WorldWideScience

Sample records for proposed power upgrade

  1. Proposed power upgrade of the hot fuel examination facility's neutron radiography reactor

    International Nuclear Information System (INIS)

    Pruett, D.P.; Richards, W.J.; Heidel, C.C.

    1984-01-01

    The Hot Fuel Examination Facility, HFEF, is one of several facilities located at the Argonne Site. HFEF comprises a large hot cell where both non-destructive and destructive examination of highly-irradiated reactor fuels are conducted in support of the LMFBR program. One of the non-destructive examination techniques utilized at HFEF is neutron radiography. When the NRAD facility was designed and constructed, an operating power level of 250 kw was considered to be adequate for obtaining radiographs of the type of specimens envisaged at that time. Since that time, several things have occurred that have tended to increase radiography exposure times to as much as 90 minutes each. In order to decrease exposure times, the reactor power level is to be increased from 250 kW to 1 MW. This increase in power will necessitate several engineering and design changes. The proposed upgrade of the NRAD facility will increase the neutron flux available in the beam tubes appreciably. The increased flux will enable NRAD to continue to meet its operational commitments in a timely manner and to develop state-of-the-art techniques in the future as it has in the past

  2. Proposal to upgrade the MIPP experiment

    Energy Technology Data Exchange (ETDEWEB)

    Isenhower, D.; Sadler, M.; Towell, R.; Watson, S. [Abilene Christian Univ., TX (United States); Peterson, R. J. [Univ. of Colorado, Boulder, CO (United States); Baker, W.; Carey, D.; Christian, D.; Demarteau, M.; Jensen, D.; Johnstone, C.; Meyer, H.; Raja, R.; Ronzhin, A.; Solomey, N.; Wester, W. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Gutbrod, H.; Peters, K. [GSI-Darmstadt (Germany); Feldman, G. [Harvard Univ., Cambridge, MA (United States); Torun, Y. [Illinois Inst. of Technology, Chicago, IL (United States); Messier, M. D.; Paley, J. [Indiana Univ., Bloomington, IN (United States)

    2006-09-01

    The upgraded MIPP physics results are needed for the support of NuMI projects, atmospheric cosmic ray and neutrino programs worldwide and will permit a systematic study of non-perturbative QCD interactions. The MIPP TPC is the largest contributor to the MIPP event size by far. Its readout system and electronics were designed in the 1990's and limit it to a readout rate of 60 Hz in simple events and {approx} 20 Hz in complicated events. With the readout chips designed for the ALICE collaboration at the LHC, we propose a low cost scheme of upgrading the MIPP data acquisition speed to 3000 Hz. This will also enable us to measure the medium energy numi target to be used for the NOvA/MINERvA experiments. We outline the capabilities of the upgraded MIPP detector to obtain high statistics particle production data on a number of nuclei that will help towards the understanding and simulation of hadronic showers in matter. Measurements of nitrogen cross sections will permit a better understanding of cosmic ray shower systematics in the atmosphere. In addition, we explore the possibilities of providing tagged neutral beams using the MIPP spectrometer that may be crucial for validating the Particle Flow Algorithm proposed for calorimeters for the International Linear Collider detectors. Lastly, we outline the physics potential of such a detector in understanding non-perturbative QCD processes.

  3. High Flux Isotope Reactor power upgrade status

    International Nuclear Information System (INIS)

    Rothrock, R.B.; Hale, R.E.; Cheverton, R.D.

    1997-01-01

    A return to 100-MW operation is being planned for the High Flux Isotope Reactor (HFIR). Recent improvements in fuel element manufacturing procedures and inspection equipment will be exploited to reduce hot spot and hot streak factors sufficiently to permit the power upgrade without an increase in primary coolant pressure. Fresh fuel elements already fabricated for future use are being evaluated individually for power upgrade potential based on their measured coolant channel dimensions

  4. Pulsed power supply for Nova Upgrade

    International Nuclear Information System (INIS)

    Bacon, J.L.; Kajs, J.P.; Walls, A.; Weldon, W.F.; Zowarka, R.C.

    1992-01-01

    This report describes work carried out at the Center for Electromechanics at The University of Texas at Austin (CEM-UT). A baseline design of the Nova Upgrade has been completed by Lawrence Livermore National Laboratory. The Nova Upgrade is an 18 beamline Nd: glass laser design utilizing fully relayed 4x4 30 cm aperture segmented optical components. The laser thus consists of 288 independent beamlets nominally producing 1.5 to 2.0 MJ of 0.35 μm light in a 3 to 5 ns pulse. The laser design is extremely flexible and will allow a wide range of pulses to irradiate ICF targets. This facility will demonstrate ignition/gain and the scientific feasibility of ICF for energy and defense applications. The pulsed power requirements for the Nova Upgrade are given. CEM-UT was contracted to study and develop a design for a homopolar generator/inductor (HPG/inductor) opening switch system which would satisfy the pulsed power supply requirements of the Nova Upgrade. The Nd:glass laser amplifiers used in the Nova Upgrade will be powered by light from xenon flashlamps. The pulsed power supply for the Nova Upgrade powers the xenon flashlamps. This design and study was for a power supply to drive flashlamps

  5. Review of current and proposed reactor upgrades

    International Nuclear Information System (INIS)

    Moon, R.M.

    1985-01-01

    In an effort to foresee the future health of neutron scattering, a survey of plans to upgrade reactors and associated experimental facilities was undertaken. The results indicate that we are now entering a period characterized by a substantial reinvestment in reactor sources and expansion in the number of neutron scattering instruments. For the group of institutions participating in this survey there will be a total investment in improved sources and experimental facilities of $500 M to $1,000 M over the next decade. This investment will result in a 30 to 40% increase in the total power of research reactors and an increase of 30 to 50% in the number of neutron scattering instruments. It is therefore reasonable to anticipate an approximate doubling in the number of reactor neutrons incident on samples in the mid 90s compared to the present

  6. ALICE upgrades its powerful eyes

    CERN Multimedia

    Yuri Kharlov, ALICE Collaboration

    2013-01-01

    The ALICE Photon Spectrometer (PHOS) is a high-resolution photon detector that measures the photons coming out of the extremely hot plasma created in the lead-lead collisions at the LHC. Taking advantage of the long accelerator shut-down, the ALICE teams are now repairing and upgrading the existing modules and getting ready to install the brand-new module in time for the next run. The upgraded PHOS detector will be faster and more stable with wider acceptance and improved photon identification.   PHOS crystal matrix during repair. The key feature and the main complexity of the ALICE PHOS detector is that it operates at a temperature of -25°C, which makes it the second-coldest equipment element at the LHC after the cryogenic superconducting magnets. Since 2009 when it was installed, the PHOS detector, with its cold and warm volumes, has been immersed in airtight boxes to avoid condensation in the cold volumes. The 10,752 lead tungstate crystals of the PHOS were completely insulated fr...

  7. UPGRADES

    CERN Multimedia

    J. Spalding and D. Contardo

    2012-01-01

      The CMS Upgrade Programme consists of four classes of projects: (a) Detector and Systems upgrades which are ongoing and largely (though not entirely) target LS1. (b) Full system upgrades for three projects that are preparing TDRs: Pixels, HCAL and L1 Trigger. The projects target completion by LS2. (c) Infrastructure consolidation and upgrades to improve operational robustness and to support the above projects. (d) Phase 2 replacement of the Tracker and major upgrades of the Trigger and Forward Detectors. For (a) and (c), detailed costing exists and is being integrated into a common reporting system. The schedule milestones for each project will be linked into the overall schedule planning for LS1. For the three TDR projects, the designs have progressed significantly since the Technical Proposal in 2010. Updated detailed cost estimates and schedules will be prepared with the TDRs to form the basis for tracking the projects through completion. To plan the upgrades and the supporting simulati...

  8. Constitutional determinants of nuclear power plant upgrading

    International Nuclear Information System (INIS)

    Mann, Thomas

    2013-01-01

    Around half a year ago the European stress test for nuclear power plants, a precautionary measure initiated by the European Council in March 2011 in response to the Fukushima disaster, revealed that while German nuclear power plants show a high degree of robustness compared with those in other European countries, they nevertheless required upgrading in one or the other respect (earthquake warning systems, protection against crashing civil passenger airplanes). The present article investigates whether this upgrading requirement can justify an injunction to carry out structural retrofitting measures or whether obligations to this end can be excluded on grounds of reasonability in view of the recent decision taken by the German parliament to phase out nuclear energy.

  9. Bohunice Nuclear Power Plant Safety Upgrading Program

    International Nuclear Information System (INIS)

    Toth, A.; Fagula, L.

    1996-01-01

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

  10. Upgrading the TFTR Transrex Power Supplies

    International Nuclear Information System (INIS)

    Lawson, J.E.; Marsala, R; Ramakrishnan, S.; Zhao, X.; Sichta, P.

    2009-01-01

    In order to provide improved and expanded experimental capabilities, the existing Transrex power supplies at PPPL are to be upgraded and modernized. Each of the 39 power supplies consists of two six pulse silicon controlled rectifier sections forming a twelve pulse power supply. The first modification is to split each supply into two independent six pulse supplies by replacing the existing obsolete twelve pulse firing generator with two commercially available six pulse firing generators. The second change replaces the existing control link with a faster system, with greater capacity, which will allow for independent control of all 78 power supply sections. The third change replaces the existing Computer Automated Measurement and Control (CAMAC) based fault detector with an Experimental Physics and Industrial Control System (EPICS) compatible unit, eliminating the obsolete CAMAC modules. Finally the remaining relay logic and interfaces to the 'Hardwired Control System' will be replaces with a Programmable Logic Controller (PLC)

  11. Upgrade of the Nuclotron power supply

    International Nuclear Information System (INIS)

    Karpinskij, V.N.; Kondrat'ev, N.G.; Osipenkov, A.L.

    2010-01-01

    One of topics of the Nuclotron development is the modification of its power supply scheme and upgrade of the energy evacuation system aimed to provide long and safe operation of the Nuclotron at the dipole magnetic field up to 2 T. It is necessary for the Nuclotron operation as a part of injection chain of the heavy ion collider under design at JINR as well as for fulfillment of its current scientific program. In the report the structure and peculiarity of the existing power supply system are described. The existing system is based on separated supply of dipole magnets and quadrupole lenses. General goals of the power supply modification are described, structural and principal schemes of the power supply, control system and the schemes of the energy evacuation key are presented

  12. Proposed Fermilab upgrade main injector project

    International Nuclear Information System (INIS)

    1992-04-01

    The US Department of Energy (DOE) proposes to construct and operate a ''Fermilab Main Injector'' (FMI), a 150 GeV proton injector accelerator, at the Fermi National Accelerator Laboratory (Fermilab) in Batavia, Illinois. The purpose and need for this action are given of this Environmental Assessment (EA). A description of the proposed FMI and construction activities are also given. The proposed FMI would be housed in an underground tunnel with a circumference of approximately 2.1 miles (3.4 kilometers), and the construction would affect approximately 135 acres of the 6,800 acre Fermilab site. The purpose of the proposed FMI is to construct and bring into operation a new 150 GeV proton injector accelerator. This addition to Fermilab's Tevatron would enable scientists to penetrate ever more deeply into the subatomic world through the detection of the super massive particles that can be created when a proton and antiproton collide head-on. The conversion of energy into matter in these collisions makes it possible to create particles that existed only an instant after the beginning of time. The proposed FMI would significantly extend the scientific reach of the Tevatron, the world's first superconducting accelerator and highest energy proton-antiproton collider

  13. Shielding assessment of the ETRR-1 Reactor Under power upgrading

    Energy Technology Data Exchange (ETDEWEB)

    Ahmad, E E [Reactor Department, Nuclear Research Center, Atomic Energy Authority, Cairo (Egypt)

    1997-12-31

    The assessment of existing shielding of the ETRR-1 reactor in case of power upgrading is presented and discussed. It was carried out using both the present EK-10 type fuel elements and some other types of fuel elements with different enrichments. The shielding requirements for the ETRR-1 when power is upgraded are also discussed. The optimization curves between the upgraded reactor power and the shield thickness are presented. The calculation have been made using the ANISN code with the DLC-75 data library. The results showed that the present shield necessitates an additional layer of steel with thickness of 10.20 and 25 cm. When its power is upgraded to 3, 6 and 10 MWt in order to cutoff all neutron energy groups to be adequately safe under normal operating conditions. 4 figs.

  14. Feasibility study for Tehran Research Reactor power upgrading

    Energy Technology Data Exchange (ETDEWEB)

    Farhadi, Kazem [Nuclear Research Center, Atomic Energy Organization of Iran (AEOI), Tehran (Iran, Islamic Republic of)], E-mail: kfarhadi@aeoi.org.ir; Khakshournia, Samad [Nuclear Research Center, Atomic Energy Organization of Iran (AEOI), Tehran (Iran, Islamic Republic of)

    2008-07-15

    The present work is concerned with a power upgrading study of Tehran Research Reactor (TRR). The upgrading study is aimed at investigating the possibility of raising power of the TRR from the current level of 5 MW{sub th} to a higher level without violating the original thermal-hydraulic safety criteria. The existing core, comprising 22 standard fuel elements and five control fuel elements, is used for the analyses. Different reactor thermal powers (5-11 MW) and different core coolant flow rates (500-921 m{sup 3}/h) are considered. It is shown that, for the present core, this goal could be achieved safely by gradually opening the butterfly control valve until the desired coolant flow rate is reached. The TRR power could be upgraded up to around 7.5 MW{sub th} with the total power peaking factor maintained at less than or equal to 3.0.

  15. Feasibility study for Tehran Research Reactor power upgrading

    International Nuclear Information System (INIS)

    Farhadi, Kazem; Khakshournia, Samad

    2008-01-01

    The present work is concerned with a power upgrading study of Tehran Research Reactor (TRR). The upgrading study is aimed at investigating the possibility of raising power of the TRR from the current level of 5 MW th to a higher level without violating the original thermal-hydraulic safety criteria. The existing core, comprising 22 standard fuel elements and five control fuel elements, is used for the analyses. Different reactor thermal powers (5-11 MW) and different core coolant flow rates (500-921 m 3 /h) are considered. It is shown that, for the present core, this goal could be achieved safely by gradually opening the butterfly control valve until the desired coolant flow rate is reached. The TRR power could be upgraded up to around 7.5 MW th with the total power peaking factor maintained at less than or equal to 3.0

  16. Upgrading Atucha 1 nuclear power plant. Regulatory perspective

    International Nuclear Information System (INIS)

    Caruso, G.

    1998-01-01

    Atucha 1 nuclear power plant has unique design and its commercial operation started in 1974. The upgrading decisions, the basis for an upgrading program and its status of implementation are presented. Regulatory decisions derived from the performance-based approach have the advantage that they enable balancing of the overall plant risk and identifying at different plant levels the areas where improvements are necessary. (author)

  17. Safety upgrading at PAKS Nuclear Power Plant

    International Nuclear Information System (INIS)

    Bajsz, J.; Elter, J.

    2000-01-01

    The operation of Paks NPP has reached its half time. Until this time the plant fulfilled expectations raised before its construction: the four units have produced safely and reliably more than 200 TWh electricity. The production of the plant has been at the stable level since its construction and has provided 43-38 % of electricity consumed in Hungary. The annual production is around 14 TWh, which means a load factor higher than 85 %. Safety upgrading activities [1] at Paks had started in the late eighties, when the commissioning work of units 3 and 4 were carried out. That time the main emphases were put to lessons learned of the TMI and Chernobyl accidents. The international reviews hosted by our plant widened our review's scope. To systematize our approach a complete safety review, the AGNES (Advanced General Safety and New Evaluation of Safety) project was started in 1991. The goal of the project was to evaluate to what extent Paks NPP satisfied the current international safety expectations and to help in determining the priorities for safety enhancement and upgrading measures. The project completed in 1994 ranked our safety upgrading measures by safety significance, which became a basis for technical design work and financial scheduling. The other important outcome of the AGNES project was the introduction the Periodical Safety Review regime by our nuclear authority. These periodical reviews held after 10 years of operation offer the possibility - and obligation for the licensee - to perform a comprehensive assessment of the safety of the plant, to evaluate the integral effects of changes of circumstances happened during the review period. The goal of these reviews is to deal with cumulative effects of NPP ageing, modifications, operating experience and technical developments aimed at ensuring a high level of safety throughout plant service life. The execution of our safety-upgrading program is well advancing. For the whole program from 1996 to 2002 250

  18. Dipole power supply for National Synchrotron Light Source Booster upgrade

    International Nuclear Information System (INIS)

    Olsen, R.; Dabrowski, J.; Murray, J.

    1992-01-01

    The booster at the NSLS is being upgraded from .75 to 2 pulses per second. To accomplish this, new power supplies for the dipole, quadrupole, and sextupole magnets have been designed and are being constructed. This paper will outline the design of the dipole power supply and control system, and will present results obtained thus far

  19. Digital signal array processor for NSLS booster power supply upgrade

    International Nuclear Information System (INIS)

    Olsen, R.; Dabrowski, J.; Murray, J.

    1993-01-01

    The booster at the NSLS is being upgraded from 0.75 to 2 pulses per second. To accomplish this, new power supplied for the dipole, quadrupole, and sextupole have been installed. This paper will outline the design and function of the digital signal processor used as the primary control element in the power supply control system

  20. Final Technical Report. Upgrades to Alabama Power Company Hydroelectric Developments

    Energy Technology Data Exchange (ETDEWEB)

    Crew, James F. [Southern Company Generation, Birmingham, AL (United States). Hydro Services; Johnson, Herbie N. [Southern Company Generation, Birmingham, AL (United States). Hydro Services

    2015-03-31

    From 2010 to 2014, Alabama Power Company (“Alabama Power”) performed upgrades on four units at three of the hydropower developments it operates in east-central Alabama under licenses issued by the Federal Energy Regulatory Commission (“FERC”). These three hydropower developments are located on the Coosa River in Coosa, Chilton, and Elmore counties in east-central Alabama.

  1. Upgrading of fire safety in Indian nuclear power plants

    International Nuclear Information System (INIS)

    Agarwal, N.K.

    1998-01-01

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

  2. Nuclear power plant security systems - The need for upgrades

    International Nuclear Information System (INIS)

    Murskyj, M.P.; Furlow, C.H.

    1989-01-01

    Most perimeter security systems for nuclear power plants were designed and installed in the late 1970s or early 1980s. This paper explores the need to regularly evaluate and possibly upgrade a security system in the area of perimeter intrusion detection and surveillance. this paper discusses US Nuclear Regulatory Commission audits and regulatory effectiveness reviews (RERs), which have raised issues regarding the performance of perimeter security systems. The audits and RERs identified various degrees of vulnerability in certain aspects of existing perimeter security systems. In addition to reviewing the regulatory concerns, this paper discusses other reasons to evaluate and/or upgrade a perimeter security system

  3. The AGS main magnet power supply upgrade

    International Nuclear Information System (INIS)

    Sandberg, J.N.; Casella, R.; Geller, J.; Marneris, I.; Soukas, A.; Schumburg, N.

    1995-01-01

    The AGS Main Magnet Power Supply consists of a group of thyristor controlled power converters that operate from full rectify to full invert. In order to minimize ripple during the critical periods of injection and extraction 24 pulse converters are used for these portions of the cycle. The maximum voltage available in this mode is nominally 2,000 volts. The converters that are functional during this portion of the cycle are called the flat-top bank or ''F'' bank modules. During acceleration and invert where voltages of up to 12,000 volts are needed and where the ripple requirements are less stringent, groups of twelve pulse converters are operational. These converters are called the Pulsed bank or ''P'' bank modules. The original controlled rectifier system consisted of 96 large mercury filled excitron tubes divided equally between the P bank and F bank converters. These devices were extremely durable and ran successfully for over twenty years. It was, decided to replace the excitron farm with multiple arrangements of three-phase, full-wave, bridge modules that utilize silicon controlled rectifiers (SCR's or thyristors) as the switching element. In order to match the existing transformer connections and buswork, eight identical modules were required; four for the P bank system and four for the F bank system. In order to reduce noise pickup and provide electrical isolation the high level SCR gate triggers are provided via fiberoptic cable. The status of various parameters such as water flow, auxiliary power supply performance, trigger circuitry failure, over voltage, overcurrent, and loss of phase reference are monitored via a programmable logic controller (PLCs). The PLCs use isolated input and output modules for various voltage levels from TTL to 150 Vdc to 125 Vac. These devices are extremely flexible and have allowed modifications and improvements that have enhanced the performance over any equivalent hard wired system

  4. 76 FR 23795 - Low-Power Television and Translator Upgrade Program: Notice of Final Closing Date

    Science.gov (United States)

    2011-04-28

    .... 110418247-1247-01] Low-Power Television and Translator Upgrade Program: Notice of Final Closing Date AGENCY... receipt of applications for the Low-Power Television and Translator Upgrade Program (Upgrade Program) will... Rules to Establish Rules for Digital Low Power Television, Television Translator, and Television Booster...

