration Option § 63.3556 How do I establish the emission capture system and add-on control...

  6. Model Code of Safe Practice in the Petroleum Industry: Pt. 8

    Energy Technology Data Exchange (ETDEWEB)

    1991-01-01

    This code has been prepared for use on a worldwide basis as a guide to safe practice for those concerned with drilling and production operations for oil and gas in offshore areas. It is intended to provide information and guidance on those offshore drilling, production and support activities which have an impact on safety and therefore require detailed care and attention. Each chapter of the Code covers an important drilling, production or support activity and has an introduction which describes the part each activity plays in the overall offshore operation. (author).

  7. Intrinsically Safe Robot Arm : Adjustable Static Balancing and Low Power Actuation

    NARCIS (Netherlands)

    Vermeulen, M.; Wisse, M.

    2010-01-01

    We present a design for a manipulator that is intrinsically mechanically safe, i.e. it can not cause pain (let alone damage) to a human being even if the control system has a failure. Based on the pressure pain thresholds for human skin, we derive a pinching safety constraint that limits the

  8. Low-temperature thermionics in space nuclear power systems with the safe-type fast reactor

    International Nuclear Information System (INIS)

    Zrodnikov, A.V.; Yarygin, V.I.; Lazarenko, G.E.; Zabudko, A.N.; Ovcharenko, M.K.; Pyshko, A.P.; Mironov, V.S.; Kuznetsov, R.V.

    2007-01-01

    The potentialities of the use of the low-temperature thermionic converters (TIC) with the emitter temperature ≤ 1500 K in the space nuclear power system (SNPS) with the SAFE-type (Safe Affordable Fission Engine) fast reactor proposed and developed by common efforts of American experts have been considered. The main directions of the 'SAFE-300-TEG' SNPS (300 kW(thermal)) design update by replacing the thermoelectric converters with the low-temperature high-performance thermionic converters (with the barrier index V B ≤ 1.9 eV and efficiency ≥ 10%) meant for a long-term operation (5 years at least) as the components of the SAFE-300-TIC SNPS for a Lunar base have been discussed. The concept of the SNPS with the SAFE-type fast reactor and low-temperature TICs with specific electric power of about 1.45 W/cm 2 as the components of the SAFE-300-TIC system meeting the Nasa's initial requirements to a Lunar base with the electric power demand of about 30 kW(electrical) for robotic mission has been considered. The results, involving optimization and mass-and-size estimation, show that the SAFE-300-TIC system meets the initial requirements by Nasa to the lunar base power supply. The main directions of the system update aimed at the output electric power increase up to 100 kW(electrical) have also been presented. (authors)

  9. Preliminary Results of the Determination of Inlet-Pressure Distortion Effects on Compressor Stall and Altitude Operating Limits of the J57-P-1 Turbojet Engine

    Science.gov (United States)

    Wallner, L. E.; Lubick, R. J.; Chelko, L. J.

    1955-01-01

    During an investigation of the J57-P-1 turbojet engine in the Lewis altitude wind tunnel, effects of inlet-flow distortion on engine stall characteristics and operating limits were determined. In addition to a uniform inlet-flow profile, the inlet-pressure distortions imposed included two radial, two circumferential, and one combined radial-circumferential profile. Data were obtained over a range of compressor speeds at an altitude of 50,000 and a flight Mach number of 0.8; in addition, the high- and low-speed engine operating limits were investigated up to the maximum operable altitude. The effect of changing the compressor bleed position on the stall and operating limits was determined for one of the inlet distortions. The circumferential distortions lowered the compressor stall pressure ratios; this resulted in less fuel-flow margin between steady-state operation and compressor stall. Consequently, the altitude operating Limits with circumferential distortions were reduced compared with the uniform inlet profile. Radial inlet-pressure distortions increased the pressure ratio required for compressor stall over that obtained with uniform inlet flow; this resulted in higher altitude operating limits. Likewise, the stall-limit fuel flows required with the radial inlet-pressure distortions were considerably higher than those obtained with the uniform inlet-pressure profile. A combined radial-circumferential inlet distortion had effects on the engine similar to the circumferential distortion. Bleeding air between the two compressors eliminated the low-speed stall limit and thus permitted higher altitude operation than was possible without compressor bleed.

  10. Integrated approach to economical, reliable, safe nuclear power production

    International Nuclear Information System (INIS)

    1982-06-01

    An Integrated Approach to Economical, Reliable, Safe Nuclear Power Production is the latest evolution of a concept which originated with the Defense-in-Depth philosophy of the nuclear industry. As Defense-in-Depth provided a framework for viewing physical barriers and equipment redundancy, the Integrated Approach gives a framework for viewing nuclear power production in terms of functions and institutions. In the Integrated Approach, four plant Goals are defined (Normal Operation, Core and Plant Protection, Containment Integrity and Emergency Preparedness) with the attendant Functional and Institutional Classifications that support them. The Integrated Approach provides a systematic perspective that combines the economic objective of reliable power production with the safety objective of consistent, controlled plant operation