  5. UPGRADES

    CERN Multimedia

    J. Butler and J. Nash

    2011-01-01

    Recent progress on the CMS upgrades was summarised, in a workshop held at Fermilab between 7th and 10th November, attended by more than 150 people, many of whom came from Europe and Asia. Important goals of the workshop were to begin to formulate a schedule for the upgrades and to determine project interdependencies. Input was received from all the upgrade working groups and will be combined into a first-pass schedule over the next several weeks. In addition, technical progress on each of the major subtasks was presented and plans for the near-term future were established. Slides from the more than 100 talks are located at: https://indico.cern.ch/conferenceDisplay.py?confId=153564 In the opening plenary session, Frank Zimmermann, of the CERN Beams Department, gave his view of the LHC luminosity evolution. The luminosity will increase faster than we assumed in designing the upgrades. CMS will need to re-evaluate the current upgrade plans and revise them if necessary. CMS Upgrade Physics coordinator...

  6. I and C upgrading at nuclear power plants

    International Nuclear Information System (INIS)

    Tamiri, A.

    2003-01-01

    Continuing the operation of existing nuclear power plants will help reduce the number of new base-load nuclear and fossil power plants that need to be built. Old nuclear power plants in Canada are operating with analog instrumentation and control systems. For a number of reasons, such as changes and improvements in the applicable standards and design, maintenance problems due to the lack of spares, technical obsolescence, the need to increase power production, availability, reliability and safety, and in order to reduce operation and maintenance costs, instrumentation and control upgrading at nuclear power plants in a cost effective manner should be considered the greatest priority. Failures of instrumentation and control (I and C) due to aging and obsolescence issues may have an immediate negative impact on plant reliability and availability and also affect long-term plant performance and safety. In today's competitive marketplace, power plants are under pressure to cut spending on maintenance while reducing the risk of equipment failure that could cause unplanned outage. To improve plant safety and availability, old nuclear power plants will require investment in new technologies that can improve the performance and reduce the costs of generation by addressing the long term reliability of systems by up-grading to modem digital instrumentation and control and optimization opportunities. Boiler drum level control at nuclear power plants is critical for both plant protection and equipment safety and applies equality to high and low levels of water within the boiler drum. Plant outage studies at Pickering Nuclear have identified boiler drum level control and feed water control systems as major contributors to plant unavailability. Ways to improve transient and steady state response, upgrading existing poor analog control systems for boiler level and feed-water control systems at Pickering Nuclear, with enhanced and robust controller will be discussed in this paper

  7. Upgrading of seismic design of nuclear power plant building

    Energy Technology Data Exchange (ETDEWEB)

    Akiyama, Hiroshi [Tokyo Univ. (Japan). Faculty of Engineering; Kitada, Yoshio

    1997-03-01

    In Japan seismic design methodology of nuclear power plant (NPP) structures has been established as introduced in the previous session. And yet efforts have been continued to date to upgrade the methodology, because of conservative nature given to the methodology in regard to unknown phenomena and technically-limited modeling involved in design analyses. The conservative nature tends to produce excessive safety margins, and inevitably send NPP construction cost up. Moreover, excessive seismic design can increase the burden on normal plant operation, though not necessarily contributing to overall plant safety. Therefore, seismic engineering has put to many tests and simulation analyses in hopes to rationalize seismic design and enhance reliability of seismic safety of NPPs. In this paper, we describe some studies on structural seismic design of NPP underway as part of Japan`s effort to upgrade existing seismic design methodology. Most studies described here are carried out by NUPEC (Nuclear Power Engineering Company) funded by MITI (the Ministry of International Trade and Industry Japan), though, similar studies with the same motive are also carrying out by nuclear industries such as utilities, NPP equipment and system manufacturers and building constructors. This paper consists of three sections, each introducing studies relating to NPP structural seismic design, new siting technology, and upgrading of the methodology of structural design analyses. (J.P.N.)

  8. Upgrading of seismic design of nuclear power plant building

    International Nuclear Information System (INIS)

    Akiyama, Hiroshi; Kitada, Yoshio.

    1997-01-01

    In Japan seismic design methodology of nuclear power plant (NPP) structures has been established as introduced in the previous session. And yet efforts have been continued to date to upgrade the methodology, because of conservative nature given to the methodology in regard to unknown phenomena and technically-limited modeling involved in design analyses. The conservative nature tends to produce excessive safety margins, and inevitably send NPP construction cost up. Moreover, excessive seismic design can increase the burden on normal plant operation, though not necessarily contributing to overall plant safety. Therefore, seismic engineering has put to many tests and simulation analyses in hopes to rationalize seismic design and enhance reliability of seismic safety of NPPs. In this paper, we describe some studies on structural seismic design of NPP underway as part of Japan's effort to upgrade existing seismic design methodology. Most studies described here are carried out by NUPEC (Nuclear Power Engineering Company) funded by MITI (the Ministry of International Trade and Industry Japan), though, similar studies with the same motive are also carrying out by nuclear industries such as utilities, NPP equipment and system manufacturers and building constructors. This paper consists of three sections, each introducing studies relating to NPP structural seismic design, new siting technology, and upgrading of the methodology of structural design analyses. (J.P.N.)

  9. UPGRADES

    CERN Document Server

    D. Contardo and J. Spalding

    2013-01-01

    There is very good progress in the execution of the LS1 projects and in launching construction of the Phase 1 upgrades. We focus here on two main achievements since the last CMS Week. The approval of the third Phase 1 TDR The preparation of the L1 Trigger Upgrade Technical Design Report has been a major effort of the collaboration at the beginning of this year, especially to develop supporting Trigger menu and physics performance studies. These studies have demonstrated the efficiency of the upgraded system to ensure low lepton and jet trigger thresholds, leading to a significant increase of the acceptance for the Higgs measurements, in the associated production mode and in the ττ decays, as well as for the stop searches involving multiple jets in the final state. The TDR was submitted to the LHCC in May and approved at the June committee meeting. It is now a public document, completing the series of the three TDRs describing the Phase 1 upgrades, with the new Pixel system and the HCAL rea...

  10. Sensitivity study of a proposed polarimetry diagnostic on ASDEX upgrade

    International Nuclear Information System (INIS)

    Callaghan, H.P.; McCarthy, P.J.

    1994-09-01

    ASDEX-Upgrade currently uses FIR interferometry (DCN, 195 μm) as a technique for measuring line integrated electron density along eight chords of the plasma cross-section. A polarimetry diagnostic based on Faraday rotation using the existing setup would yield ∫ n e B.dl along the same chords which, in combination with the ∫ n e dl measurements, would provide additional information about the poloidal magnetic field. This would be helpful for reconstructing the q(ψ) profile, which is difficult to recover from external magnetic measurements alone. A sensitivity study to determine the effectiveness of adding polarimetry to ASDEX Upgrade is carried out using function parameterization on a simulated equilibrium database, together with a database of randomly chosen density profiles with four degrees of freedom. The robustness of the recovery in the presence of measurement noise and the effects of plasma birefringence are taken into account. (orig.)

  11. Modernization and power upgrading of the Loviisa NPP

    International Nuclear Information System (INIS)

    Keskinen, A.

    1997-01-01

    In 1995, Imatran Voima Oy (IVO) started a project for modernization and power upgrading of the Loviisa NPP. The main objectives of the project are to ensure plant safety, to increase electricity production and to improve the expertise of the IVO staff. The total electricity output of Loviisa 1 and 2 units is planned to be increased by about 100 MW. This will be achieved through renovation of the steam turbines and through gradual increase in the thermal reactor power up to 1,500 MW from the present level of 1,375 MW. The Loviisa NPP Final Safety Analysis Report has been revised to a great extent in connection with the licensing process of the reactor power upgrading. The project also includes certain improvements in the primary and safety systems to ensure plant safety. The total cost estimate of the project is around 200 million FIM. The project implementation started in 1995 and in accordance with the plans in 2000 after several phases the last measures at power plant will be completed. (orig.)

  12. Modernization and power upgrading of the Loviisa NPP

    Energy Technology Data Exchange (ETDEWEB)

    Keskinen, A. [IVO Power Engineering Ltd., Vantaa (Finland)

    1997-12-31

    In 1995, Imatran Voima Oy (IVO) started a project for modernization and power upgrading of the Loviisa NPP. The main objectives of the project are to ensure plant safety, to increase electricity production and to improve the expertise of the IVO staff. The total electricity output of Loviisa 1 and 2 units is planned to be increased by about 100 MW. This will be achieved through renovation of the steam turbines and through gradual increase in the thermal reactor power up to 1,500 MW from the present level of 1,375 MW. The Loviisa NPP Final Safety Analysis Report has been revised to a great extent in connection with the licensing process of the reactor power upgrading. The project also includes certain improvements in the primary and safety systems to ensure plant safety. The total cost estimate of the project is around 200 million FIM. The project implementation started in 1995 and in accordance with the plans in 2000 after several phases the last measures at power plant will be completed. (orig.). 4 refs.

  13. Modernization and power upgrading of the Loviisa NPP

    Energy Technology Data Exchange (ETDEWEB)

    Keskinen, A [IVO Power Engineering Ltd., Vantaa (Finland)

    1998-12-31

    In 1995, Imatran Voima Oy (IVO) started a project for modernization and power upgrading of the Loviisa NPP. The main objectives of the project are to ensure plant safety, to increase electricity production and to improve the expertise of the IVO staff. The total electricity output of Loviisa 1 and 2 units is planned to be increased by about 100 MW. This will be achieved through renovation of the steam turbines and through gradual increase in the thermal reactor power up to 1,500 MW from the present level of 1,375 MW. The Loviisa NPP Final Safety Analysis Report has been revised to a great extent in connection with the licensing process of the reactor power upgrading. The project also includes certain improvements in the primary and safety systems to ensure plant safety. The total cost estimate of the project is around 200 million FIM. The project implementation started in 1995 and in accordance with the plans in 2000 after several phases the last measures at power plant will be completed. (orig.). 4 refs.

  14. Torness: proposed nuclear power station

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    The need for and desirability of nuclear power, and in particular the proposed nuclear power station at Torness in Scotland, are questioned. Questions are asked, and answered, on the following topics: position, appearance and cost of the proposed Torness plant, and whether necessary; present availability of electricity, and forecast of future needs, in Scotland; energy conservation and alternative energy sources; radiation hazards from nuclear power stations (outside, inside, and in case of an accident); transport of spent fuel from Torness to Windscale; radioactive waste management; possibility of terrorists making a bomb with radioactive fuel from a nuclear power station; cost of electricity from nuclear power; how to stop Torness. (U.K.)

  15. Upgrading the safety assessment of exported nuclear power plants

    International Nuclear Information System (INIS)

    Rosen, M.

    1978-01-01

    An examination of the safety aspects of exported nuclear power plants demonstrates that additional and somewhat special considerations exist for these plants, and thus that some new approaches may be required to insure their safety. In view of the generally small regulatory staffs of importing countries, suggestions are given for measures which should be taken by the various organizations involved in the export and import of nuclear power facilities to raise the level of the very essential safety assessment. These include the upgrading of the 'export edition' of the traditionally supplied safety documentation by use of a Supplementary Information Report, written specifically for the needs of a smaller and/or less technically qualified staff, which highlights the differences that exist between the facility to be constructed and the supposedly similar reference plant of the supplier country; by improvement of supporting safety documentation to allow for adequate understanding of significant safety parameters; and by attention to the needs of smaller countries in the critical Operating Regulations (Technical Specifications for Operation). Consideration is also given to upgrading the regulatory effort and to the obligations of principal organizations involved with exported nuclear plants, including national and international, for insuring the importing countries' technical readiness and the adequacy of the regulatory effort. Special attention is directed towards the project contract as a means of implementing programmes to achieve these goals. (author)

  16. UPGRADES

    CERN Multimedia

    D. Contardo and J. Spalding

    2012-01-01

      Good progress is being made on the projects that will be installed during LS1. CSC chamber production for ME4/2 is progressing at a rate of four chambers per month, with 25 built so far, and the new electronics for ME1/1 is undergoing a pre-production integration testing. For the RPC chambers, gap production is underway with first deliveries to the chamber assembly sites at CERN and Ghent. The third site at Mumbai will begin production next month. For the PMT replacement in the forward hadron calorimeters (HF), the 1728 PMTs are all characterised and ready to be installed. Testing of the electronics boards is going well. Preparations to replace the HPDs in the outer calorimeter (HO) with SiPMs are also on-track. All components are at CERN and burn-in of the new front-end electronics is proceeding. There are three major upgrade projects targeting the period from LS1 through LS2: a new pixel detector, upgraded photo-detectors and electronics for HCAL, and development of a new L1 Trigger. The new ...

  17. UPGRADES

    CERN Multimedia

    Didier Contardo

    2012-01-01

      The CMS Upgrade Programme is making good progress on the LS1 and Phase 1 projects, in the planning for Phase 2. The construction of the ME4/2 muon chambers to be installed during LS1 has started and the two first CSC production chambers have been fully qualified. The three muon groups have recently established a set of milestones towards the completion of their project, that will be integrated in the detailed planning and scheduling for the shutdown work established by Technical Coordination. The project to replace the photo-detectors in the HF and HO calorimeters is also well advanced and at the validation stage. The operation of an HF slice with new multi-anode PMTs and back-end electronics has already been demonstrated in 2012. For the Phase 1 data-taking, as discussed in the Chamonix workshop, it is likely that the LHC performance will exceed the nominal luminosity and pile-up before the second shutdown, still scheduled in 2018. The collaboration is therefore pursuing a strategy to upgrade ...

  18. UPGRADES

    CERN Multimedia

    D. Contardo and J. Spalding

    2013-01-01

    The three post-LS1 Phase 1 Upgrade projects (the L1-Trigger, Pixel Tracker, and HCAL) are all making excellent progress and are transitioning from the prototype to the execution phase. Meanwhile plans are developing for Phase 2, a major Upgrade programme targeting the third long shutdown, LS3. News on Phase 1 is included under the respective projects; we only provide a brief summary here. Phase 1 The plan for the L1 Trigger relies on the installation during the present shutdown of optical splitting for the Trigger input signals. This will allow the new Trigger system to be brought online and fully commissioned during beam operation in 2015, while CMS relies on the existing legacy Trigger for physics. Once fully commissioned the experiment can switch over to the new Trigger, which will provide greatly improved performance at high event pile-up, by 2016. System tests of the splitter system, and of the new architecture of the calorimeter trigger were very successful, and the work in LS1 is on-track. Prototype ...

  19. Cost evaluation of I and C upgrade approach in nuclear power plants

    International Nuclear Information System (INIS)

    Kang, Hyun-Tae; Lee, Jae-Ki

    2013-01-01

    Highlights: • Cost evaluation process for I and C system upgrade is built. • 4 cost factors affecting I and C system upgrade are described. • Additional cost incurred by a phased upgrade is calculated. • Cost for system upgrade between upgrade implementations is compared. - Abstract: Utilities have recently been debating the respective pros and cons of implementation of a multi-phase upgrade during several normal outages versus a single major upgrade implementation during a prolonged outage. We have studied these approaches and have been developing the basic design of nuclear power plants (NPPs) instrumentation and control (I and C) upgrade since early 2008. As part of this study, analyses of the NPPs I and C systems were conducted and the need for upgrading the systems was raised. One of the primary concerns regarding the system upgrade is a cost-benefit implementation, which will influence the upgrade approach. From this viewpoint, the I and C upgrade must consider economic factors such as I and C vendor cost, architecture engineering cost, installation cost, utility cost, and other transition costs such as training and procedure development. This paper presents a comparison study of economical aspects including cost evaluation between the aforementioned upgrade implementations and suggests a solution for I and C upgrade approach

  20. Power inverter design for ASDEX Upgrade saddle coils

    Energy Technology Data Exchange (ETDEWEB)

    Teschke, M., E-mail: teschke@ipp.mpg.de [Max Planck Institute for Plasma Physics, EURATOM Association, Boltzmannstr. 2, 85748 Garching (Germany); Suttrop, W.; Rott, M. [Max Planck Institute for Plasma Physics, EURATOM Association, Boltzmannstr. 2, 85748 Garching (Germany)

    2013-10-15

    Highlights: ► A cost effective inverter topology for AUG's 16 in-vessel saddle coils has been found. ► Use of commercially available power modules is possible. ► Exchange of reactive power between multiple inverters is possible. ► Influence of electromagnetic noise to AUG's diagnostics was measured. ► Gas insulation of electric feed through significantly depends on magnetic fields. It is protected by fast turn-off circuit. -- Abstract: A set of 16 in-vessel saddle coils has been installed in the ASDEX Upgrade (AUG) experiment since the end of 2011 [1]. To achieve full performance, it is necessary to operate them with alternating current (AC) of arbitrary waveforms. To generate spatially resolved magnetic fields, it is required to allocate separate power inverters to every single coil. Therefore, different topologies are analyzed and compared. Studies of the commutation behavior of power stages, different pulse width modulation (PWM) schemes and single-phase-to-earth fault detection are executed. Experiments to evaluate the electromagnetic interference (EMI) of possible inverter topologies on the AUG diagnostics are done as well. A special focus is put on the feasibility of analyzed topologies using industrially available and fully assembled “power modules” to minimize development effort and costs.

  1. Feasibility of maintaining natural convection mode core cooling in research reactor power upgrades

    International Nuclear Information System (INIS)

    Ha, J.J.; Belhadj, M.; Aldemir, T.; Christensen, R.N.

    1987-01-01

    Two operational concerns for natural convection coooled research reactors using plate type fuels are: 1) pool top 16 N activity (PTNA), and 2) nucleate boiling in core channels. The feasibility assessment of a power upgrade while maintaining natural convection mode core cooling requires addressing these operational concerns. Previous studies have shown that: a) The conventional technique for reducing PTNA by plume dispersion may not be effective in a large power upgrade of research reactors with small pools. b) Currently used correlations to predict onset of nucleate boiling (ONB) in thin, rectangular core channels are not valid for low-velocity, upward flows such as encountered in natural convection cooling. The PTNA depends on the velocity distribution in the reactor pool. COMMIX-1A code is used to determine the three-dimensional velocity fields in The Ohio State University Research Reactor (OSURR) pool as a function of varying design conditions, following a power upgrade to 500 kW with LEU fuel. It is shown that a sufficiently deep stagnant water layer can be created below the pool top by properly choosing the disperser flow rate. The ONB heat flux is experimentally determined for channel gaps and upward flow velocities in the range 2mm-4mm and 3-16 cm/sec., respectively. Two alternatives to plume dispersion for reducing PTNA and a new correlation to determine the ONB heat flux in thin, rectangular channels under low-velocity, upward flow conditions are proposed. (Author)

  2. Upgrading and efficiency improvement in coal-fired power plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-01

    Improving the efficiencies of the large number of older coal-fired power plants operating around the world would give major savings in CO2 emissions together with significant other benefits. This report begins with a summary of the ways efficiency can become degraded and of the means available to combat the decrease in performance. These include improvements to operating and maintenance practices and more major techniques that are available, including boiler and turbine retrofits. There is also an update on fuel drying developments as a route to higher efficiency in plants firing high moisture lignites. The largest chapter of the report contains a number of descriptions of case study improvement projects, to illustrate measures that have been applied, benefits that have been achieved and identify best practices, which are summarised. Major national and international upgrading programmes are described.

  3. Upgrade of maintenance technologies of Nuclear Power Plants

    International Nuclear Information System (INIS)

    Kamada, Kazuaki

    2005-01-01

    In order to enhance long-term safe and stable operation of Ikata Nuclear Power Plants (NPPs) in more efficient way, maintenance technology upgrade project was started aiming at establishment of simplified and efficient self-maintenance system with affiliated companies. Maintenance technique and supervisor qualification system was introduced after improvement and reinforcement of personnel education and training. Reflecting investigation of maintenance activities of US NPPs and productivity improvement in other industries, preventive maintenance optimization project had been performed such as introduction of key performance indicator (KPI), new system incorporating reliability-centered maintenance (RCM) and condition-based maintenance (CBM), and on-line monitoring and maintenance (OLM) based on risk assessment. Enterprise asset management (EAM) to establish information data base and total productive maintenance (TPM) action for every personnel to participate in self-maintenance was also introduced. (T. Tanaka)

  4. UPGRADES

    CERN Multimedia

    D. Contardo and J. Spalding

    2013-01-01

      LS1 and Phase 1 The detector projects targeting LS1 are progressing well, and a fully integrated schedule developed by Technical Coordination includes installation milestones and a detailed work-plan. The first chambers of the RPC system were produced and are being qualified. Production will ramp up this year to a rate of 20 chambers per month. 32 chambers of the CSC system have been fabricated for the ME4/2 CSC stations, and production proceeds at a rate of 4 per month. The new ME1/1 Front-End Board is in production and the off-detector electronics integration tests are ongoing. The new Theta Trigger Boards for the DT readout production is started and the relocation of the Sector Collector boards with new Optical Links as been successfully tested. All the components for the upgrade of the Forward Hadron Calorimeter PMTs have been received at CERN and assemblies are being qualified. The situation is similar for the Hadron Outer Calorimeter new SiPMs and readout modules. Three projects are plan...

  5. Proposed upgrade of the lower tier water moderators for the LANSE 1L MARK-III upgrade

    International Nuclear Information System (INIS)

    Muhrer, G.; Pitcher, E.J.; Russell, G.J.

    2005-01-01

    We will show in this article the proposed upgrade for the lower tier water moderators for the LANSCE 1L Mark-III design. This proposal will include the introduction of pre-moderators for the high intensity moderators and a change of the decoupler from Cadmium to Gadolinium on all lower tier water moderators. We will present the influence of these changes on the integrated thermal flux and the time distribution of these moderators. As part of the upgrade of the Manual Lujan Jr. Neutron Scattering Center target (1L target) the goal was to increase the integrated thermal flux of the lower high intensity and the high resolution moderator by 20%. We will show in this paper that this goal can be achieved by introducing a pre-moderator concept on the high resolution moderators and by changing the decoupling scheme on all three moderators. Furthermore we will show that this goal can be achieved without jeopardizing the time of flight resolution of these moderators. For the all these calculations we used the radiation transport code MCNPX, which is most commonly used for this type of calculations.

  6. Upgrading the power supplies of TEXTOR for three Tesla operation

    International Nuclear Information System (INIS)

    Giesen, B.; Veiders, E.; Petree, F.; Fink, R.; Wagnitz, R.

    1986-01-01

    The toroidal magnetic system of TEXTOR can tolerate a magnetic field load of up to 2.6 Tesla routinely at full plasma current, and of up to 3 Tesla under certain boundary conditions and for a restricted number of discharges. The original power supply which can generate a toroidal magnetic field of 2 Tesla has been upgraded to operate at a field strength of 3 Tesla, by adding a new, controlled rectifier, with its own independent control, connected in parallel with the first. Studies were undertaken to determine its behaviour where control is lost, such as when a circuit breaker trips or in ''freewheel'' operation. This paper analyzes this asymmetrical arrangement and discusses the danger of damaging the smaller unit by commutating a large current into it. Moreover, in order to improve the availability of TEXTOR, the new controlled rectifier is redundant to two other units that control the vertical field and the ohmic heating coil currents. For this purpose the two bridges of this 12-pulse system are to be changed from a parallel to a series connexion, the free-wheeling diodes are disconnected and redeployed to block the large voltage pulses that are induced at plasma initiation, and 3-phase ''freewheeling'' thyristors are added that serve to reduce reactive power consumption

  7. Nova Upgrade: A proposed ICF facility to demonstrate ignition and gain, revision 1

    Science.gov (United States)

    1992-07-01

    The present objective of the national Inertial Confinement Fusion (ICF) Program is to determine the scientific feasibility of compressing and heating a small mass of mixed deuterium and tritium (DT) to conditions at which fusion occurs and significant energy is released. The potential applications of ICF will be determined by the resulting fusion energy yield (amount of energy produced) and gain (ratio of energy released to energy required to heat and compress the DT fuel). Important defense and civilian applications, including weapons physics, weapons effects simulation, and ultimately the generation of electric power will become possible if yields of 100 to 1,000 MJ and gains exceeding approximately 50 can be achieved. Once ignition and propagating bum producing modest gain (2 to 10) at moderate drive energy (1 to 2 MJ) has been achieved, the extension to high gain (greater than 50) is straightforward. Therefore, the demonstration of ignition and modest gain is the final step in establishing the scientific feasibility of ICF. Lawrence Livermore National Laboratory (LLNL) proposes the Nova Upgrade Facility to achieve this demonstration by the end of the decade. This facility would be constructed within the existing Nova building at LLNL for a total cost of approximately $400 M over the proposed FY 1995-1999 construction period. This report discusses this facility.

  8. Reactive Power Support of Electrical Vehicle Charging Station Upgraded with Flywheel Energy Storage System

    DEFF Research Database (Denmark)

    SUN, BO; Dragicevic, Tomislav; Savaghebi, Mehdi

    2015-01-01

    Electrical vehicles (EVs) are presenting increasingly potential to replace the conventional fossil fuel based vehicles due to environmental friendly characteristic. Accordingly, Charging Stations (CS), as an intermediate between grid and large numbers of EVs, are supposed to have more critical...... influence on future smart transportation network. This paper explores an off-board charging station upgraded with flywheel energy storage system that could provide a reactive power support to the grid utility. A supervisory control scheme based on distributed bus signaling is proposed to coordinate...... the operation of each component in the system. As a result, the charging station could supply the reactive power support to the utility grid without compromising the charging algorithm and preserve the battery’s lifetime. Finally, the real-time simulation results based on dSPACE1006 verifies the proposed...

  9. A comparison of advanced thermal cycles suitable for upgrading existing power plant

    International Nuclear Information System (INIS)

    Heyen, G.; Kalitventzeff, B.

    1999-01-01

    In view of the constant growth of electricity usage and public pressure to reduce the dependence on nuclear power plants in the energy supply, solutions are sought to increase the capacity of power plants using fossil fuels. Highly efficient cycles are available: gas turbines combined with waste heat boilers and steam cycles are able to achieve efficiencies above 50-55%. However building new plants requires a large amount of capital.Alternative proposals are based on upgrades of existing plants : capital savings are expected by reusing part of the facilities. In the present study, three parallel proposals are compared on the basis of exergy efficiency; cost of investment and flexibility of operation are also discussed. They are compared with classical Rankine cycle and state of the art combined cycles. (Copyright (c) 1999 Elsevier Science B.V., Amsterdam. All rights reserved.)

  10. Upgrading instrumentation and control in nuclear power plants. Design criteria

    International Nuclear Information System (INIS)

    Rodriguez Rodriguez, M.C.; Alvarez Menendez, A.

    1997-01-01

    The use of programmed digital technology in Protection, Control, Monitoring and Information Systems in new generation nuclear power plants, or the use of this technology to replace or upgrade existing systems based on wired analog instrumentation and electromechanical relays, has led to new international standards which establish new design requirements or adapt existing requirements to this technology. Additionally, both regulatory organisations and the industry are discussing the reliability of this technology, regarding common mode failures that may occur in redundant protection channels, due to the use of equipment and software with the same characteristics. The first part of this paper addresses the most important aspects of new international standards regarding classification criteria for I and C systems, equipment and functions, depending on their importance to safety and the design criteria applicable to each category. Special attention is drawn to requirements concerning software quality assurance and the design of new control rooms. The paper then goes on to discuss the different technical solutions being implemented, using equipment and software diversification, in order to prevent the possibility of common mode failures affecting the protection function. (Author)

  11. Seismic assessment and upgrading of Paks nuclear power plant

    International Nuclear Information System (INIS)

    Tamas, K.

    2001-01-01

    A comprehensive programme for seismic assessment and upgrading is currently in progress at Hungary's Paks NPP. The re-evaluation of the site seismic hazard had been already completed. The technology of safe shut down and heat removal is established and the systems and structures relevant for seismic safety are identified. A seismic instrumentation is installed. The pre-earthquake preparedness and post-earthquake actions are elaborated. The methods for seismic capacity assessment are selected. The seismic capacity evaluation and the design of upgrading measures are currently in progress. The easy to perform upgrading covering the most urgent measures had been already performed. (author)

  12. Modernisation of hydrogenerators. Upgrading of power plants for more efficiency; Modernisierung von Hydrogeneratoren. Kraftwerks-Upgrade fuer mehr Effizienz

    Energy Technology Data Exchange (ETDEWEB)

    Allen, John

    2012-07-01

    Ever since the construction of the first alternating current hydroelectric power plant with a performance of 12.5 kW in the year 1882, the number and performance of hydroelectric power plants had increased substantially. For example, the hydroelectric power plant at the Three Gorges Dam in the People's Republic of China has a total performance of 22,500 MW. The isolation systems of the hydrogenerators have a limited lifetime and have to be exchanged after fifty years usually. Under this aspect, the authors of the contribution under consideration reports on the upgrading of hydrogenerators for more efficiency.

  13. Questions to the reactors power upgrade of the Nuclear Power Plant of Laguna Verde

    International Nuclear Information System (INIS)

    Salas M, B.

    2014-08-01

    The two reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) were subjected to power upgrade labors with the purpose of achieving 20% upgrade on the original power; these labors concluded in August 24, 2010 for the Reactor 1 and in January 16, 2011 for the Reactor 2, however in January of 2014, the NNP-L V has not received by part of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) the new Operation License to be able to work with the new power, because it does not fulfill all the necessary requirements of safety. In this work is presented and analyzed the information obtained in this respect, with data provided by the Instituto Federal de Acceso a la Informacion Publica y Proteccion de Datos (IFAI) and the Comision Federal de Electricidad (CFE) in Mexico, as well as the opinion of some workers of the NPP-L V. The Governing Board of the CFE announcement that will give special continuation to the behavior on the operation and reliability of the NPP-L V, because the frequency of not announced interruptions was increased 7 times more in the last three years. (Author)

  14. Shielding assessment for the proposed HRIBF upgrade to the National ISOL Facility

    International Nuclear Information System (INIS)

    Slater, C.O.; Olsen, D.K.; Johnson, J.O.; Lillie, R.A.; Gabriel, T.A.

    1997-04-01

    An upgrade of the existing ORNL Holifield Radioactive Ion Beam Facility (HRIBF) to the National Radioactive Ion Beam Isotope Separator On Line (RIB ISOL) Facility is being proposed. Part of the upgrade involves increasing the source proton energy and current, resulting in more intense, higher energy radiation. Shielding requirements for the proposed upgrade to the HRIBF have been assessed with respect to weight, space, and dose-rate constraints. Shielding assessments were made for operating, shutdown, and accident conditions. The results indicate reasonable shielding solutions for the target room except for the marginal dose rate on the roof. Shielding requirements in the target room were greatly reduced by decisions to move the target to a more interior room and to direct the proton beam downward into the target. A slightly more difficult shielding problem arises for proton beam extraction losses from the cyclotron. Here, the assumed isotropic beam losses (hence, neutron emissions) mean higher roof dose rates than those over the target room unless substantial localized shielding is placed over the cyclotron. Shutdown dose rates were found to present no problems. While dose rates through the sides of the facility during accident conditions will probably satisfy the accident dose-rate constraints, dose rates above the roof will be well above the constraints unless a solution is devised to shield the locations where beam losses are likely to occur. Ground activation analysis was postponed for this study

  15. Overview of new, upgraded, or proposed high energy physics facilities in the United States and Canada

    International Nuclear Information System (INIS)

    Gabriel, T.A.

    1994-01-01

    This article reviews six new, proposed, or upgraded accelerator facilities in the United States and Canada. All of the accelerators that are presented here in one form or fashion challenge the validity of the Standard Model of high energy physics which ''currently explains'' all experimentally know phenomena. These facilities include the Continuous Electron Beam Accelerator Facility (CEBAF) at Newport News, Virginia, the Kaon Factory at TRIUMF in Vancouver, British Columbia, Canada, the Asymmetric B Factory at the Stanford Linear Accelerator Center (SLAC) in Palo Alto, California, the Relativistic Heavy Ion Collider (RHIC) facility at Brookhaven National Laboratory in Upton, New York, the injector upgrade project at the Fermi National Accelerator Laboratory (FNAL) in Batavia, Illinois, and the Superconducting Super Collider Laboratory (SSCL) in Waxachachie, Texas

  16. High power electron cyclotron heating in ISX and ORMAK Upgrade at ORNL

    International Nuclear Information System (INIS)

    England, A.C.; Eldridge, O.C.; Marcus, F.B.; Sprott, J.C.; Namkung, W.; Wilgen, J.B.

    1976-05-01

    A phased program of plasma heating at the electron cyclotron frequency is proposed for the Oak Ridge tokamaks ISX and ORMAK Upgrade. The past history of the program of electron cyclotron heating (ECH) at ORNL on mirrors and in the ELMO Bumpy Torus has been successful. Future technological developments in the production of high power high frequency microwave tubes look promising at this time. The physics of wave propagation and particle heating are fairly well understood and indicate the viability of this technique. Studies on breakdown and on runaway electron reduction will provide useful information for larger machines. Recent experiments in the USSR on small tokamaks have shown that ECH is a viable heating technique. Providing that the microwave tubes become available, the engineering considerations suggest that the technique is practical and workable, based on present day technology

  17. Technical Proposal for the Phase-II Upgrade of the CMS Detector

    CERN Document Server

    CMS Collaboration; Contardo, D; Klute, M; Mans, J; Silvestris, L; Butler, J; CERN. Geneva. The LHC experiments Committee; LHCC

    2015-01-01

    This Technical Proposal presents the upgrades foreseen to prepare the CMS experiment for the High Luminosity LHC. In this second phase of the LHC physics program, the accelerator will provide to CMS an additional integrated luminosity of about 2500 fb-1 over 10 years of operation, starting in 2025. This will substantially enlarge the mass reach in the search for new particles and will also greatly extend the potential to study the properties of the Higgs boson discovered at the LHC in 2012. In order to meet the experimental challenges of unprecedented p-p luminosity, the CMS collaboration will need to address the aging of the present detector and to improve the ability of the apparatus to isolate and precisely measure the products of the most interesting collisions. This document describes the conceptual designs and the expected performance of the upgrades, along with the plans to develop the appropriate experimental techniques. The infrastructure upgrades and the logistics of the installation in the experim...

  18. Upgrading safety documentation for exported nuclear power plants

    International Nuclear Information System (INIS)

    Rosen, M.

    1978-01-01

    In view of the generally small regulatory staffs of importing countries, suggestions are given for upgrading the ''export edition'' of the traditionally supplied safety documentation by use of a Supplementary Information Report, written specifically for the needs of a smaller and/or less technically qualified staff, which would highlight the differences that exist between the facility to be constructed and the supposedly similar reference plant of the supplier country; by improvement of supporting safety documentation to allow for adequate understanding of significant safety parameters; and by attention to the needs of smaller countries in the critical operating regulations (Technical Specifications for Operation). (author)

  19. 76 FR 20624 - Oglethorpe Power Corporation: Proposed Biomass Power Plant

    Science.gov (United States)

    2011-04-13

    ... DEPARTMENT OF AGRICULTURE Rural Utilities Service Oglethorpe Power Corporation: Proposed Biomass Power Plant AGENCY: Rural Utilities Service, USDA. ACTION: Notice of Availability of a Draft... financial assistance to Oglethorpe Power Corporation (Oglethorpe) for the construction of a 100 megawatt (MW...

  20. Proposal of an alternative upper divertor in ASDEX Upgrade supported by EMC3-EIRENE simulations

    Directory of Open Access Journals (Sweden)

    T. Lunt

    2017-08-01

    Full Text Available We discuss the benefits of installing a pair of in-vessel coils with currents |Ifx| ≲ 50 kAt in the upper divertor of ASDEX Upgrade (AUG to study a series of ‘alternative’ divertor configurations, like the Snowflake (SF and the X-divertor (XD, that are currently considered as alternative solutions for the power exhaust problem. The possibility of operating the standard lower single-null (SN and double-null (DN would be preserved. Potential effects to reduce the peak parallel- and/or perpendicular heat flux are predicted from a simple geometrical-diffusive model as well as by numerical EMC3-EIRENE simulations for pure deuterium attached conditions with spatially constant diffusion coefficients. Beyond that a series of other potential transport- and radiation related heat flux mitigation effects are identified and could be studied experimentally with the modified upper divertor in the high-power divertor Tokamak AUG.

  1. A proposal for the GridPixel Tracker for the ATLAS sLHC upgrade.

    CERN Document Server

    The ATLAS collaboration

    2009-01-01

    A proposal for GridPix Tracker for the ATLAS sLHC upgrade. F. Hartjes, M.Fransen, W. Koppert, K.Konovalov, S.Morozov, A.Romaniouk, M. Rogers, H. van der Graaf. A concept of the GridPix detector as a tracker for the ATLAS Inner Detector proposed for SLHC upgrade is presented. The detector can combine precise vector tracking function and particle identification features using a transition radiation and dE/dX measurements. Test beam and MC studies of the tracking and the particle identification properties have been performed with the dedicated GridPix prototype. Data was taken with the different gas mixtures. Special accuracy achieved in the test beam is ~30 m. For one layer of the GridPix detector a vector angular accuracy of about 10 mrad was obtained. It was shown that for one layer of the real detector at very realistic conditions one should expect angular accuracy better than 5 mrad. For particle identification studies detector was filled with a Xe/CO2(70/30) mixture. A block of a transition radiation ra...

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

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

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

    International Nuclear Information System (INIS)

    1998-04-01

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

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

    International Nuclear Information System (INIS)

    Toth, A.

    1998-01-01

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

  5. The upgraded PSI application in the BEPCⅡ power supply control system

    International Nuclear Information System (INIS)

    Li Jiangqi; Wang Xiaoli; Wang Chunhong; Liu Jia

    2011-01-01

    There are about 460 magnet power supplies in the two rings and the transport lines of the BEPCⅡ which are controlled by the power supply controller and the power supply interface. An upgraded Power Supply Interface (PSI-Ⅱ) was developed for replacing the old one in the power supply control system of the BEPCⅡ. It will firstly describe feature of the PSI-Ⅱ and difference from the PSI. Then, discuss performance test of the PSI-Ⅱ well as its application in the power supply control system. (authors)

  6. Upgrading the standard makeup node at the Dukovany nuclear power plant

    International Nuclear Information System (INIS)

    Charvat, L.; Dvorak, J.

    1999-01-01

    Modifications made on the normal makeup and boron control system of the Dukovany nuclear power plant in 1997 and 1998 are described. The reasons for and objectives of the upgrading are highlighted in relation to the reliability of the facility and maintenance cost of the system. (author)

  7. Some aspects of digital I and C and digital human-system interface upgrades in nuclear power plants

    International Nuclear Information System (INIS)

    Mandic, D.

    2005-01-01

    Digital I and C technology introduces some new terms and new processes like software life cycle, process computer configuration control, digital human-system interface (HSI), software V and V (Verification and Validation), software common mode failure potential, software documentation, etc. Based on the experience from NEK, and other NPPs and published reports from other organizations, this paper sheds light on challenging tasks related to some aspects of the digital I and C upgrades and especially the NPP MCR/MCB HSI (Nuclear Power Plant Main Control Room / Main Control Board Human-System Interface) upgrade. The Ref. [1], EPRI Report TR-1008122 was used as a guidance to analyze original NEK MCR/MCB HSI design (1970s), to describe migration from the original MCR/MCB HSI design to the 2005 AS-BUILT status and to propose the authors vision for the key planning aspects for I and C upgrades and MCR modernization. This paper submits the justified proposal for the endpoint vision and the migration path applicable to NEK MCR/MCB HSI modernization, as well as some of the possible risks and lessons learned. (author)

  8. Upgrading of electrostatic precipitators in old thermal power plant

    Energy Technology Data Exchange (ETDEWEB)

    Gurumurthy, H V

    1987-02-01

    Indian thermal power stations installed in the 60's and earlier had dust collectors whose efficiency was well below the acceptable level of emission under the Air (Prevention and Control of Pollution) Act 1981. This necessitates the need for higher efficiency dust collectors to be installed in old thermal power stations. Further, the poor quality of the coal being received at power stations presently causes severe environmental pollution in and around the plant. This paper deals with the retrofitting of electrostatic precipitators in existing units and the problems encountered in executing the same.

  9. A proposed NSLS x-ray ring upgrade using B factory technology

    International Nuclear Information System (INIS)

    Blum, E.B.

    1995-01-01

    A proposed upgrade to the NSLS X-Ray Ring is described that will allow the storage of a 2.4 A. 3 GeV electron beam using technology developed for the PEP-II B factory at SLAC. In this configuration, a peak flux of greater than 10 16 photons/sec/0.1% bandwidth/5 mrad will be produced. The four existing 53 MHz RF cavities will be replaced with eight 476 MHz cavities. Two 952 MHz cavities will also be used to lengthen the bunch, increasing the Touschek life-time. A copper vacuum chamber will be needed to absorb the increased synchrotron radiation and a feedback system may be needed to prevent multi-bunch instabilities

  10. 75 FR 32940 - Request for Proposals for New or Upgraded Transmission Line Projects Under Section 1222 of the...

    Science.gov (United States)

    2010-06-10

    ... financial condition and has the ability to secure the necessary financing to meet the Project's requirements... for Proposals for New or Upgraded Transmission Line Projects Under Section 1222 of the Energy Policy..., Department of Energy. ACTION: Request for Project Proposals. SUMMARY: The Department of Energy (DOE or...

  11. DIII-D ICRF high voltage power supply regulator upgrade

    International Nuclear Information System (INIS)

    Cary, W.P.; Burley, B.L.; Grosnickle, W.H.

    1997-11-01

    For reliable operation and component protection, of the 2 MW 30--120 MHz ICRF Amplifier System on DIII-D, it is desirable for the amplifier to respond to high VSWR conditions as rapidly as possible. This requires a rapid change in power which also means a rapid change in the high voltage power supply current demands. An analysis of the power supply's regulator dynamics was needed to verify its expected operation during such conditions. Based on this information it was found that a new regulator with a larger dynamic range and some anticipation capability would be required. This paper will discuss the system requirements, the as-delivered regulator performance, and the improved performance after installation of the new regulator system. It will also be shown how this improvement has made the amplifier perform at higher power levels more reliably

  12. Upgrading to lead firm position via international acquisition: learning from the global biomass power plant industry

    DEFF Research Database (Denmark)

    Hansen, Ulrich Elmer; Fold, Niels; Hansen, Teis

    2016-01-01

    This article examines the case of a Chinese firm that has upgraded to lead firm position in the global biomass power plant industry mainly through acquisitions of technological frontier firms in Denmark. Sustaining the lead firm position was, however, challenged by difficulties in developing...... innovative capability. Drawing on the literature on (i) firm-level technological capability and (ii) knowledge transfer in international acquisitions, we explain the reasons for insufficient innovative capability building. Based on these empirical findings, we suggest maintaining the existing upgrading...