  11. New Developments in FPGA Devices: SEUs and Fail-Safe Strategies from the NASA Goddard Perspective

    Science.gov (United States)

    Berg, Melanie; LaBel, Kenneth; Pellish, Jonathan

    2016-01-01

    It has been shown that, when exposed to radiation environments, each Field Programmable Gate Array (FPGA) device has unique error signatures. Subsequently, fail-safe and mitigation strategies will differ per FPGA type. In this session several design approaches for safe systems will be presented. It will also explore the benefits and limitations of several mitigation techniques. The intention of the presentation is to provide information regarding FPGA types, their susceptibilities, and proven fail-safe strategies; so that users can select appropriate mitigation and perform the required trade for system insertion. The presentation will describe three types of FPGA devices and their susceptibilities in radiation environments.

  12. Method of operating a nuclear reactor

    International Nuclear Information System (INIS)

    Spurgin, A.J.; Schaefer, W.F.

    1978-01-01

    A method of controlling a nuclear power generting station in the event of a malfunction of particular operating components is described. Upon identification of a malfunction, preselected groups of control rods are fully inserted sequentially until a predetermined power level is approached. Additional control rods are then selectively inserted to quickly bring the reactor to a second given power level to be compatible with safe operation of the system with the malfunctioning component. At the time the thermal power output of the reactor is being reduced, the turbine is operated at a rate consistent with the output of the reactor. In the event of a malfunction, the power generating system is operated in a turbine following reactor mode, with the reactor power rapidly reduced, in a controlled manner, to a safe level compatible with the type of malfunction experienced

  13. Hanaro operation

    International Nuclear Information System (INIS)

    Lee, Ji Bok; Jeon, Byung Jin; Kwack, Byung Ho

    1997-01-01

    HANARO was configurated its first operating core in 1995. Long term operation test was conducted up to 3-1 cycle during 1996, in order to investigate the reactor characteristics due to fuel depletion and additional fuel loading. Now HANARO has accumulated 168.4 days of total operation time and 2,687.5 MWD of total thermal output. Reactor analysis, producing operation datum and its validation with test, periodic inspection and maintenance of the facility are continuously conducted for safe operation of the HANARO. Conducted the verification tests for installed utilization facilities, and successfully performed the radiation emergency drill. The shutdown report of TRIGA Mark II and III was submitted to MOST, and decommissioning will be started from 1997. (author). 70 tabs., 50 figs., 27 refs

  14. Modern Project: monitoring developments for safe repository operation and staged closure

    International Nuclear Information System (INIS)

    Mayer, S.; Ouchhi, S.; Verstricht, J.; Maurer, H.; Breen, B.

    2010-01-01

    Document available in extended abstract form only. In a first part, the overall objectives of the MoDeRn project (Monitoring Developments for safe Repository operation and stage closure project) are presented. MoDeRn is a four year (2009-2013) collaborative project co-funded under the 7. Framework Program for Nuclear Research and Training (EURATOM). It involves 17 organizations responsible for research into radioactive waste management in the European Union, United States, Japan and Switzerland, with partners with extensive experience in monitoring activities in underground research laboratories (URL); as well as research institutes and universities with substantial experience in research on socio-technical interactions and public and stakeholder engagement. An overview of the project work packages and of their interdependencies is given. The successful implementation of a repository program for radioactive waste relies on both the technical aspects of a sound safety strategy and scientific and engineering excellence as well as on social aspects such as stakeholder acceptance and confidence. Monitoring is considered key in serving both technical and social objectives. It is not only essential to underpin the technical safety strategy and quality of the engineering, but it can also be an important tool for public communication, contributing to public understanding of and confidence in the repository behaviour. By inclusion of specific national contexts of waste management programs in different countries, the MoDeRn project aims at providing a reference framework for development and implementation of monitoring activities. This will be achieved by stakeholder engagement during all identifiable phases of the radioactive waste disposal process. Thus, site characterisation, construction, operation and staged closure, as well as post-closure institutional control phases have to be addressed. MoDeRn considers different host rock types, such as salt, tuff, crystalline rock

  15. The safe home project.

    Science.gov (United States)

    Arphorn, Sara; Jiraniratisai, Sopaphan; Rungtakul, Rungsri; Phutta, Nikom

    2011-12-01

    The Thai Health Promotion Foundation supported the Improvement of Quality of Life of Informal Workers project in Ban Luang District, Amphur Photaram, Ratchaburi Province. There were many informal workers in Ban Luang District. Sweet-crispy fish producers in Ban Luang were the largest group among the sweet-crispy fish producers in Thailand. This project was aimed at improving living and working conditions of informal workers, with a focus on the sweet-crispy fish group. Good practices of improved living and working conditions were used to help informal workers build safe, healthy and productive work environments. These informal workers often worked in substandard conditions and were exposed to various hazards in the working area. These hazards included risk of exposure to hot work environment, ergonomics-related injuries, chemical hazards, electrical hazards etc. Ergonomics problems were commonly in the sweet-crispy fish group. Unnatural postures such as prolonged sitting were performed dominantly. One hundred and fifty informal workers participated in this project. Occupational health volunteers were selected to encourage occupational health and safety in four groups of informal workers in 2009. The occupational health volunteers trained in 2008 were farmers, beauty salon workers and doll makers. The occupational health and safety knowledge is extended to a new informal worker group: sweet-crispy fish producer, in 2009. The occupational health and safety training for sweet-crispy fish group is conducted by occupational health volunteers. The occupational health volunteers increased their skills and knowledge assist in to make safe home and safe community through participatory oriented training. The improvement of living and working condition is conducted by using a modified WISH, Work Improvement for Safe Home, checklist. The plans of improvement were recorded. The informal workers showed improvement mostly on material handling and storage. The safe uses and safe