  13. Approach of seismic upgrading in Kashiwazaki-Kariwa Nuclear Power Plant

    International Nuclear Information System (INIS)

    Sato, Hitoshi

    2009-01-01

    Because guide for reviewing seismic design of nuclear power reactor facilities was reworked in 2006, we formulated new Design Base Seismic Motion Ss, and we are doing evaluation of seismic safety (back-check). In Japan, depending on aseismatic importance, equipments are classified into S-class, B-class and C-class. For S-class equipments, we evaluate it on the basis of new Ss, and do seismic upgrading. For B-class and C-class equipments, we do seismic upgrading voluntarily on the basis of the experiences of the Niigataken Chuetsu-Oki (NCO) Earthquake. (author)

  14. 76 FR 77963 - Oglethorpe Power Corporation; Proposed Biomass Power Plant

    Science.gov (United States)

    2011-12-15

    ... Service Oglethorpe Power Corporation; Proposed Biomass Power Plant AGENCY: Rural Utilities Service, USDA... related to possible financial assistance to Oglethorpe Power Corporation's (Oglethorpe) for the... online at the following Web site: http://www.rurdev.usda.gov/UWP-OglethorpePower.html and at the: Warren...

  15. Low voltage powering of on-detector electronics for HL-LHC experiments upgrades

    CERN Document Server

    Bobillier, Vincent; Vasey, Francois; Karmakar, Sabyasachi; Maity, Manas; Roy, Subhasish; Kundu, Tapas Kumar

    2018-01-01

    All LHC experiments will be upgraded during the next LHC long shutdowns (LS2 and LS3). The increase in resolution and luminosity and the use of more advanced CMOS technology nodes typically implies higher current consumption of the on-detector electronics. In this context, and in view of limiting the cable voltage drop, point-of-load DC-DC converters will be used on detector. This will have a direct impact on the existing powering scheme, implying new AC-DC and/or DC-DC stages as well as changes in the power cabling infrastructure. This paper presents the first results obtained while evaluating different LV powering schemes and distribution layouts for HL-LHC trackers. The precise low voltage power source requirements are being assessed and understood using the CMS tracker upgrade as a use-case.

  16. Feasibility study on Bobovdol thermal power plant upgrading project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-03-01

    A survey has been made in relation with the improvement project intended of energy conservation, and reduction of global warming gas emission at the Bobovdol thermal power plant located in the suburb of Sofia, the capital of the Republic of Bulgaria. The existing Bobovdol power plant having a total capacity of 630 MW with three generators is a coal burning thermal power plant having been used already for 23 to 27 years, hence over-aged. The survey has discussed an improvement project of scrap-and-build type to make the plant a high-efficiency gas combined cycle power plant using gas turbines. The project calls for building 210-MW gas combined power generation facilities having 70-MW gas turbines, one each in three stages in 2007, 2012 and 2017. As a result of the discussions, the fuel consumption reducing rate was found to reach 37.99%, whereas the cumulative energy saving quantity in 41 years will reach 16.37 million tons of fuel oil equivalent. In addition, the reduction rate of global warming gas emission is 57.75%, and the cumulative reduction quantity in 41 years is 105.18 million tons. (NEDO)

  17. U.S.-Russia MPC and A upgrades at the Beloyarsk Nuclear Power Plant

    International Nuclear Information System (INIS)

    Saraev, O.; Haase, M.; Smarto, C.; Mikkelsen, K.; Heinberg, C.; Showalter, R.; Soo Hoo, M.; Hatcher, C.; Forehand, M.

    1998-01-01

    During the January 1996 meeting of the Gore-Chernomyrdin Commission, the Beloyarsk Nuclear Power Plant (BNPP) was identified as one of the additional sites for cooperative projects on upgrading Materials Protection, Control and Accounting (MPC and A). Since June 1996, Sandia National Laboratories (SNL), Pacific Northwest National Laboratories (PNNL), and Los Alamos National Laboratory (LANL) have worked with BNPP to upgrade MPC and A at the facility. Some unique challenges were encountered because BNPP has an operating BN-600 600-Megawatt breeder reactor. SNL has been responsible for working with BNPP to implement physical protection upgrades to the Central Alarm Station, Fresh Fuel Storage building, Spent Fuel Storage Area, and Vehicle/Personnel Portal. In addition, improved communication equipment for the Ministry of the Interior (MVD) guards and training of personnel were provided. PNNL has been responsible for coordinating Material Control and Accounting (MC and A) upgrades at BNPP. PNNL, in conjunction with LANL, has implemented such MC and A upgrades as a computerized nuclear materials accounting system, training in MC and A elements, nondestructive assay instrumentation for fresh fuel, installation of a fork detector for measuring spent fuel, and installation of an underwater video camera for verification of spent fuel serial numbers

  18. Divertor power and particle fluxes between and during type-I ELMs in the ASDEX Upgrade

    Science.gov (United States)

    Kallenbach, A.; Dux, R.; Eich, T.; Fischer, R.; Giannone, L.; Harhausen, J.; Herrmann, A.; Müller, H. W.; Pautasso, G.; Wischmeier, M.; ASDEX Upgrade Team

    2008-08-01

    Particle, electric charge and power fluxes for type-I ELMy H-modes are measured in the divertor of the ASDEX Upgrade tokamak by triple Langmuir probes, shunts, infrared (IR) thermography and spectroscopy. The discharges are in the medium to high density range, resulting in predominantly convective edge localized modes (ELMs) with moderate fractional stored energy losses of 2% or below. Time resolved data over ELM cycles are obtained by coherent averaging of typically one hundred similar ELMs, spatial profiles from the flush-mounted Langmuir probes are obtained by strike point sweeps. The application of simple physics models is used to compare different diagnostics and to make consistency checks, e.g. the standard sheath model applied to the Langmuir probes yields power fluxes which are compared with the thermographic measurements. In between ELMs, Langmuir probe and thermography power loads appear consistent in the outer divertor, taking into account additional load due to radiation and charge exchange neutrals measured by thermography. The inner divertor is completely detached and no significant power flow by charged particles is measured. During ELMs, quite similar power flux profiles are found in the outer divertor by thermography and probes, albeit larger uncertainties in Langmuir probe evaluation during ELMs have to be taken into account. In the inner divertor, ELM power fluxes from thermography are a factor 10 larger than those derived from probes using the standard sheath model. This deviation is too large to be caused by deficiencies of probe analysis. The total ELM energy deposition from IR is about a factor 2 higher in the inner divertor compared with the outer divertor. Spectroscopic measurements suggest a quite moderate contribution of radiation to the target power load. Shunt measurements reveal a significant positive charge flow into the inner target during ELMs. The net number of elementary charges correlates well with the total core particle loss

  19. Upgrade of DC power supply system in ITER CS model coil test facility

    International Nuclear Information System (INIS)

    Shimono, Mitsugu; Uno, Yasuhiro; Yamazaki, Keita; Kawano, Katsumi; Isono, Takaaki

    2014-03-01

    Objective of the ITER CS Model Coil Test Facility is to evaluate a large scale superconducting conductor for fusion using the Central Solenoid (CS) Model Coil, which can generate a 13T magnetic field in the inner bore with a 1.5 m diameter. The facility is composed of a helium refrigerator / liquefier system, a DC power supply system, a vacuum system and a data acquisition system. The DC power supply system supplies currents to two superconducting coils, the CS Model Coil and an insert coil. A 50-kA DC power supply is installed for the CS Model Coil and two 30 kA DC power supplies are installed for an insert coil. In order to evaluate superconducting performance of a conductor used for ITER Toroidal Field (TF) coils whose operating current is 68 kA, the line for an insert coil is upgraded. A 10 kA DC power supply was added, DC circuit breakers were upgraded, bus bars and current measuring instrument were replaced. In accordance to the upgrade, operation manual was revised. (author)

  20. Nuclear instrument upgrade at Connecticut Yankee Atomic Power Station

    International Nuclear Information System (INIS)

    Brothers, M.H.; Flynn, B.J.; Shugars, H.G.

    1989-01-01

    After 20 years of commercial operation, the Connecticut Yankee Atomic Power Station decided to replace the original nuclear instrument system. The plant was motivated primarily by reliability and maintainability problems, the former attributed to equipment wearout and discrete component failure, and the latter to the unavailability of qualified spare parts, another effect of the equipment's age. In replacing the system, the plant also had to address current regulatory, design, and plant technical specification requirements, including physical separation, signal isolation, and changes in equipment qualification. This paper discusses the motivation for the system's replacement, the challenges to the plant engineers and equipment designers, the ways in which the new design met the challenges, the test results of the new system, and other potential benefits supported by the test results

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  2. H-mode confinement properties close to the power threshold in ASDEX Upgrade

    International Nuclear Information System (INIS)

    Ryter, F; Fuchs, J; Schneider, W; Sips, A; Staebler, A; Stober, J

    2008-01-01

    Confinement properties close to the H-mode power threshold are studied in the ASDEX Upgrade tokamak. The results show that good confinement can be obtained close to the threshold with Type-I ELMs. The existence of Type-I ELMs does not necessarily require the heating power to be higher than the H-Mode power threshold, but it requires collisionality to be low enough. At higher collisionality Type-III ELMs replace the Type-I ELMs and confinement time is reduced by about 20%

  3. Constitutional determinants of nuclear power plant upgrading; Verfassungsrechtliche Determinanten bei der Nachruestung von Kernkraftwerken

    Energy Technology Data Exchange (ETDEWEB)

    Mann, Thomas [Goettingen Univ. (Germany). Lehrstuhl fuer Oeffentliches Recht, insbesondere Verwaltungsrecht; NdsOVG - Niedersaechsisches Oberverwaltungsgericht (Germany)

    2013-11-01

    Around half a year ago the European stress test for nuclear power plants, a precautionary measure initiated by the European Council in March 2011 in response to the Fukushima disaster, revealed that while German nuclear power plants show a high degree of robustness compared with those in other European countries, they nevertheless required upgrading in one or the other respect (earthquake warning systems, protection against crashing civil passenger airplanes). The present article investigates whether this upgrading requirement can justify an injunction to carry out structural retrofitting measures or whether obligations to this end can be excluded on grounds of reasonability in view of the recent decision taken by the German parliament to phase out nuclear energy.

  4. Brain Gain Malaysia (BGM): Feasibility Studies to Upgrading the Power of TRIGA PUSPATI Reactor (RTP)

    International Nuclear Information System (INIS)

    Naim Shauqi Hamzah; Mohd Fairus Abdul Farid; Julia Abdul Karim

    2011-01-01

    BGM Programme introduced by MOSTI has give the opportunities for Reactor Technology Division to get the expertise from Romania for upgrading the power output of RTP. 2 and a half months programme include expertise development in neutronic fields and thermal hydraulics and also introduction of reactor technology to IPTA and IPTS students. This programme also benefited the staffs of BTR as activities conducted intensively and hands-on to make the researchers can improved their knowledge on related computer code effectively. (author)

  5. Empiricial scaling of inter-ELM power widths in ASDEX Upgrade and JET

    Energy Technology Data Exchange (ETDEWEB)

    Eich, T., E-mail: teich@ipp.mpg.de [Max-Planck-Institut für Plasmaphysik, EURATOM Association, Boltzmannstr. 2, D-85748 Garching (Germany); Sieglin, B.; Scarabosio, A.; Herrmann, A.; Kallenbach, A. [Max-Planck-Institut für Plasmaphysik, EURATOM Association, Boltzmannstr. 2, D-85748 Garching (Germany); Matthews, G.F. [EURATOM/CCFE Association, Culham Science Centre, Abingdon, Oxon OX14 3DB (United Kingdom); Jachmich, S. [ERM-KMS, EURATOM Association, Brussels (Belgium); Brezinsek, S.; Rack, M. [IEK-4, Forschungszentrum Jülich, EURATOM Association (Germany); Goldston, R.J. [Princeton Plasma Physics Labaratory, Princeton, NJ 08543 (United States)

    2013-07-15

    The SOL power decay length (λ{sub q}) deduced from analysis of fully attached divertor heat load profiles from two tokamaks, JET and ASDEX Upgrade with carbon plasma facing components, are presented. Interpretation of the target heat load profiles is performed by using a 1D-fit function which disentangles the upstream λ{sub q} and an effective diffusion in the divertor (S), the latter essentially acting as a power spreading parameter in the divertor volume. It is shown that the so called integral decay length λ{sub int} is approximately given by λ{sub int}≈λ{sub q}+1.64×S. An empirical scaling reveals parametric dependency λ{sub q}/mm≃0.9·B{sub T}{sup -0.7}q{sub cyl}{sup 1.2}P{sub SOL}{sup 0}R{sub geo}{sup 0} for type-I ELMy H-modes. Extrapolation to ITER gives λ{sub q}≃1 mm. Recent measurements in JET-ILW and from ASDEX Upgrade full-W confirm the results. It is shown that a regression for the divertor power spreading parameter S is not yet possible due to the large effect of different divertor geometries of JET and ASDEX Upgrade Divertor-I and Divertor-IIb.

  6. A proposal to upgrade the ATLAS RPC system for the High Luminosity LHC

    CERN Document Server

    ATLAS Collaboration; The ATLAS collaboration

    2015-01-01

    The architecture of the present trigger system in the ATLAS Muon Barrel was designed according to a reference luminosity of 10^34 cm-2 s-1 with a safety factor of 5, with respect to the simulated background rates, now confirmed by LHC Run-1 data. HL-LHC will provide a luminosity 5 times higher and an order of magnitude higher background. As a result, the performance demand increases, while the detector being susceptible to ageing effects. Moreover, the present muon trigger acceptance in the barrel is just above 70%, due to the presence of the barrel toroid structures. This scenario induced the ATLAS muon Collaboration to propose an appropriate upgrade plan, involving both detector and trigger-readout electronics, to guarantee the performance required by the physics program for the 20 years scheduled. This consists in installing a layer of new generation RPCs in the inner barrel, to increase the redundancy, the selectivity, and provide almost full acceptance. The first 10% of the system, corresponding to the e...

  7. Digitalizing upgrade of the power supplies for the extraction septum magnets in HIRFL-CSR

    International Nuclear Information System (INIS)

    Zhao Jiang; Zhang Huajian; Wu Fengjun; Yuan Zhendong; Chen Youxin; Huang Yuzhen; Gao Daqing

    2014-01-01

    This paper introduces the working principle of the power supplies for the septum magnets in HIRFL-CSR and presents a feasible scheme of digitalizing these power supplies. The scheme employed the SOPC (system-on-a-programmable-chip) technology based on FPGA, the software framework of NIOSII and the polycyclic adjustment algorithm realized by the hardware description language. Then, several key problems that could be encountered in realizing the power supply control algorithm on FPGA were discussed. After the power supplies were upgraded, the beam of HIRFL-CSR was extracted more reliably and the stability of beam spot position at the experimental terminals has been obviously improved. This work would provide a valuable reference for the engineers of digitalizing other magnetic power supplies in HIRFL-CSR and of developing magnetic power supplies for heavy ion cancer therapy. (authors)

  8. Upgrade of the synchronous data management system of the EAST poloidal field power supply

    International Nuclear Information System (INIS)

    Zhu, Lili; Huang, Liansheng; Fu, Peng; Gao, Ge; He, Shiying

    2016-01-01

    Highlights: • The upgraded synchronous data management system of EAST poloidal field power supply supports long-pulse data storage. • Slice storage mechanism on MDSplus has been adopted for quasi real-time data storage. • The state machine has been adopted for managing the system sequencer. • IEEE-1588 protocol via Ethernet for the synchronization of clock signal was detailed described. - Abstract: Poloidal field (PF) power supply is an important subsystem of the Experimental Advanced Superconducting Tokamak (EAST). The upgrade of the PF control system of EAST is a great improvement over the original data management system which could not meet the requirements necessary for experiments on synchronization, modularity and sampling rate. In order to better analyze the power operation performance, the Synchronization Data Management System (SDMS) needs to be upgraded as well. This upgrade is based on distributed data acquisition and an MDSPLUS database. It consists of three data acquisition nodes synchronized by an reference clock from the EAST central timing system that also provides the start trigger of the EAST pulse. After being processed by a signal conditioning unit, experimental signals are digitized and written into the database in MDSPLUS format. Multi-channel, multi-tasking and continuous data storage have been achieved by using multi-threading technology on a Linux operation system. The SDMS has been used on the server in PF control system for the entire 2015 EAST campaign. The SDMS has had good performance during experiments and convenient human-machine interface to satisfy the requirements of all the experiments.

  9. Upgrade of the synchronous data management system of the EAST poloidal field power supply

    Energy Technology Data Exchange (ETDEWEB)

    Zhu, Lili; Huang, Liansheng, E-mail: huangls@ipp.ac.cn; Fu, Peng; Gao, Ge; He, Shiying

    2016-11-15

    Highlights: • The upgraded synchronous data management system of EAST poloidal field power supply supports long-pulse data storage. • Slice storage mechanism on MDSplus has been adopted for quasi real-time data storage. • The state machine has been adopted for managing the system sequencer. • IEEE-1588 protocol via Ethernet for the synchronization of clock signal was detailed described. - Abstract: Poloidal field (PF) power supply is an important subsystem of the Experimental Advanced Superconducting Tokamak (EAST). The upgrade of the PF control system of EAST is a great improvement over the original data management system which could not meet the requirements necessary for experiments on synchronization, modularity and sampling rate. In order to better analyze the power operation performance, the Synchronization Data Management System (SDMS) needs to be upgraded as well. This upgrade is based on distributed data acquisition and an MDSPLUS database. It consists of three data acquisition nodes synchronized by an reference clock from the EAST central timing system that also provides the start trigger of the EAST pulse. After being processed by a signal conditioning unit, experimental signals are digitized and written into the database in MDSPLUS format. Multi-channel, multi-tasking and continuous data storage have been achieved by using multi-threading technology on a Linux operation system. The SDMS has been used on the server in PF control system for the entire 2015 EAST campaign. The SDMS has had good performance during experiments and convenient human-machine interface to satisfy the requirements of all the experiments.

  10. Booster main magnet power supply, present operation and potential future upgrades

    Energy Technology Data Exchange (ETDEWEB)

    Bajon, E.; Bannon, M.; Marneris, I.; Danowski, G.; Sandberg, J.; Savatteri, S.

    2011-03-28

    The Brookhaven Booster Main Magnet Power Supply (MMPS) is a 24 pulse thyristor control supply, rated at 5500 Amps, +/-2000 Volts, or 3000 Amps, +/-6000 Volts. The power supply is fed directly from the power utility and the peak magnet power is 18 MWatts. This peak power is seen directly at the incoming ac line. This power supply has been in operation for the last 18 years. This paper will describe the present topology and operation of the power supply, the feedback control system and the different modes of operation of the power supply. Since the power supply has been in operation for the last 18 years, upgrading this power supply is essential. A new power supply topology has been studied where energy is stored in capacitor banks. DC to DC converters are used to convert the dc voltage stored in the capacitor banks to pulsed DC voltage into the magnet load. This enables the average incoming power from the ac line to be constant while the peak magnet power is pulsed to +/- 18 MWatts. Simulations and waveforms of this power supply will be presented.

  11. Presentation plan of the reconstruction and upgrade hydroelectric power plant 'Zvornik'

    Directory of Open Access Journals (Sweden)

    Krstić Dušan B.

    2016-01-01

    Full Text Available By the basic project of the energy utilization of the middle part of the river Drina (from Višegrad to Zvornik building of five large hydroelectric power plants was planned. Hydroelectric power plant near Zvornik had the greatest advantage, and it is the first built. Hydroelectric power plant 'Zvornik' separates the river Drina, about 1 km upstream from Mali Zvornik in Serbia and Zvornik in Bosnia and Herzegovina. In order to extend the work life, by the urban development project was planned modernization of production aggregates and associated equipment, the upgrade of annexes above the aggregate siphons A1 and A2, as well as the upgrade of the annexes of the powerhouse on the right bank of the river in the function of accommodation of electrical equipment. By replacing of the vital parts of turbines with increasing diameter with an increase of efficiency, Bow and power, as well as replacing generators with new generator of higher power with excitation and all the necessary auxiliary equipment, will ensure reliable operation of the hydroelectric power plant and will extend the working life of the next 40 years, creating opportunities for retrofitting additional fifth unit.

  12. Study of the performance of the photovoltaic system of the Pierre Auger Observatory and proposal for an upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Aguera, A.L.; Anjos, J.C. dos; Barbosa, A.F.; Piombini, F.M.; Ramos, V.S. [Centro Brasileiro de Pesquisas Fisicas (CBPF), Rio de Janeiro, RJ (Brazil); Bonifazi, C. [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil); Guedes, G.P. [Universidade Estadual de Feira de Santana (UEFS), BA (Brazil); Pepe, I.M. [Universidade Federal da Bahia (UFBA), Salvador, BA (Brazil)

    2011-07-01

    Full text: Each one of the 1660 stations of the Surface Detector of the Pierre Auger Observatory is powered by a 100W stand-alone photovoltaic (PV) system composed of a solar panel and two batteries in series on a 24 V setup. Each station continuously stores information by use of a data logger and a radio link. Data is recorded and transmitted roughly every 6 minutes to the Central Data Acquisition Building. In addition to cosmic ray related data, PV performance parameters are also monitored. As a consequence, Auger constitutes an interesting setup for PV stand-alone systems research. In this work, we present the control processes used to ensure optimal performance of the solar power system in the Auger Observatory and propose an upgrade to ensure a better system performance. Most of the work is centered on the batteries, which are the most sensitive elements of the power chain. The batteries are of the Valve Regulated Lead-Acid (VRLA) type, manufactured by Moura-Brazil. A dedicated system has been designed and built in order to qualify the batteries before installation in the field. During regular operation, the monitoring data are exhaustively analyzed in order to detect failures. A set of analysis tools has been developed, both for anomalies detection and for lifetime predictions. From the reported analysis, it has been possible to identify some aspects of the adopted PV system that may be improved, mainly on the batteries voltage unbalance, which rises on charging two batteries in series on a 24V setup. We show that the same behavior is observed in laboratory tests. In order to reduce battery failures, we proposed and tested the detector electronics performance when working with batteries in parallel on a 12V setup. The main changes on the solar power system of the detector are the connections of the solar panel and batteries (from 24V to 12V), the replacement of the charge controller and the introduction a low power DC-DC converter. Our results show that this

  13. Study of the performance of the photovoltaic system of the Pierre Auger Observatory and proposal for an upgrade

    International Nuclear Information System (INIS)

    Aguera, A.L.; Anjos, J.C. dos; Barbosa, A.F.; Piombini, F.M.; Ramos, V.S.; Bonifazi, C.; Guedes, G.P.; Pepe, I.M.

    2011-01-01

    Full text: Each one of the 1660 stations of the Surface Detector of the Pierre Auger Observatory is powered by a 100W stand-alone photovoltaic (PV) system composed of a solar panel and two batteries in series on a 24 V setup. Each station continuously stores information by use of a data logger and a radio link. Data is recorded and transmitted roughly every 6 minutes to the Central Data Acquisition Building. In addition to cosmic ray related data, PV performance parameters are also monitored. As a consequence, Auger constitutes an interesting setup for PV stand-alone systems research. In this work, we present the control processes used to ensure optimal performance of the solar power system in the Auger Observatory and propose an upgrade to ensure a better system performance. Most of the work is centered on the batteries, which are the most sensitive elements of the power chain. The batteries are of the Valve Regulated Lead-Acid (VRLA) type, manufactured by Moura-Brazil. A dedicated system has been designed and built in order to qualify the batteries before installation in the field. During regular operation, the monitoring data are exhaustively analyzed in order to detect failures. A set of analysis tools has been developed, both for anomalies detection and for lifetime predictions. From the reported analysis, it has been possible to identify some aspects of the adopted PV system that may be improved, mainly on the batteries voltage unbalance, which rises on charging two batteries in series on a 24V setup. We show that the same behavior is observed in laboratory tests. In order to reduce battery failures, we proposed and tested the detector electronics performance when working with batteries in parallel on a 12V setup. The main changes on the solar power system of the detector are the connections of the solar panel and batteries (from 24V to 12V), the replacement of the charge controller and the introduction a low power DC-DC converter. Our results show that this

  14. Status of the upgraded version of the NRL GAMBLE II pulse power generator

    International Nuclear Information System (INIS)

    Boller, J.R.; Burton, J.K.; Shipman, J.D. Jr.

    1979-01-01

    The GAMBLE II water dielectric pulse power generator, in 1970, was the forerunner of the high energy (> 50 kJ) class of water dielectric generators. It has been redesigned internally to make maximum use of its original outer conductor shell and to optimize it for the positive polarity mode of operation for positive ion beam experimentation. The new design also initiates the use of an oil dielectric multi-channel switch at the output of the pulse forming line. This switch, because of its low capacitance, eliminates the need for an extra prepulse switch. The upgraded version has been tested up to power and energy levels which are nearly twice the original

  15. The magnet power control system for the tandem mirror experiment-upgrade

    International Nuclear Information System (INIS)

    Bell, H.H.

    1983-01-01

    This paper describes the desktop computer/CAMAC based system that controls the power source for the Tandem Mirror Experiment-Upgrade (TMX-U) magnet power system. Presently it contains 42 dc rectifier power supplies connected to 24 magnet coils arranged in 17 circuits. During each shot, the system delivers 22.6 MW dc to the magnets for about 3 s. The system is presently being changed to add six power supplies, two solenoidal throttle coils, and two reverse C-coils. When complete, the delivered power will increase to 36.9 MW. The closed-loop control system usually provides current (and thus, magnetic field) that is within 1% of the requested current. Achieving this accuracy required using grounding, shielding, and isolation methods to reduce noise and related problems

  16. Dynamic analysis of compact helical system power supply and designs of its upgrade

    International Nuclear Information System (INIS)

    Tanahashi, S.; Yamada, S.

    1991-09-01

    Computed dynamic waveforms are compared with measured ones for the power supply of the Compact Helical System (CHS) during 1.5T operation and found to be in good agreement. On the basis of these results, designs for the upgraded power supply for 2T operation are discussed in the two cases, with and without power consumption for additional heating. In the former case, the additional heating power is supplied from the ac generator that powers the CHS coils. Electric voltages and currents in the electric circuit are shown for both cases. These designs show the possibility for 2T operation by addition of some components without changing the ratings of existing components. (author)

  17. Environmental assessment for the proposed CMR Building upgrades at the Los Alamos National Laboratory, Los Alamos, New Mexico. Final document

    International Nuclear Information System (INIS)

    1997-01-01

    In order to maintain its ability to continue to conduct uninterrupted radioactive and metallurgical research in a safe, secure, and environmentally sound manner, the US Department of Energy (DOE) proposes to upgrade the Los Alamos National Laboratory (LANL) Chemistry and Metallurgy Research (CMR) Building. The building was built in the early 1950s to provide a research and experimental facility for analytical chemistry, plutonium and uranium chemistry, and metallurgy. Today, research and development activities are performed involving nuclear materials. A variety of radioactive and chemical hazards are present. The CMR Building is nearing the end of its original design life and does not meet many of today's design codes and standards. The Proposed Action for this Environmental Assessment (EA) includes structural modifications to some portions of the CMR Building which do not meet current seismic criteria for a Hazard Category 2 Facility. Also included are upgrades and improvements in building ventilation, communications, monitoring, and fire protection systems. This EA analyzes the environmental effects of construction of the proposed upgrades. The Proposed Action will have no adverse effects upon agricultural and cultural resources, wetlands and floodplains, endangered and threatened species, recreational resources, or water resources. The Proposed Action would have negligible effects on human health and transportation, and would not pose a disproportionate adverse health or environmental impact on minority or low-income populations within an 80 kilometer (50 mile) radius of the CMR Building

  18. Environmental assessment for the proposed CMR Building upgrades at the Los Alamos National Laboratory, Los Alamos, New Mexico. Final document

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-04

    In order to maintain its ability to continue to conduct uninterrupted radioactive and metallurgical research in a safe, secure, and environmentally sound manner, the US Department of Energy (DOE) proposes to upgrade the Los Alamos National Laboratory (LANL) Chemistry and Metallurgy Research (CMR) Building. The building was built in the early 1950s to provide a research and experimental facility for analytical chemistry, plutonium and uranium chemistry, and metallurgy. Today, research and development activities are performed involving nuclear materials. A variety of radioactive and chemical hazards are present. The CMR Building is nearing the end of its original design life and does not meet many of today`s design codes and standards. The Proposed Action for this Environmental Assessment (EA) includes structural modifications to some portions of the CMR Building which do not meet current seismic criteria for a Hazard Category 2 Facility. Also included are upgrades and improvements in building ventilation, communications, monitoring, and fire protection systems. This EA analyzes the environmental effects of construction of the proposed upgrades. The Proposed Action will have no adverse effects upon agricultural and cultural resources, wetlands and floodplains, endangered and threatened species, recreational resources, or water resources. The Proposed Action would have negligible effects on human health and transportation, and would not pose a disproportionate adverse health or environmental impact on minority or low-income populations within an 80 kilometer (50 mile) radius of the CMR Building.

  19. A HIGH BANDWIDTH BIPOLAR POWER SUPPLY FOR THE FAST CORRECTORS IN THE APS UPGRADE*

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Ju; Sprau, Gary

    2017-06-25

    The APS Upgrade of a multi-bend achromat (MBA) storage ring requires a fast bipolar power supply for the fast correction magnets. The key performance requirement of the power supply includes a small-signal bandwidth of 10 kHz for the output current. This requirement presents a challenge to the design because of the high inductance of the magnet load and a limited input DC voltage. A prototype DC/DC power supply utilizing a MOSFET H-bridge circuit with a 500 kHz PWM has been developed and tested successfully. The prototype achieved a 10-kHz bandwidth with less than 3-dB attenuation for a signal 0.5% of the maximum operating current of 15 amperes. This paper presents the design of the power circuit, the PWM method, the control loop, and the test results.

  20. Active Control of Power Exhaust in Strongly Heated ASDEX Upgrade Plasmas

    Science.gov (United States)

    Dux, Ralph; Kallenbach, Arne; Bernert, Matthias; Eich, Thomas; Fuchs, Christoph; Giannone, Louis; Herrmann, Albrecht; Schweinzer, Josef; Treutterer, Wolfgang

    2012-10-01

    Due to the absence of carbon as an intrinsic low-Z radiator, and tight limits for the acceptable power load on the divertor target, ITER will rely on impurity seeding for radiative power dissipation and for generation of partial detachment. The injection of more than one radiating species is required to optimise the power removal in the main plasma and in the divertor region, i.e. a low-Z species for radiation in the divertor and a medium-Z species for radiation in the outer core plasma. In ASDEX Upgrade, a set of robust sensors, which is suitable to feedback control the radiated power in the main chamber and the divertor as well as the electron temperature at the target, has been developed. Different feedback schemes were applied in H-mode discharges with a maximum heating power of up to 23,W, i.e. at ITER values of P/R (power per major radius) to control all combinations of power flux into the divertor region, power flux onto the target or electron temperature at the target through injection of nitrogen as the divertor radiator and argon as the main chamber radiator. Even at the highest heating powers the peak heat flux density at the target is kept at benign values. The control schemes and the plasma behaviour in these discharges will be discussed.

  1. OVERVIEW OF A RECONFIGURABLE SIMULATOR FOR MAIN CONTROL ROOM UPGRADES IN NUCLEAR POWER PLANTS

    Energy Technology Data Exchange (ETDEWEB)

    Ronald L. Boring

    2012-10-01

    This paper provides background on a reconfigurable control room simulator for nuclear power plants. The main control rooms in current nuclear power plants feature analog technology that is growing obsolete. The need to upgrade control rooms serves the practical need of maintainability as well as the opportunity to implement newer digital technologies with added functionality. There currently exists no dedicated research simulator for use in human factors design and evaluation activities for nuclear power plant modernization in the U.S. The new research simulator discussed in this paper provides a test bed in which operator performance on new control room concepts can be benchmarked against existing control rooms and in which new technologies can be validated for safety and usability prior to deployment.

  2. HOW ECOLOGICAL ENGINEERING HELPED TO CONTINUE BUILDING AND UPGRADE OF THE OPOLE POWER PLANT

    Directory of Open Access Journals (Sweden)

    Jan Siuta

    2016-09-01

    Full Text Available Principles of ecological engineering were applied for upgrading the Opole Power Plant under construction, complete with modern installation to protect the environment. The modernized project was a subject of „Integrated environmental impact assessment of the Opole Power Plant” developed by the Institute of Environmental Protection in 1981. The main issues covered by the impact assessment were presented and discussed at the national scientific conference attended, among others, by the representatives of local community from Opole. The conference was organized by the Polish Society of Ecological Engineering on June 5 and 6, 1992. The main aim of the conference was to identify and deliver as broad as possible analysis of environmental conditions for designing, building and operating coal fired power plants. A secondary goal, though of main concern for the Opole agglomeration, was to evaluate many-sided environmental risks resulting from the construction and operation of the Power Plant. The feasibility of continuing the construction of a power generating facility that meets the requirements of the 21st century was demonstrated by the fact that the Opole Power Plant S.A. was awarded the ISO 14001 - Environmental Management System certificate by the British Standards Institution. Advanced construction of the two consecutive blocks of a combined power of 1800 MW in the Opole Power Plant substantiates the validity and effectiveness of the conference organized in 1992.

  3. Proposal for the award of a contract for the upgrade of clean and waste water systems for the LHC

    CERN Document Server

    2003-01-01

    This document concerns the award of a contract for the upgrade of clean and waste water systems for the LHC. Following a market survey carried out among 61 firms in thirteen Member States, a call for tenders (IT-3176/ST/LHC) was sent on 28 May 2003 to four firms and four consortia in six Member States. By the closing date, CERN had received six tenders from two firms and four consortia in five Member States. The Finance Committee is invited to agree to the negotiation of a contract with ABB (CH), the lowest bidder, for the upgrade of clean and waste water systems for the LHC for a total amount of 920 000 Swiss francs, not subject to revision. The firm has indicated the following distribution by country of the contract value covered by this adjudication proposal: DE - 35%; FR - 31%; CH - 17%; SE - 13%; DK - 4%.

  4. A proposed strategy for upgrade of the ORNL Process Wastewater Treatment Plant

    International Nuclear Information System (INIS)

    Kent, T.E.; Robinson, S.M.; Scott, C.B.

    1990-01-01

    An approach to the upgrade of the radiological Process Wastewater Treatment Plant (PWTP) at Oak Ridge National Laboratory (ORNL) has been developed that, if adopted, will result in significant cost reductions and improved water quality. The strategy described in this report satisfies the short-term upgrade needs of the PWTP and ultimately results in replacement of existing PWTP softening/ion- exchange technology with a zeolite molecular sieve treatment system for removal of radioactive contaminants from process wastewater. Use of zeolites will improve wastewater quality while reducing operating and disposal costs. The zeolite system would be constructed adjacent to the site now occupied by the Non-Radiological Process Wastewater Treatment Plant (NRWTP), thereby consolidating all process wastewater treatment systems at one location. 4 refs., 4 figs

  5. A proposed strategy for upgrade of the ORNL process wastewater treatment plant

    International Nuclear Information System (INIS)

    Kent, T.E.; Robinson, S.M.; Scott, C.B.

    1990-01-01

    This paper reports on an approach to the upgrade of the radiological Process Wastewater Treatment Plant (PWTP) at Oak Ridge National Laboratory (ORNL), which has been developed and that, if adopted, will result in significant cost reductions and improved water quality. The strategy described in this report satisfies the short-term upgrade needs of the PWTP and ultimately results in replacement of existing PWTP softening/ion-exchange technology with a zeolite molecular sieve treatment system for removal of radioactive contaminants from process wastewater. Use of zeolites will improve wastewater quality while reducing operating and disposal costs. The zeolite system would be constructed adjacent to the site now occupied by the Non-Radiological Process Wastewater Treatment Plant (NRWTP), thereby consolidating all process wastewater treatment systems at one location

  6. Upgrade of KNPEC no.2 Simulator for Kori Unit 3 Power Uprating

    Energy Technology Data Exchange (ETDEWEB)

    Hong, Jin-Hyuk; Lee, Seung-Ho [KEPRI, Daejeon (Korea, Republic of)

    2007-07-01

    Kori-Unit 3 and 4 is preparing the operation of the power-uprating (2900MWt), and therefore the Korea regulatory body(KINS) requested the operator training with the simulator reflecting the power-uprating. As a result of the intensive research and expertise of KEPRI on the simulators, KEPRI accomplished the upgrade project of KNPEC no.2 simulator for Kori-Unit 3 power-uprating. This project includes various high-tech methods incorporating - realtime neutronics model based on MASTER (Multi-purpose Analyzer for Static and Transient Effects of Reactors) code, best-estimate neutronics code by the KINS, (By using the RMASTER, the precision of the simulation of the neutron behaviors in the core is highly improved.) - betterment of the reactor coolant system and the balance-of-plant system - modification of the corresponding setpoints due to the power-uprating And the acceptance test procedure (ATP) was successfully carried out through the integration of system models and its performance tests. Through the success of this project, the operator training for the power uprating of the Kori-Unit 3 will be accomplished before its power operation and, after all, this simulator will contribute to the safe operation for the power-uprating of the Kori-Unit 3 and 4.

  7. New drive converter and digital control for the pulsed power supply system of ASDEX Upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Käsemann, Claus-Peter, E-mail: c.p.kaesemann@ipp.mpg.de [Max Planck Institute for Plasma Physics, Boltzmannstraße 2, 85748 Garching (Germany); Jacob, Christian; Nguyen, Hong Ha; Stobbe, Ferdinand; Mayer, Alois [Max Planck Institute for Plasma Physics, Boltzmannstraße 2, 85748 Garching (Germany); Sachs, Edgar; Klein, Reiner [Siemens AG, Industrial Automation Systems, Gleiwitzer Straße 555, 90475 Nürnberg (Germany)

    2015-10-15

    Highlights: • IGBT converter system with integrated control. • Proven technology reduces time and budget. • Flexibility to be integrated into a 35 years old installation. • Stable control algorithms for static and dynamic speed control. • Possibilities for active and reactive power management. - Abstract: Safety and reliability are major issues for the ASDEX Upgrade (AUG) pulsed power supply systems. To avoid long downtimes during an experimental campaign, fault-prone components have to be identified and treated early. This becomes even more important due to the AUG participation in the EUROfusion Medium Sized Tokamak (MST) program. Operating equipment which is up to 40 years old adds additional complications. This contribution describes one such example where a 35 year old flywheel generator at AUG was identified as fault-prone and pre-emptively upgraded with a new drive converter with integrated control. Most challenging was to adapt a modern converter, originally designed for wind turbines, toward a drive system for a flywheel-motor-generator system. To identify the layout of the controller and the control parameters, accurate modeling and comprehensive simulations were performed. This effort paid off during commissioning and measuring results verified the calculated design values. Finally, the system shows good performance during AUG plasma experiments.

  8. Lessons learned in digital upgrade projects digital control system implementation at US nuclear power stations

    International Nuclear Information System (INIS)

    Kelley, S.; Bolian, T. W.

    2006-01-01

    AREVA NP has gained significant experience during the past five years in digital upgrades at operating nuclear power stations in the US. Plants are seeking modernization with digital technology to address obsolescence, spare parts availability, vendor support, increasing age-related failures and diminished reliability. New systems offer improved reliability and functionality, and decreased maintenance requirements. Significant lessons learned have been identified relating to the areas of licensing, equipment qualification, software quality assurance and other topics specific to digital controls. Digital control systems have been installed in non safety-related control applications at many utilities within the last 15 years. There have also been a few replacements of small safety-related systems with digital technology. Digital control systems are proving to be reliable, accurate, and easy to maintain. Digital technology is gaining acceptance and momentum with both utilities and regulatory agencies based upon the successes of these installations. Also, new plants are being designed with integrated digital control systems. To support plant life extension and address obsolescence of critical components, utilities are beginning to install digital technology for primary safety-system replacement. AREVA NP analyzed operating experience and lessons learned from its own digital upgrade projects as well as industry-wide experience to identify key issues that should be considered when implementing digital controls in nuclear power stations

  9. Cost-effective instrumentation and control upgrades for commercial nuclear power plants surety principles developed at Sandia National Laboratories

    International Nuclear Information System (INIS)

    Rochau, G.E.; Dalton, L.J.

    1998-01-01

    Many nuclear power plants use instrument and control systems based on analog electronics. The state of the art in process control and instrumentation has advanced to use digital electronics and incorporate advanced technology. This technology includes: distributed microprocessors, fiber optics, intelligent systems (neutral networks), and advanced displays. The technology is used to optimize processes and enhance the man-machine interface while maintaining control and safety of the processes. Nuclear power plant operators have been hesitant to install this technology because of the cost and uncertainty in the regulatory process. This technology can be directly applied in an operating nuclear power plant provided a surety principle-based 'administrator' hardware system is included in parallel with the upgrade. Sandia National Laboratories has developed a rigorous approach to High Consequence System Surety (HCSS). This approach addresses the key issues of safety, security, and control while satisfying requirements for reliability and quality. We believe that HCSS principles can be applied to nuclear power plants in a manner that allows the off-the-shelf use of process control instrumentation while maintaining a high level of safety and enhancing the plant performance. We propose that an HCSS Administrator be constructed as a standardized approach to address regulatory issues. Such an administrator would allow a plant control system to be constructed with commercially available, state-to-the-art equipment and be customized to the needs of the individual plant operator. (author)

  10. Cost-effective instrumentation and control upgrades for commercial nuclear power plants using surety principles developed at Sandia National Laboratories

    International Nuclear Information System (INIS)

    Rochau, G.E.; Dalton, L.J.