  16. An EPRI methodology for determining and monitoring simulator operating limits

    International Nuclear Information System (INIS)

    Eichelberg, R.; Pellechi, M.; Wolf, B.; Colley, R.

    1989-01-01

    Of paramount concern to nuclear utilities today is whether their plant-referenced simulator(s) comply with ANSI/ANS 3.5-1985. Of special interest is Section 4.3 of the Standard which requires, in part, that a means be provided to alert the instructor when certain parameters approach values indicative of events beyond the implemented model or known plant behavior. EPRI established Research Project 2054-2 to develop a comprehensive plan for determining, monitoring, and implementing simulator operating limits. As part of the project, a survey was conducted to identify the current/anticipated approach each of the sampled utilities was using to meet the requirements of Section 4.3. A preliminary methodology was drafted and host utilities interviewed. The interview process led to redefining the methodology. This paper covers the objectives of the EPRI project, survey responses, overview of the methodology, resource requirements and conclusions

  17. Il sistema EGNOS a supporto della navigazione sicura nei porti: il progetto SafePort

    Directory of Open Access Journals (Sweden)

    Antonio Casoria

    2012-09-01

    Full Text Available Il progetto SafePort, sviluppato all’interno del 7° Programma Quadro promosso dalla Unione Europea con la supervisione di European GNSS Agency (GSA che segue tutti i programmi applicativi inerenti ai sistemi GNSS europei, Galileo ed EGNOS, ha l’obbiettivo di migliorare la capacità recettiva dei porti europei, aumentando al contempo la sicurezza delle operazioni di navigazione, di attracco e di ormeggio. The EGNOS system to support safe navigation in ports: the project SafePORT SafePORT The project, developed within the 7 th Framework Programme  sponsored  by  European  Union  under  the  super-vision of European GNSS Agency (GSA, which follows all ap-plications relating to the European GNSS systems, Galileo and EGNOS, has the aim to improve receptive capacity of Europe-an ports, while increasing the safety of operations, navigation, docking and mooring.

  18. Safe transport of radioactive material. Second edition

    International Nuclear Information System (INIS)

    1991-01-01

    The transport of radioactive material embraces the carriage of radioisotopes for industrial, medical and research uses, and the movement of waste, in addition to consignments of nuclear fuel cycle material. It has been estimated that between eighteen and thirty-eight million package shipments take place each year. On the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM), which enjoys wide representations from the Agency's Member States and international organizations, the Secretariat is preparing a training kit comprising this training manual and complementary visual aids. The kit is intended to be the basis for an extensive course on the subject and can be used in whole or in part for inter-regional, regional and even national training purposes. Member States can thus benefit from the material either through training courses sponsored by the Agency, or, alternatively, organized by themselves. As a step towards achieving that goal, the current training manual was compiled using material from the first Inter-Regional Training Course on the Safe Transport of Radioactive material that was held in co-operation with the Nuclear Power Training Centre of the then Central Electricity Generating Board at Bristol, United Kingdom. This Manual was initially published in 1990. On the recommendation of the Agency's Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM), the Manual has since been expanded and updated in time for the second Inter-Regional Training Course, that will in 1991 similarly be held in Bristol. Refs, figs, tabs

  19. The Bivalve Production Chain in Santa Catarina, Brazil, and its Management and Operational Limitations

    OpenAIRE

    Gallon, Alessandra Vasconcelos; Universidade Federal do Ceará (UFC); Nascimento, Cristiano; Universidade Federal do Paraná - UFPR; Pfitscher, Elisete Dahmer; Universidade Federal de Santa Catarina

    2011-01-01

    Bivalve farming (mussels and oysters), a major component in the socio-economic development of the state of Santa Catarina, Brazil, combines the activities of public and private agencies in fish farming. Current analysis deals with the management and the operational limitations of the local bivalve production chain. Current exploratory research, undertaken by direct observations and the literature on the subject, employs data quality. Results show that the bivalve production chain, comprising ...

  20. Ergonomic design for operator flexibility

    International Nuclear Information System (INIS)

    Pope, R.H.

    1980-01-01

    The Three Mile Island accident highlighted the importance of ergonomic design of control rooms. Emphasis has been on a reappraisal of the reactor/operator interface, but in the United Kingdom the CEGB maintains that safe efficient operation needs a centralised information system optimised for all control room staff. (author)