    1997-01-01

    Many nuclear power plants use instrument and control systems based on analog electronics. The state of the art in process control and instrumentation has advanced to use digital electronics and incorporate advanced technology. This technology includes distributed microprocessors, fiber optics, intelligent systems (neural networks), and advanced displays. The technology is used to optimize processes and enhance the man-machine interface while maintaining control and safety of the processes. Nuclear power plant operators have been hesitant to install this technology because of the cost and uncertainty in the regulatory process. This technology can be directly applied in an operating nuclear power plant provided a surety principle-based open-quotes administratorclose quotes hardware system is included in parallel with the upgrade Sandia National Laboratories has developed a rigorous approach to High Consequence System Surety (HCSS). This approach addresses the key issues of safety, security, and control while satisfying requirements for reliability and quality. HCSS principles can be applied to nuclear power plants in a manner that allows the off-the-shelf use of process control instrumentation while maintaining a high level of safety and enhancing the plant performance. We propose that an HCSS administrator be constructed as a standardized approach to address regulatory issues. Such an administrator would allow a plant control system to be constructed with commercially available, state-of-the-art equipment and be customized to the needs of the individual plant operator

  11. Multistage and multiobjective formulations of globally optimal upgradable expansions for electric power distribution systems

    Science.gov (United States)

    Vaziri Yazdi Pin, Mohammad

    Electric power distribution systems are the last high voltage link in the chain of production, transport, and delivery of the electric energy, the fundamental goals of which are to supply the users' demand safely, reliably, and economically. The number circuit miles traversed by distribution feeders in the form of visible overhead or imbedded underground lines, far exceed those of all other bulk transport circuitry in the transmission system. Development and expansion of the distribution systems, similar to other systems, is directly proportional to the growth in demand and requires careful planning. While growth of electric demand has recently slowed through efforts in the area of energy management, the need for a continued expansion seems inevitable for the near future. Distribution system and expansions are also independent of current issues facing both the suppliers and the consumers of electrical energy. For example, deregulation, as an attempt to promote competition by giving more choices to the consumers, while it will impact the suppliers' planning strategies, it cannot limit the demand growth or the system expansion in the global sense. Curiously, despite presence of technological advancements and a 40-year history of contributions in the area, many of the major utilities still relay on experience and resort to rudimentary techniques when planning expansions. A comprehensive literature review of the contributions and careful analyses of the proposed algorithms for distribution expansion, confirmed that the problem is a complex, multistage and multiobjective problem for which a practical solution remains to be developed. In this research, based on the 15-year experience of a utility engineer, the practical expansion problem has been clearly defined and the existing deficiencies in the previous work identified and analyzed. The expansion problem has been formulated as a multistage planning problem in line with a natural course of development and industry

  12. Proposal of upgrade of the ATLAS muon trigger in the barrel-endcap transition region with RPCs

    CERN Document Server

    Massa, L; The ATLAS collaboration

    2014-01-01

    This report presents a project for the upgrade of the Level-1 muon trigger in the barrel-endcap transition region (1.01) caused by charged particles originating from secondary interactions downstream of the interaction point. After the LHC upgrade forseen for 2018, the Level-1 muon trigger rate would saturate the allocated bandwidth unless new measures are adopted to improve the rejection of fake triggers. ATLAS is going to improve the trigger selectivity in the region |$\\eta$|>1.3 with the New Small Wheel detector upgrade. To obtain a similar trigger selectivity in the barrel-endcap transition region, it is proposed to add new RPC chambers at the edge of the inner layer of the barrel muon spectrometer. These chambers will be based on a three layer structure with thinner gas gaps and electrodes with respect to the ATLAS standard and a new low-profile light-weight mechanical structure that will allow the installation in the limited available space. New front-end electronics, integrating fast TDC capabilities w...

  13. A Proposal to upgrade KREM with respect to Scale and Code Deficiency

    International Nuclear Information System (INIS)

    Lee, Sang Yong

    2015-01-01

    In this paper, it is shown that the EDC process can be formulated with respect to the scaled system uncertainty quantification. The second suggestion is concerning the bias due to the scale deficiency related with the multi-dimensional effect. A proposal to extend KREM to have multi-dimensional capability is made so that the related bias can be removed. Korea Realistic Evaluation Model (KREM) basically follows Code Scale Applicability and Uncertainty (CSAU) methodology (Fig.1 and 2). Since KREM was approved by the Korean authority in 2002, it has been applied to support several important domestic and foreign projects such as APR-1400(Advanced Power Reactor) design, APR-1400 export to United Arab Emirates (UAE) and U.S. NRC design certification of APR-1400. Encouraged by these activities, I would like to propose some suggestions to modify and improve KREM. The first suggestion is related with the Experimental Data Covering (EDC) process (Fig.2). The terminology SSUQ is introduced to replace the term EDC in KREM to naturally include the operational parameters. COBRA-TF is strongly recommended to handle the multi-dimensional phenomena in the improved KREM

  14. Constructing an I and C Upgrade Architecture for Korea Standard Nuclear Power Plants

    International Nuclear Information System (INIS)

    Suh, Yong Suk; Hur, Seop; Kim, Dong Hoon; Sung, Chan Ho; Kang, Hyun Tai; Lee, Jae Ki; Cho, Chang Hwan

    2008-01-01

    This paper presents three architectures of the KSNP I and C upgrade. The architectures are constructed with an adoption of PLCs and DCS technology and 3-phase upgrade strategy. The 3-phase upgrade strategy is established to ensure the safety of the upgrade. Based on the architecture, the cabinet configuration is being constructed. From the configuration, it is expected to figure out how to optimize the layout of the cabinets. It is required to study the performance and safety design requirements of the upgrade further

  15. A new algorithm to determine the total radiated power at ASDEX upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Gloeggler, Stephan; Bernert, Matthias; Eich, Thomas [Max Planck Institute for Plasma Physics, Boltzmannstr. 2, 85748 Garching (Germany); Collaboration: The ASDEX Upgrade Team

    2016-07-01

    Radiation is an essential part of the power balance in a fusion plasma. In future fusion devices about 90% of the power will have to be dissipated, mainly by radiation. For the development of an appropriate operational scenario, information about the absolute level of plasma radiation (P{sub rad,tot}) is crucial. Bolometers are used to measure the radiated power, however, an algorithm is required to derive the absolute power out of many line-integrated measurements. The currently used algorithm (BPD) was developed for the main chamber radiation. It underestimates the divertor radiation as its basic assumptions are not satisfied in this region. Therefore, a new P{sub rad,tot} algorithm is presented. It applies an Abel inversion on the main chamber and uses empirically based assumptions for poloidal asymmetries and the divertor radiation. To benchmark the new algorithm, synthetic emissivity profiles are used. On average, the new Abel inversion based algorithm deviates by only 10% from the nominal synthetic value while BPD is about 25% too low. With both codes time traces of ASDEX Upgrade discharges are calculated. The analysis of these time traces shows that the underestimation of the divertor radiation can have significant consequences on the accuracy of BPD while the new algorithm is shown to be stable.

  16. Thyristor crowbar system for the high current power supplies of ASDEX upgrade

    International Nuclear Information System (INIS)

    Kaesemann, C.-P.; Lieshout, L. van; Huart, M.; Sihler, C.

    2005-01-01

    The ohmic heating system and the poloidal field coils of ASDEX upgrade are supplied by 15 thyristor converter units with an installed apparent power of 600 MVA. To protect the thyristor converters against dc overvoltage arising from abnormal operations and resulting damages caused by the large energy stored in the AUG magnet coils an overvoltage protection system was required. The paper describes the motivation for-and the design and testing of the thyristor crowbar system representing the thyristor converter overvoltage protection system. It will present the layout, analyse the results of measurements obtained during commissioning, compare them to the calculated (design) values and report on the first experience of operation on the AUG coils improving the safety of the equipment

  17. Autothermal upgrading of biomass and wastes for clean and efficient production of power

    Energy Technology Data Exchange (ETDEWEB)

    Rafal Kobylecki; Zbigniew Bis; Wojciech Nowak [Czestochowa University of Technology (Poland)

    2005-07-01

    In this paper it is demonstrated that the main barrier of large scale heat and electricity production from biomass may be significantly reduced or eliminated by fuel upgrading and thermal treatment in a specially-designed pilot plant autothermal reactor. The process does not require significant amount of additional energy, since the whole process is run autothermal. The process final products are hot flue gases and a solid residue called a 'biocarbon' of LHV of roughly 28 MJ/kg. The properties of the biocarbon were similar, regardless of the input raw fuel type (biomass, waste, sewage sludge, energy crops, etc.). The use of the biocarbon for direct co-combustion with coal does not require installation of any additional feeding or fuel treatment systems at the power plants. Apart from its possible direct combustion, the biocarbon can be also efficiently used as a promising solid energy carrier for other processes (e.g. fuel cells). 6 refs., 6 figs.

  18. Experiences with the upgraded SKP system during refuelling Paks nuclear power plant

    International Nuclear Information System (INIS)

    Baranyai, A.; Hetzmann, A.

    1997-01-01

    In order to control the neutron flux during the refueling period, new measuring chains were developed and put into operation by the experts of KFKI-RegTron Co., Ltd. and the Paks Nuclear Power Plant with the purpose of partially substituting the original Refuelling Neutron Monitoring system (SKP) of WWER-440 reactor units. The modified monitoring system processes the signals of detectors located in channels outside the core. The outputs of measurement amplifiers equipped with up-to-date electronics fit in the original system perfectly. Use of the out-of-core measuring technique confirmed the preliminary expectations: interference sensitivity has decreased, the neutron/gamma ration increased and refueling time has become shorter by one to one-and-a-half day. The paper details the reasons for upgrading, the essence of utilized solutions and the operational experience. (author)

  19. Data acquisition and PV module power production in upgraded TEP/AzRISE solar test yard

    Science.gov (United States)

    Bennett, Whit E.; Fishgold, Asher D.; Lai, Teh; Potter, Barrett G.; Simmons-Potter, Kelly

    2017-08-01

    The Tucson Electric Power (TEP)/University of Arizona AzRISE (Arizona Research Institute for Solar Energy) solar test yard is continuing efforts to improve standardization and data acquisition reliability throughout the facility. Data reliability is ensured through temperature-insensitive data acquisition devices with battery backups in the upgraded test yard. Software improvements allow for real-time analysis of collected data, while uploading to a web server. Sample data illustrates high fidelity monitoring of the burn-in period of a polycrystalline silicon photovoltaic module test string with no data failures over 365 days of data collection. In addition to improved DAQ systems, precision temperature monitoring has been implemented so that PV module backside temperatures are routinely obtained. Weather station data acquired at the test yard provides local ambient temperature, humidity, wind speed, and irradiance measurements that have been utilized to enable characterization of PV module performance over an extended test period

  20. Upgrade of the SLAC SLED II Pulse Compression System Based on Recent High Power Tests

    International Nuclear Information System (INIS)

    Vlieks, A.E.; Fowkes, W.R.; Loewen, R.J.; Tantawi, S.G.

    2011-01-01

    the key components of SLED-II; the Magic Tee and the 'Flower Petal' mode converter (converts between TE 10 rectangular and TE 01 circular modes), were not robust enough at higher power levels. Because of this, a major effort is underway to upgrade the existing devices to operate stably at the higher power levels, and also to investigate new components, which have inherently low field enhancement in their design and therefore more robust.

  1. Upgrading Planning and Executive Strategy for Reactor Protection System and Relative Equipment in Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Jiang Zuyue

    2010-01-01

    Qinshan Nuclear Power Plant (QNPP) is the first nuclear power plant in China which completed the reactor protection system (RPS) upgrading with new digital safety instrumentation and control (I and C) platform instead of original analog system. At the same time,the nuclear instrumentation system (NIS) was upgraded with the same digital I and C platform. For adapting QNPP's actual engineering situation,the upgrading planning was taken by comprehensively investigating current development and application of digital safety I and C platform in the worldwide scope and by reviewing plant's original systems operation history. The project executive strategy-QNPP's leading role with necessary overseas cooperation and internal technical supports as great as possible, was determined. Some significant factors might influence and restrict the RPS and relative equipment upgrading executive actions in an operating NPP were analyzed.Finally, the engineering feasibility was briefly assessed to recognize the anticipated issues and difficulties and to prepare the relative solutions in advance for the purpose of ensuring the RPS upgrading objectives completely realized. (authors)

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

    International Nuclear Information System (INIS)

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

    2017-01-01

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

  3. Armenian nuclear power plant: US NRC assistance programme for seismic upgrade and safety analysis

    International Nuclear Information System (INIS)

    Simos, N.; Perkins, K.; Jo, J.; Carew, J.; Ramsey, J.

    2003-01-01

    This paper summarizes the U.S. Nuclear Regulatory Commission's (US NRC) technical support program activities associated with the Armenian Nuclear Power Plant (ANPP) safety upgrade. The US NRC program, integrated within the overall IAEA-led initiative for safety re-evaluation of the WWER plants, has as its main thrust the technical support to the Armenian Nuclear Regulatory Authority (ANRA) through close collaboration with the scientific staff at Brookhaven National Laboratory (BNL). Several major technical areas of support to ANRA form the basis of the NRC program. These include the seismic re-evaluation and upgrade of the ANPP, safety evaluation of critical systems, and the generation of the Safety Analysis Report (SAR). Specifically, the seismic re-evaluation of the ANPP is part of a broader activity that involves the re-assessment of the seismic hazard at the site, the identification of the Safe Shutdown Equipment at the plant and the evaluation of their seismic capacity, the detailed modeling and analysis of the critical facilities at ANPP, and the generation of the Floor Response Spectra (FRS). Based on the new spectra that incorporate all new findings (hazard, site soil, structure, etc.), the overall capacity of the main structures and the seismic capacity of the critical systems are being re-evaluated. In addition, analyses of critical safe shutdown systems and safe shutdown processes are being performed to ensure both the capabilities of the operating systems and the enhancement of safety due to system upgrades. At present, one of the principal goals of the US NRC's regulatory assistance activities with ANRA is enhancing ANRA's regulatory oversight of high-priority safety issues (both generic and plant-specific) associated with operation of the ANPP. As such, assisting ANRA in understanding and assessing plant-specific seismic and other safety issues associated with the ANPP is a high priority given the ANPP's being located in a seismically active area

  4. European type NPP electric power and vent systems. For safety improvement and proposal of international center

    International Nuclear Information System (INIS)

    Sugiyama, Kenichiro

    2011-01-01

    For prevention of reactor accidents of nuclear power plants, multiplicity and redundancy of emergency power would be most important. At station blackout accident, European type manually operated vent operation could minimize release amount of radioactive materials and keep safety of neighboring residents. After Fukushima Daiichi accident, nuclear power plants could not restart operation even after completion of periodical inspection. This article introduced European type emergency power and vent systems in Swiss, Sweden and Germany with state of nuclear power phaseout for reference at considering to upgrade safety and accident mitigation measures for better understanding of the public. In addition, it would be important to recover trust of nuclear technology to continue to disseminate latest information on new knowledge of accident site and decontamination technologies to domestic and overseas people. As its implementation, establishment of Fukushima international center was proposed. (T. Tanaka)

  5. Seismic analysis of two 1050 mm diameter heavy water upgrading towers for 235 MWe Kaiga Atomic Power Plant Site

    International Nuclear Information System (INIS)

    Soni, R.S.; Kushwaha, H.S.; Mahajan, S.C.; Kakodkar, A.; Narwaria, Suresh; Vardarajan, T.G.; Sadhukhan, H.K.

    1992-01-01

    This report deals with the analysis carried out for the evaluation of earthquake induced stresses and deflections in two 1050 mm diameter heavy water upgrading towers for Kaiga Atomic Power Plant Site. The analysis of upgrading tower has been carried out for two mutually perpendicular horizontal excitations and one vertical excitation applied simultaneously. The upgrading towers have been analysed using beam model taking into account soil-structure interaction. Response spectrum analysis has been carried out using site spectra for 235 MWe Kaiga reactor site. The seismic analysis has been performed for both the towers with supporting structure along with concrete pedestals and raft foundation. The towers have been checked for its stability due to compressive stresses to avoid buckling so that the nearby safety related structures are not geopardised in the event of safe shutdown earthquake (SSE) loading. (author). 14 refs., 12 figs., 18 tabs

  6. Mechanical braking system for the pulsed power supply system of ASDEX Upgrade

    International Nuclear Information System (INIS)

    Käsemann, C.-P.; Huart, M.; Stobbe, F.; Goldstein, I.; Sigalov, A.; Sachs, E.; Perk, E.

    2013-01-01

    Highlights: ► Compact and innovative solution for dumping of large kinetic energy. ► Small mass of energy converter at the shaft due to circulating storage medium. ► Design of the active parts ensures flat torque/power characteristics. ► Also suitable for spending a great part of operating life in “Freewheeling” mode. -- Abstract: A few years ago, IPP reviewed the safety of the ASDEX Upgrade pulsed power supply system. Two critical sub-systems had been identified: The (electrical) braking system for the flywheel generators and the oil lubrication system for the shaft bearings. A simultaneous failure of these two systems may lead to severe damages and could have consequences for the safety of operating personnel. Therefore a second, independent braking possibility for every generator was stipulated. Especially the challenges adapting a dynamometer, originally designed for motor test benches, towards a plant safety system for generator EZ4 will be described in the paper. Further on, the paper will present the problems, implementing such a system into an existing installation, including the calculation of the required supporting structure, balancing of the extended shaft line and required water cooling and control. Finally it will report on the performance achieved during operation

  7. Ion cyclotron resonance heating systems upgrade toward high power and CW operations in WEST

    Energy Technology Data Exchange (ETDEWEB)

    Hillairet, Julien, E-mail: julien.hillairet@cea.fr; Mollard, Patrick; Bernard, Jean-Michel; Argouarch, Arnaud; Berger-By, Gilles; Charabot, Nicolas; Colas, Laurent; Delaplanche, Jean-Marc; Ekedahl, Annika; Fedorczak, Nicolas; Ferlay, Fabien; Goniche, Marc; Hatchressian, Jean-Claude; Helou, Walid; Jacquot, Jonathan; Joffrin, Emmanuel; Litaudon, Xavier; Lombard, Gilles; Magne, Roland; Patterlini, Jean-Claude [CEA, IRFM, F-13108 Saint Paul-lez-Durance (France); and others

    2015-12-10

    The design of the WEST (Tungsten-W Environment in Steady-state Tokamak) Ion cyclotron resonance heating antennas is based on a previously tested conjugate-T Resonant Double Loops prototype equipped with internal vacuum matching capacitors. The design and construction of three new WEST ICRH antennas are being carried out in close collaboration with ASIPP, within the framework of the Associated Laboratory in the fusion field between IRFM and ASIPP. The coupling performance to the plasma and the load-tolerance have been improved, while adding Continuous Wave operation capability by introducing water cooling in the entire antenna. On the generator side, the operation class of the high power tetrodes is changed from AB to B in order to allow high power operation (up to 3 MW per antenna) under higher VSWR (up to 2:1). Reliability of the generators is also improved by increasing the cavity breakdown voltage. The control and data acquisition system is also upgraded in order to resolve and react on fast events, such as ELMs. A new optical arc detection system comes in reinforcement of the V{sub r}/V{sub f} and SHAD systems.

  8. Mechanical braking system for the pulsed power supply system of ASDEX Upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Käsemann, C.-P., E-mail: c.p.kaesemann@ipp.mpg.de [Max Planck Institute for Plasma Physics, EURATOM Association, Boltzmannstr. 2, 85748 Garching (Germany); Huart, M. [Max Planck Institute for Plasma Physics, EURATOM Association, Boltzmannstr. 2, 85748 Garching (Germany); Michel Huart Personal Coaching and Consulting, Georgenschwaigstraße 23 RG, 80807 München (Germany); Stobbe, F.; Goldstein, I.; Sigalov, A. [Max Planck Institute for Plasma Physics, EURATOM Association, Boltzmannstr. 2, 85748 Garching (Germany); Sachs, E. [Siemens AG, Industrial Automation Systems, Gleiwitzer Straße 555, 90475 Nürnberg (Germany); Perk, E. [Piper Test and Measurement Ltd., The Barn, Bilsington, Ashford, Kent TN25 7JT, England (United Kingdom)

    2013-10-15

    Highlights: ► Compact and innovative solution for dumping of large kinetic energy. ► Small mass of energy converter at the shaft due to circulating storage medium. ► Design of the active parts ensures flat torque/power characteristics. ► Also suitable for spending a great part of operating life in “Freewheeling” mode. -- Abstract: A few years ago, IPP reviewed the safety of the ASDEX Upgrade pulsed power supply system. Two critical sub-systems had been identified: The (electrical) braking system for the flywheel generators and the oil lubrication system for the shaft bearings. A simultaneous failure of these two systems may lead to severe damages and could have consequences for the safety of operating personnel. Therefore a second, independent braking possibility for every generator was stipulated. Especially the challenges adapting a dynamometer, originally designed for motor test benches, towards a plant safety system for generator EZ4 will be described in the paper. Further on, the paper will present the problems, implementing such a system into an existing installation, including the calculation of the required supporting structure, balancing of the extended shaft line and required water cooling and control. Finally it will report on the performance achieved during operation.

  9. Experiences in seismic upgrading of equipment and structures in Kozloduy nuclear power plant (440 WWER-PWR)

    International Nuclear Information System (INIS)

    Ordonez Villalobos, A.

    1993-01-01

    Within the framework of the 'Emergency programme for Nuclear Safety of Kozloduy NPP' it has been concluded that the increase in seismic safety of a NPP can be achieved by upgrading the key equipment in a cost effective way. Essential and vulnerable equipment has to be identified. Seismic capacity should be evaluated base don realistic state of the art criteria. Seismic review teams ef experienced engineers should conduct planned walk-downs in order to propose effective upgrading solutions. Team work of plan engineers and construction engineers would enhance the effectiveness of the solutions. It is recommended that all the participants be motivated and have a clear understanding of the objectives of the upgrading

  10. Research on real-time simulation test for upgrades of digital I and C system in nuclear power plant

    International Nuclear Information System (INIS)

    Shi Ji; Jiang Mingyu; Ma Yunqin

    2005-01-01

    The developing trend that digital instrument and control (I and C) system will supplant traditional analog I and C system in nuclear power plant is emphasized. This paper introduces mathematical model of steam generator of full scope simulator for nuclear power plant. The independent real-time simulation system, which forms the interactive closed loop together with the steam generator control system, can be applied to provide a simulation target for upgrades of instrument and control system and the research of control schemes. At the same time, a simulation method for this purpose is presented in this paper. In this method all of the hardware and software are composed of real distributed control system except the model of controlled object. This will not only create favorable conditions for commissioning on site in the future, but also give a theoretical analysis for upgrades of digital I and C system in nuclear power plant. (authors)

  11. The Proposed 2009 War Powers Consultation Act

    Science.gov (United States)

    2009-03-19

    both political branches of government participate in matters of national security. 15. SUBJECT TERMS Separation of Powers , National Security Law...Strategy Research Project DATE: 19 March 2009 WORD COUNT: 8,090 PAGES: 46 KEY TERMS: Separation of Powers , National Security Law, Constitution...Arthur Bestor, “ Separation of Powers in the Domain of Foreign Affairs: The Intent of the Constitution Historically Examined,” Seton Hall L. Rev. 5 (1974

  12. RF Power Detector/Monitor Upgrade for the 500MHz Systems at the ALS

    International Nuclear Information System (INIS)

    Baptiste, K.

    2003-01-01

    Several systems rely on the accurate and linear detection of 500 MHz signals, (the fundamental frequency of both the Booster Ring and Storage Ring) over a dynamic range in excess of 25dB. Prior to this upgrade, the detector/monitor was diode based and though this type of detector could handle the dynamic range requirement it could not do so in an accurate and linear manner. In order to meet the requirements (dynamic range greater than or equal to 25dB, accurate and linear to +-0.25dB over the range, and additional circuitry to interface to the legacy control system and interlocks), a new RF Power Detector/Monitor has been developed using two AD8361, Analog Devices Tru RMS Detectors and a fuzzy comparator, which extends the overall detector's range to twice that of the AD8361. Further information is available [www.analogedevices.com/]. Details of the design requirements and the detector/monitor's circuit as well as the performance of the detector will be presented

  13. Optimized tokamak power exhaust with double radiative feedback in ASDEX Upgrade

    Science.gov (United States)

    Kallenbach, A.; Bernert, M.; Eich, T.; Fuchs, J. C.; Giannone, L.; Herrmann, A.; Schweinzer, J.; Treutterer, W.; the ASDEX Upgrade Team

    2012-12-01

    A double radiative feedback technique has been developed on the ASDEX Upgrade tokamak for optimization of power exhaust with a standard vertical target divertor. The main chamber radiation is measured in real time by a subset of three foil bolometer channels and controlled by argon injection in the outer midplane. The target heat flux is in addition controlled by nitrogen injection in the divertor private flux region using either a thermoelectric sensor or the scaled divertor radiation obtained by a bolometer channel in the outer divertor. No negative interference of the two radiation controllers has been observed so far. The combination of main chamber and divertor radiative cooling extends the operational space of a standard divertor configuration towards high values of P/R. Pheat/R = 14 MW m-1 has been achieved so far with nitrogen seeding alone as well as with combined N + Ar injection, with the time-averaged divertor peak heat flux below 5 MW m-2. Good plasma performance can be maintained under these conditions, namely H98(y,2) = 1 and βN = 3.

  14. Applying wind turbines and battery storage to defer Orcas Power and Light Company distribution circuit upgrades

    International Nuclear Information System (INIS)

    Zaininger, H.W.; Barnes, P.R.

    1997-03-01

    The purpose of this study is to conduct a detailed assessment of the Orcas Power and Light Company (OPALCO) system to determine the potential for deferring the costly upgrade of the 25-kV Lopez- Eastsound circuit, by the application of a MW-scale wind farm and battery storage facilities as appropriate. Local wind resource data has been collected over the past year and used to determine MW-scale wind farm performance. This hourly wind farm performance data is used with measured hourly Eastsound load data, and recent OPALCO distribution system expansion plans and cost projections in performing this detailed benefit-cost assessment. The OPALCO distribution circuit expansion project and assumptions are described. MW-scale wind farm performance results are given. The economic benefit-cost results for the wind farm and battery storage applications on the OPALCO system using OPALCO system design criteria and cost assumptions are reported. A recalculation is presented of the benefit-cost results for similar potential wind farm and battery storage applications on other utility systems with higher marginal energy and demand costs. Conclusions and recommendations are presented. costs. Conclusions and recommendations are presented

  15. Development of a serial powering scheme and a versatile characterization system for the ATLAS pixel detector upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Filimonov, Viacheslav

    2017-08-15

    In order to increase the probability of new discoveries the LHC will be upgraded to the HL-LHC. The upgrade of the ATLAS detector is an essential part of this program. The entire ATLAS tracking system will be replaced by an all-silicon detector called Inner Tracker (ITk) which should be able to withstand the increased luminosity of 5 x 10{sup 34} cm{sup -2}s{sup -1}. The work presented in this thesis is focused on the ATLAS ITk pixel detector upgrade. Advanced silicon pixel detectors will be an essential part of the ITk pixel detector where they will be used for tracking and vertexing. Characterization of the pixel detectors is one of the required tasks for a successful ATLAS tracker upgrade. Therefore, the work presented in this thesis includes the development of a versatile and modular test system for advanced silicon pixel detectors for the HL-LHC. The performance of the system is verified. Single and quad FE-I4 modules functionalities are characterized with the developed system. The reduction of the material budget of the ATLAS ITk pixel detector is essential for a successful operation at high luminosity. Therefore, a low mass, efficient power distribution scheme to power detector modules (serial powering scheme) is investigated as well in the framework of this thesis. A serially powered pixel detector prototype is built with all the components that are needed for current distribution, data transmission, sensor biasing, bypassing and redundancy in order to prove the feasibility of implementing the serial powering scheme in the ITk. Detailed investigations of the electrical performance of the detector prototype equipped with FE-I4 quad modules are made with the help of the developed readout system.

  16. Development of a serial powering scheme and a versatile characterization system for the ATLAS pixel detector upgrade

    International Nuclear Information System (INIS)

    Filimonov, Viacheslav

    2017-08-01

    In order to increase the probability of new discoveries the LHC will be upgraded to the HL-LHC. The upgrade of the ATLAS detector is an essential part of this program. The entire ATLAS tracking system will be replaced by an all-silicon detector called Inner Tracker (ITk) which should be able to withstand the increased luminosity of 5 x 10 34 cm -2 s -1 . The work presented in this thesis is focused on the ATLAS ITk pixel detector upgrade. Advanced silicon pixel detectors will be an essential part of the ITk pixel detector where they will be used for tracking and vertexing. Characterization of the pixel detectors is one of the required tasks for a successful ATLAS tracker upgrade. Therefore, the work presented in this thesis includes the development of a versatile and modular test system for advanced silicon pixel detectors for the HL-LHC. The performance of the system is verified. Single and quad FE-I4 modules functionalities are characterized with the developed system. The reduction of the material budget of the ATLAS ITk pixel detector is essential for a successful operation at high luminosity. Therefore, a low mass, efficient power distribution scheme to power detector modules (serial powering scheme) is investigated as well in the framework of this thesis. A serially powered pixel detector prototype is built with all the components that are needed for current distribution, data transmission, sensor biasing, bypassing and redundancy in order to prove the feasibility of implementing the serial powering scheme in the ITk. Detailed investigations of the electrical performance of the detector prototype equipped with FE-I4 quad modules are made with the help of the developed readout system.

  17. Reliability and efficiency upgrades of power systems operation by implementing intelligent electronic devices with synchrophasor measurement technology support

    Directory of Open Access Journals (Sweden)

    Mokeev Alexey

    2017-01-01

    Full Text Available This paper reviews issues of reliability and efficiency upgrades of power systems functions by means of a widespread implementation of intelligent electronic devices (IED in various purposes supporting synchrophasor measurement technology. Thus, such issues as IED’s operational analysis in the conditions of electromagnetic and electromechanical transient processes and synthesis of digital filters that improve static and dynamic responses of these devices play an important role in their development.

  18. Reliability and efficiency upgrades of power systems operation by implementing intelligent electronic devices with synchrophasor measurement technology support

    OpenAIRE

    Mokeev Alexey

    2017-01-01

    This paper reviews issues of reliability and efficiency upgrades of power systems functions by means of a widespread implementation of intelligent electronic devices (IED) in various purposes supporting synchrophasor measurement technology. Thus, such issues as IED’s operational analysis in the conditions of electromagnetic and electromechanical transient processes and synthesis of digital filters that improve static and dynamic responses of these devices play an important role in their devel...

  19. A TTC upgrade proposal using bidirectional 10G-PON FTTH technology

    Science.gov (United States)

    Kolotouros, D. M.; Baron, S.; Soos, C.; Vasey, F.

    2015-04-01

    A new generation FPGA-based Timing-Trigger and Control (TTC) system based on emerging Passive Optical Network (PON) technology is being proposed to replace the existing off-detector TTC system used by the LHC experiments. High split ratio, dynamic software partitioning, low and deterministic latency, as well as low jitter are required. Exploiting the latest available technologies allows delivering higher capacity together with bidirectionality, a feature absent from the legacy TTC system. This article focuses on the features and capabilities of the latest TTC-PON prototype based on 10G-PON FTTH components along with some metrics characterizing its performance.

  20. A TTC upgrade proposal using bidirectional 10G-PON FTTH technology

    International Nuclear Information System (INIS)

    Kolotouros, D.M.; Baron, S.; Soos, C.; Vasey, F.

    2015-01-01

    A new generation FPGA-based Timing-Trigger and Control (TTC) system based on emerging Passive Optical Network (PON) technology is being proposed to replace the existing off-detector TTC system used by the LHC experiments. High split ratio, dynamic software partitioning, low and deterministic latency, as well as low jitter are required. Exploiting the latest available technologies allows delivering higher capacity together with bidirectionality, a feature absent from the legacy TTC system. This article focuses on the features and capabilities of the latest TTC-PON prototype based on 10G-PON FTTH components along with some metrics characterizing its performance

  1. Life extension, power upgrade, and return to service work for Pickering NGS and other PWR and CANDU plants

    International Nuclear Information System (INIS)

    Millman, J.; Idvorian, N.; Schneider, W.

    2002-01-01

    Work on life extension, power upgrade and return to service has been performed and is in progress for a number of PWR and CANDU plants. For PWR plants, power upgrade work has been done for the new replacement steam generators in several cases. This work consists of redoing the formal equipment qualification analysis and reports for the uprated operating conditions to support the application for license adjustment. Life extension assessments have been performed for several CANDU plants. These are highly detailed assessments in which the particular steam generator is reassessed part by part as to the ability of each to sustain full life operation and also extended life operation. Return to service work for Pickering NGSA specifically has included this type of assessment and also specific repair, cleaning and retrofit activities including secondary side inspection, waterlancing, divider plate repair, eddy current inspection, etc. Steam generator modifications and retrofit work have been performed in a number of cases. The paper discusses various life extension, power upgrade, equipment modification and return to service activities all of which are part of the renewed drive in the industry to realise the full potential of nuclear plants by getting more and better performance from the extended service of existing plants. (author)

  2. Karachi nuclear power plant - A review of performance, problems and upgrades

    International Nuclear Information System (INIS)

    Hussain, S.B.

    1998-01-01

    KANUPP during its 23 years of operation has experienced multiple challenges in keeping the plant operating and supplying safe and economical power to the Karachi grid. The biggest challenge was faced in 1976, when the original vendor imposed unilateral embargo leading to the stoppage of supplies of essential spare-parts, nuclear fuel, heavy water and technical support. This forced KANUPP to a net, way of operating the plant which necessarily had to be based on indigenous support. Obsolescence of C and I components became evident soon after plant went into commercial operation because of explosive development and advancement in the electronic and computer technology. KANUPP was, however, able to cope with the normal maintenance and improvement of its process, mechanical and electrical equipment till 80's. However, many of the critical components are now reaching the end of their designed life and developing chronic problems due to ageing. The only technically suitable and commercially viable alternative is the complete replacement of CC and I components. KANUPP has already undertaken this job alongwith other related work under ''Technological Upgradation Project''. In order to manage ageing related degradation and carry out full scale assessment of the health of reactor fuel channels KANUPP prepared an ''Integrated Safety Master Action Plan'' and submitted it to IAEA for arranging international assistance. After intense negotiations and with the IAEA's cooperation in May 1990, Canadian policy towards KANUPP was revised allowing it to provide assistance for Safe Operation of KANUPP (SOK) through the IAEA and only for the IAEA suggested remedial actions. Work under SOK is being carried out to: Combat ageing and obsolence Problems; Modernize Operational Safety practices; Improve safety systems design. This paper describes KANUPP's efforts in overcoming different problems mentioned above

  3. Thermal-hydraulic analysis of the OSURR pool for power upgrade with natural convection core cooling

    International Nuclear Information System (INIS)

    Ha, J.J.; Aldemir, T.

    1988-01-01

    Natural convection mode core cooling will be maintained in the LEU conversion/power upgrade of The Ohio State University Research Reactor (OSURR) to 250-500 kW. The pool water will be cooled by a water-glycol-air and a water-water heat exchanger. A plume disperser will be installed in the pool to minimize evaporation from the pool top and to maintain the dose rate due to N-16 activity within allowable levels. The minimization of the pool heat removal system operation costs necessitates maximizing the inlet temperature to the water-glycol-air heat exchanger. For the maximization process, the change in the pool temperature and velocity fields have to be investigated as a function of: location and orientation of the heat removal system components and the plume disperser in the pool; mass flow rate through the plume disperser. The velocity and temperature fields in the pool are determined using COMMIX-1A. The computational system model accounts for the presence of all the pool components (i.e. core, thermal column, beam ports, ion chamber, guide tubes, rabbit, neutron source etc.). The results show that: (1) Both the heat removal system inlet point and the plume disperser have to be located close to the top of the core. (2) Using a disperser system consisting of several pipes may be more feasible than a single unit. (3) For high disperser flow, the disperser jet has to be almost parallel to the top of the core to prevent flow reversal in coolant channels. (4) More than one disperser system may be necessary to create an inversion layer in the pool

  4. EMI environment EMC considerations concerning equipment upgrades at a nuclear utility power generating station a case history

    International Nuclear Information System (INIS)

    Metcalf, M.J.

    1993-01-01

    As equipment is upgraded during scheduled power outages in nuclear power generating stations, more and more utilities will be faced with the problem of dealing with Electromagnetic Compatibility (EMC) issues that have evolved with the trend of manufacturers designing equipment based around state-of-the-art high technology logic devices. This paper lists Commonwealth Edison Company (CECO) equipment that was scrutinized by National Technical Systems (NTS) for its EMI impact. The test requirements and test procedures for assessing EMI and EMC are outlined. Although on-site mapping data was gathered to assist CECO for the upgrade described here of the Auxiliary Electric Equipment Room of a Westinghouse Eagle 21 Reactor Protection System at the Zion Unit No.1 Station, blanket mapping of every location for every upgrade is a short term, expensive solution to the EMI problem. It is concluded that the primary problem of lack of system and component level EMI specifications must be addressed by a governing body. 7 refs., 2 figs

  5. Feasibility study of the university of Utah TRIGA reactor power upgrade - part II: Thermohydraulics and heat transfer study in respect to cooling system requirements and design

    Directory of Open Access Journals (Sweden)

    Babitz Philip

    2013-01-01

    Full Text Available The thermodynamic conditions of the University of Utah's TRIGA Reactor were simulated using SolidWorks Flow Simulation, Ansys, Fluent and PARET-ANL. The models are developed for the reactor's currently maximum operating power of 90 kW, and a few higher power levels to analyze thermohydraulics and heat transfer aspects in determining a design basis for higher power including the cost estimate. It was found that the natural convection current becomes much more pronounced at higher power levels with vortex shedding also occurring. A departure from nucleate boiling analysis showed that while nucleate boiling begins near 210 kW it remains in this state and does not approach the critical heat flux at powers up to 500 kW. Based on these studies, two upgrades are proposed for extended operation and possibly higher reactor power level. Together with the findings from Part I studies, we conclude that increase of the reactor power is highly feasible yet dependable on its purpose and associated investments.

  6. Upgrade of a 30 kV/10 mA anode power supply for triode type gyrotron

    Energy Technology Data Exchange (ETDEWEB)

    Siravo, Ugo, E-mail: ugo.siravo@epfl.ch; Alberti, Stefano; Dubray, Jérémie; Fasel, Damien; Hogge, Jean-Philippe; Marlétaz, Blaise; Marmillod, Philippe; Perez, Albert; Silva, Miguel

    2015-10-15

    Highlights: • Triode type gyrotron is fed by 3 power supplies: the main, an anode PS(APS) and a heater. • This paper presents the upgrade of 3APS, supplied in 1999, that never fulfilled the specs. • The new working principle is very efficient, easy to implement, for a minimal cost. • Upgraded APS provides extended modulation capabilities, no overshoot and lowerripple. • This upgrade will allow exploring new operation regimes for the 3 TCV X3 gyrotrons. - The RF power of a gyrotron with a triode type magnetron-injection-gun (MIG) can be directly controlled via the voltage applied between its anode and its cathode. Hence, the performance of this type of gyrotron relies directly on the possibilities offered by the power supply controlling the anode to cathode voltage. For a system of gyrotrons connected to the same main high-voltage power supply, with a triode MIG one has the additional advantage of independently controlling each individual gyrotron. This paper presents the modifications brought to the three existing 30 kV/10 mA anode power supplies connected to the 500 kW/118 GHz/2s X3 gyrotrons operated on the TCV Tokamak. The new working principle based on phase-shift modulation (PSM) is described in detail. Experimental results obtained on dummy load are compared to simulations performed during the design phase. With respect to the initial working principle, the modulation frequency capability has been increased by a factor 10 reaching more than 5 kHz, whereas the output voltage ripple as well as the overshoot/undershoot have been significantly reduced.

  7. An Upgraded Front-End Switching Power Supply Design For the ATLAS TileCAL Detector of the LHC

    CERN Document Server

    Drake, Gary; The ATLAS collaboration

    2011-01-01

    We present the design of an upgraded switching power supply brick for the front-end electronics of the ATLAS hadron tile calorimeter (TileCAL) at the LHC. The new design features significant improvement in noise, improved fault detection, and generally a more robust design, while retaining the compact size, water-cooling, output control, and monitoring features in this 300 KHz design. We discuss the improvements to the design, and the radiation testing that we have done to qualify the design. We also present our plans for the production of 2400 new bricks for installation on the detector in 2013.

  8. An Upgraded Front-End Switching Power Supply Design for the ATLAS TileCAL Detector of the LHC

    CERN Document Server

    Drake, G; The ATLAS collaboration; De Lurgio, P; Henriques, A; Minashvili, I; Nemecek, S; Price, L; Proudfoot, J; Stanek, R

    2011-01-01

    We present the design of an upgraded switching power supply brick for the front-end electronics of the ATLAS hadron tile calorimeter (TileCAL) at the LHC. The new design features significant improvement in noise, improved fault detection, and generally a more robust design, while retaining the compact size, water-cooling, output control, and monitoring features in this 300 KHz design. We discuss the improvements to the design, and the radiation testing that we have done to qualify the design. We also present our plans for the production of 2400 new bricks for installation on the detector in 2013.

  9. The Belgian experience on the backfitting and safety upgrading of old operating nuclear power plants

    International Nuclear Information System (INIS)

    Brognon, T.

    1993-01-01

    The paper describes the methodology for backfitting and safety upgrading during the reevaluation of the Belgian NPP's: first generation (Doel-1, Doel-2, Tihange-1) and second generation plants (Doel-3, Doel-4, Tihange-2 and Tihange-3). A list of essential safety subjects and topics is given. The experience has proved the feasibility of a safety upgrading of operating NPP without injury to its availability, the benefit of a close cooperation between owner, engineering company and safety authorities throughout the project. A global approach to solving numerous specific deficiencies along with the optimization of the investments regarding the safety improvement of the NPP is suggested. Further increase of the know-how will be achieved through the present Belgian programme along with similar activities abroad. (R.I.)

  10. Upgrade of the main ring magnet power supply for the KEK 12GeV proton synchrotron

    International Nuclear Information System (INIS)

    Sato, H.; Sueno, T.; Toyama, T.; Mikawa, M.; Toda, T.; Matsumoto, S.

    1991-01-01

    In order to use the slow extracted beam of the PS more effectively, the period of slow extraction has been extended. In this paper, upgrade of the main ring magnet power supply is described. The main power supply consists of thyrister rectifiers, DC filters, reactive power compensators, AC harmonic filters and control systems. To increase the current capacity during flat top, the rectifiers and transformers were improved. AC network and DC filter were remained as it is, since the acceleration and deceleration times were not varied. Analog control devices and the computer control software have also been improved to realize a 2 sec flat top with a 4 sec repetition rate compared with the former 0.6sec flat top with a 2.5 sec repetition rate

  11. Failures during Load-Frequency Control Maneuvers in an Upgraded Hydropower Plant: Causes, Identification of Causes and Solution Proposals

    Directory of Open Access Journals (Sweden)

    Juan I. Pérez-Díaz

    2015-09-01

    Full Text Available The objective of this paper is to investigate the cause of several unexpected high amplitude oscillations that occurred in the surge tank water level of a real hydropower plant during secondary load-frequency control (LFC maneuvers, after the replacement of the turbine runner, and to propose solutions that allow the power plant to continue providing secondary LFC in a safe and reliable manner. For this purpose, a simulation model has been developed and calibrated from data gathered during several on-site tests. Two different solutions are proposed in order to cope with the observed problem: using a state-dependent load change rate limiter or modifying the hydro turbine governor gains; the turbine governor remains the same as before the runner replacement. The proposed solutions are tested against a set of realistic secondary LFC signals by means of simulations and compared to each other as a function of the probability that the surge tank water level descends below a minimum safe level and the quality of the secondary LFC response. The results presented in the paper demonstrate the validity of the methodology proposed to determine the state-dependent ramp limit, as well as its effectiveness to prevent the surge tank drawdown and to provide clear insight into the trade-off between response quality and power plant safety.

  12. A new slip stacking RF system for a twofold power upgrade of Fermilab's Accelerator Complex

    Energy Technology Data Exchange (ETDEWEB)

    Madrak, Robyn [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States)

    2014-05-15

    Fermilab's Accelerator Complex has been recently upgraded, in order to increase the 120 GeV proton beam power on target from about 400 kW to over 700 kW for NOvA and other future intensity frontier experiments. One of the key ingredients of the upgrade is the offloading of some Main Injector synchrotron operations - beam injection and RF manipulation called ''slip stacking'' - to the 8GeV Recycler Ring, which had until recently been used only for low-intensity antiproton storage and cooling. This required construction of two new 53 MHz RF systems for the slip-stacking manipulations. The cavities operate simultaneously at Vpeak ≲150 kV, but at slightly different frequencies (Δf=1260 Hz). Their installation was completed in September 2013. This article describes the novel solutions used in the design of the new cavities, their tuning system, and the associated high power RF system. First results showing effective operation of the RF system, beam capture and successful slip-stacking in the Recycler Ring are presented.

  13. Maintenance procedure upgrade programs

    International Nuclear Information System (INIS)

    Campbell, J.J.; Zimmerman, C.M.

    1988-01-01

    This paper describes a systematic approach to upgrading nuclear power plant maintenance procedures. The approach consists of four phases: diagnosis, program planning, program implementation, and program evaluation. Each phase is explained as a series of steps to ensure that all factors in a procedure upgrade program are considered

  14. Seismic assessment and upgrading of nuclear power plants in Eastern Europe

    Energy Technology Data Exchange (ETDEWEB)

    Katona, T; Kostov, M

    1997-03-01

    The basic findings of the seismic re-qualification programmes going on recently at all VVER plants in Eastern Europe can be summarised. The problems of the seismic safety have to be solved taking into account the general concept of the nuclear safety enhancement of the units. There are cases where the system improvements lead to better and more effective solution of the problem than the structural upgrading. The equipment and piping of the primary system have sufficient capacity. The viscous dampers are considered usually for the upgrading. The equipment anchorage especially the electrical and I and C equipment anchorage have to be upgraded. There are general consideration for replacement of the hydraulic snubbers by viscous dampers in the primary circuit of the VVER 440/V230. The considerations are not only because of the better seismic behaviour but mainly because of the better operational performance. There is relatively good seismic instrumentation at the plants considered. The definition of the scram level of the units not designed for an OBE is an essential problem. More effort needed for the definition of this level on the basis of re-evaluation experience of the plant equipment and after the proper definition of post-earthquake activities. The seismic re-evaluation and re-qualification of the VVER units is a general safety issue in Easter European countries. This rather complex problem can be solved adopting the experience, methods and requirements of western countries and taking into account the design features of the VVER units as well as the as built and as it is conditions. (J.P.N.)

  15. Seismic assessment and upgrading of nuclear power plants in Eastern Europe

    International Nuclear Information System (INIS)

    Katona, T.; Kostov, M.

    1997-01-01

    The basic findings of the seismic re-qualification programmes going on recently at all VVER plants in Eastern Europe can be summarised. The problems of the seismic safety have to be solved taking into account the general concept of the nuclear safety enhancement of the units. There are cases where the system improvements lead to better and more effective solution of the problem than the structural upgrading. The equipment and piping of the primary system have sufficient capacity. The viscous dampers are considered usually for the upgrading. The equipment anchorage especially the electrical and I and C equipment anchorage have to be upgraded. There are general consideration for replacement of the hydraulic snubbers by viscous dampers in the primary circuit of the VVER 440/V230. The considerations are not only because of the better seismic behaviour but mainly because of the better operational performance. There is relatively good seismic instrumentation at the plants considered. The definition of the scram level of the units not designed for an OBE is an essential problem. More effort needed for the definition of this level on the basis of re-evaluation experience of the plant equipment and after the proper definition of post-earthquake activities. The seismic re-evaluation and re-qualification of the VVER units is a general safety issue in Easter European countries. This rather complex problem can be solved adopting the experience, methods and requirements of western countries and taking into account the design features of the VVER units as well as the as built and as it is conditions. (J.P.N.)

  16. Electrical and mechanical adaptation of commercially available power inverter modules for BUSSARD – The power supply of ASDEX Upgrade in vessel saddle coils

    Energy Technology Data Exchange (ETDEWEB)

    Rott, Michael, E-mail: Michael.Rott@ipp.mpg.de [Max Planck Institute for Plasma Physics, Boltzmannstrasse 2, D-85748 Garching (Germany); Arden, Nils; Eixenberger, Horst [Max Planck Institute for Plasma Physics, Boltzmannstrasse 2, D-85748 Garching (Germany); Klädtke, Kevin [Technical University Munich, Arcisstraße 21, D-80333 München (Germany); Teschke, Markus; Suttrop, Wolfgang [Max Planck Institute for Plasma Physics, Boltzmannstrasse 2, D-85748 Garching (Germany)

    2015-10-15

    Highlights: • Mechanical design of inverters for restricted space and good mountability. • Supply of DC link possible with thyristor converter. • Plant safety by independent overcurrent protections and a commercially arc detection system. • Ground fault detection by fast differential current measurement. • Possibilities of changing the inductance of a two windings iron core choke. - Abstract: To supply the ASDEX Upgrade's B-coils with AC current up to 1.3 kA{sub p} at 500 Hz with arbitrary waveforms, a set of 16 inverters has been designed and partially built. To keep cost and development time low, commercially available power modules are used and existing current converters feed the DC links. Three power modules are mounted in one cubicle for realizing a three level neutral point clamped (NPC) topology with lowest possible inductivity and making the most of the limited space available. The paper presents the effort and steps required to adapt standard power blocks towards the needs of the ASDEX Upgrade power supply as well as the mechanical optimizations for good mountability, flexibility and scalability. Besides, solutions for mandatory personnel safety and plant safety are presented.

  17. Electrical and mechanical adaptation of commercially available power inverter modules for BUSSARD – The power supply of ASDEX Upgrade in vessel saddle coils

    International Nuclear Information System (INIS)

    Rott, Michael; Arden, Nils; Eixenberger, Horst; Klädtke, Kevin; Teschke, Markus; Suttrop, Wolfgang

    2015-01-01

    Highlights: • Mechanical design of inverters for restricted space and good mountability. • Supply of DC link possible with thyristor converter. • Plant safety by independent overcurrent protections and a commercially arc detection system. • Ground fault detection by fast differential current measurement. • Possibilities of changing the inductance of a two windings iron core choke. - Abstract: To supply the ASDEX Upgrade's B-coils with AC current up to 1.3 kA_p at 500 Hz with arbitrary waveforms, a set of 16 inverters has been designed and partially built. To keep cost and development time low, commercially available power modules are used and existing current converters feed the DC links. Three power modules are mounted in one cubicle for realizing a three level neutral point clamped (NPC) topology with lowest possible inductivity and making the most of the limited space available. The paper presents the effort and steps required to adapt standard power blocks towards the needs of the ASDEX Upgrade power supply as well as the mechanical optimizations for good mountability, flexibility and scalability. Besides, solutions for mandatory personnel safety and plant safety are presented.

  18. Upgrading uncompetitive products economically

    DEFF Research Database (Denmark)

    Lu, Hua; Jensen, Christian Søndergaard

    2012-01-01

    for upgrading an uncompetitive product, and combine the solutions into a single solution. We also propose a spatial join-based solution that assumes P and T are indexed by an R-tree. Given a set of products in the same R-tree node, we derive three lower bounds on their upgrading costs. These bounds are employed...

  19. Upgrading security at nuclear power plants: effect on utility operations and costs

    International Nuclear Information System (INIS)

    Salvesen, R.S.

    1977-01-01

    The impact of the new security regulation on Salem Unit No. 1 is discussed. The upgrading of security requirements in 10CFR 73.55 did not alter the basic elements of a security plan established in ANSI 18.17, but rather upgraded the level of the threat to which a security plan must respond. Its basic thrust is first to require a hardening of physical barriers and/or increase the security organization response capability to better neutralize a threat from the outside. Secondly, to implement more extensive search requirements to reduce the threat from inside by preventing the entry of unauthorized material that might be used for sabotage. Thirdly, it requires a reevaluation of security organization responsibilities and preplanning for contingencies to assure effective coordination of all involved parties. The new regulations impact most significantly on two of the five elements of a basic security plan--Physical Barriers and the Security Force and to some extent on administrative controls. At this time, I cannot accurately estimate the cost increase but would guess it will be double or triple our initial costs. There will be reduced productivity to some extent in stores and material handling activities and some impediment to all employees who must pass access control points, however, its overall affect on operating a its overall affect on operating activities should not be significant

  20. Obtaining muonic density estimates via application of matrix formalism to proposed surface detector upgrade at the Pierre Auger Observatory

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, David; Engel, Ralph; Roth, Markus [Karlsruhe Institute of Technology, Karlsruhe (Germany); Collaboration: Pierre Auger-Collaboration

    2015-07-01

    Event-by-event identification of cosmic ray primary composition lends itself to enhanced event selection in the search for anisotropic arrival directions. Principally, the number of muons reaching Earth's surface in an extensive air shower is indicative of composition. The Pierre Auger Observatory seeks to capitalize on this axiom by improving reconstructed muonic density estimates via an upgrade to its surface detector array. This upgrade, consisting of placing a scintillator on top of each existing water Cherenkov detector, exploits the differing response of two detectors to muonic and electromagnetic particles. Exploitation of this difference may be expressed in a matrix formalism whose application to simulated proton and iron showers is presented here.

  1. Analogue to digital upgrade project-boiler feedwater control system for Bruce Power nuclear units 1 & 2

    International Nuclear Information System (INIS)

    Long, R.

    2012-01-01

    Bruce Power Nuclear Generating Station A, “Bruce A” is in the final stages of its Restart Project. This capital project will see a large scale rehabilitation of Units 1 and 2 resulting in addition of 1500MW of safe, reliable, clean electricity to the Ontario grid. Restart Project Scope 375, Boiler Feedwater Controls Upgrade was sanctioned to replace obsolete analog devices with a modern digital control system. This project replaced the existing Foxboro H Line analog controls which comprised of 81 individual control modules and support instrumentation. The replacement system was a Triconex Triple Modular Redundant PLC which interfaces with two redundant touch screen monitors. The upgraded digital system incorporates the following controls: 1. Boiler Level Control Loops 2. Dearator Level Control Loops 3. Dearator Pressure Control Loops 4. Boiler Feedwater Recirculation Flow Control Loops A number of technical challenges were addressed when installing a new digital system within the existing plant configuration. Interfaces to new, old and refurbished field devices must be understood as well as implications of connecting to the plant’s Digital Control Computers (DCC’s) and newly installed Steam Generators. The overall project involved many stakeholders to address various requirements from conceptual / design stage through procurement, construction, commissioning and return to service. In addition, the project highlighted the unique requirements found in Nuclear Industry with respect to Human Factors and Software Quality Assurance. (author)

  2. Utilization of surplus electricity from wind power for dynamic biogas upgrading

    DEFF Research Database (Denmark)

    Jurgensen, Lars; Ehimen, Ehiazesebhor Augustine; Born, Jens

    2014-01-01

    The methanation of CO2 has been increasingly discussed for the potential long term storage of electricity and for facilitating grid load management. Using the regions of northern Germany as a case study, the feasibility of CO2 conversion from biogas plants and its integration in existing natural...... gas grid was examined in this study. Furthermore the material and energy flows of in the methanation process, were evaluated to provide expression for the quantities of excess electrical energy which could be potentially stored using the biogas integrated systems. The study results showed...... that with 480 biogas plants in the region would be able to utilize up to 0.7 TWh surplus electricity could be used to produce 100 106 m3 at standard temperature and pressure of upgraded methane per year....

  3. Developing architecture for upgrading I and C systems of an operating nuclear power plant using a quality attribute-driven design method

    Energy Technology Data Exchange (ETDEWEB)

    Suh, Yong Suk; Keum, Jong Yong [SMART Technology Validation Division, Korea Atomic Energy Research Institute, 150-1 Dukjin-dong, Yuseong-gu, Daejon (Korea, Republic of); Kim, Hyeon Soo, E-mail: hskim401@cnu.ac.kr [Department of Computer Science and Engineering, Chungnam Nat' l Univ., 220 Gung-dong, Yuseong-gu, Daejon (Korea, Republic of)

    2011-12-15

    This paper presents the architecture for upgrading the instrumentation and control (I and C) systems of a Korean standard nuclear power plant (KSNP) as an operating nuclear power plant. This paper uses the analysis results of KSNP's I and C systems performed in a previous study. This paper proposes a Preparation-Decision-Design-Assessment (PDDA) process that focuses on quality oriented development, as a cyclical process to develop the architecture. The PDDA was motivated from the practice of architecture-based development used in software engineering fields. In the preparation step of the PDDA, the architecture of digital-based I and C systems was setup for an architectural goal. Single failure criterion and determinism were setup for architectural drivers. In the decision step, defense-in-depth, diversity, redundancy, and independence were determined as architectural tactics to satisfy the single failure criterion, and sequential execution was determined as a tactic to satisfy the determinism. After determining the tactics, the primitive digital-based I and C architecture was determined. In the design step, 17 systems were selected from the KSNP's I and C systems for the upgrade and functionally grouped based on the primitive architecture. The overall architecture was developed to show the deployment of the systems. The detailed architecture of the safety systems was developed by applying a 2-out-of-3 voting logic, and the detailed architecture of the non-safety systems was developed by hot-standby redundancy. While developing the detailed architecture, three ways of signal transmission were determined with proper rationales: hardwire, datalink, and network. In the assessment step, the required network performance, considering the worst-case of data transmission was calculated: the datalink was required by 120 kbps, the safety network by 5 Mbps, and the non-safety network by 60 Mbps. The architecture covered 17 systems out of 22 KSNP's I and C

  4. Developing architecture for upgrading I and C systems of an operating nuclear power plant using a quality attribute-driven design method

    International Nuclear Information System (INIS)

    Suh, Yong Suk; Keum, Jong Yong; Kim, Hyeon Soo

    2011-01-01

    This paper presents the architecture for upgrading the instrumentation and control (I and C) systems of a Korean standard nuclear power plant (KSNP) as an operating nuclear power plant. This paper uses the analysis results of KSNP's I and C systems performed in a previous study. This paper proposes a Preparation–Decision–Design–Assessment (PDDA) process that focuses on quality oriented development, as a cyclical process to develop the architecture. The PDDA was motivated from the practice of architecture-based development used in software engineering fields. In the preparation step of the PDDA, the architecture of digital-based I and C systems was setup for an architectural goal. Single failure criterion and determinism were setup for architectural drivers. In the decision step, defense-in-depth, diversity, redundancy, and independence were determined as architectural tactics to satisfy the single failure criterion, and sequential execution was determined as a tactic to satisfy the determinism. After determining the tactics, the primitive digital-based I and C architecture was determined. In the design step, 17 systems were selected from the KSNP's I and C systems for the upgrade and functionally grouped based on the primitive architecture. The overall architecture was developed to show the deployment of the systems. The detailed architecture of the safety systems was developed by applying a 2-out-of-3 voting logic, and the detailed architecture of the non-safety systems was developed by hot-standby redundancy. While developing the detailed architecture, three ways of signal transmission were determined with proper rationales: hardwire, datalink, and network. In the assessment step, the required network performance, considering the worst-case of data transmission was calculated: the datalink was required by 120 kbps, the safety network by 5 Mbps, and the non-safety network by 60 Mbps. The architecture covered 17 systems out of 22 KSNP's I and C systems. The

  5. Coal upgrading

    Energy Technology Data Exchange (ETDEWEB)

    Nunes, S. [IEA Clean Coal Centre, London (United Kingdom)

    2009-10-15

    This report examines current technologies and those likely to be used to produce cleaner coal and coal products, principally for use in power generation and metallurgical applications. Consideration is also given to coal production in the leading coal producing countries, both with developed and developing industries. A range of technologies are considered. These include the coal-based liquid fuel called coal water mixture (CWM) that may compete with diesel, the production of ultra-clean coal (UCC) and coal liquefaction which competes with oil and its products. Technologies for upgrading coal are considered, especially for low rank coals (LRC), since these have the potential to fill the gap generated by the increasing demand for coal that cannot be met by higher quality coals. Potential advantages and downsides of coal upgrading are outlined. Taking into account the environmental benefits of reduced pollution achieved through cleaner coal and reduced transport costs, as well as other positive aspects such as a predictable product leading to better boiler design, the advantages appear to be significant. The drying of low rank coals improves the energy productively released during combustion and may also be used as an adjunct or as part of other coal processing procedures. Coal washing technologies vary in different countries and the implications of this are outlined. Dry separation technologies, such as dry jigging and electrostatic separation, are also described. The demonstration of new technologies is key to their further development and demonstrations of various clean coal technologies are considered. A number of approaches to briquetting and pelletising are available and their use varies from country to country. Finally, developments in upgrading low rank coals are described in the leading coal producing countries. This is an area that is developing rapidly and in which there are significant corporate and state players. 81 refs., 32 figs., 3 tabs.

  6. Power demand operation - environment and potential. Proposals for main project

    International Nuclear Information System (INIS)

    Wathne, M.

    1995-01-01

    This report discusses proposals for a main project on environmental and other problems arising when hydroelectric power stations supply energy at gigawatt levels. The project aims in particular to identify environmental problems where too little is known today for proper planning of this type of operation. The proposals emphasize the consequences which cannot be adequately analysed in terms of current techniques. These techniques presuppose steady state conditions. One proposal concerns market terms for power sales. Other proposals deal with hydrological data and uncertainty, capacity of watercourses, ice and temperature, aquatic eco-systems, erosion, supersaturation of water with air, flooding and dam breaks, impact on climate, inflow of fresh water in fjords and impact on algae. 33 refs., 4 tabs

  7. J-PARC accelerator and neutrino beamline upgrade programme

    Science.gov (United States)

    Friend, M.

    2017-09-01

    The 30 GeV proton beam from the J-PARC Main Ring (MR) accelerator is used to produce a world-class conventional neutrino beam - the neutrino source for the J-PARC long-baseline neutrino programme, including the current T2K experiment and proposed future experiments. Planned upgrades to increase the beam power of the MR from the current ˜400 kW to the design power of 750 kW and beyond, to 1.3+ MW, are underway. These include hardware modifications, such as upgrades of the MR magnet power supplies, RF systems, and feedback systems, as well as a change of the MR beam betatron tune point. Upgrades to the neutrino beamline, such as to the proton beam monitoring, horns, and radioactive material handling, will also be required to accommodate the increased proton beam power. An overview of planned J-PARC MR and neutrino facility upgrades is given.

  8. A proposal of nuclear fusion power plant equipped with SMES

    International Nuclear Information System (INIS)

    Natsukawa, Tatsuya; Makamura, Hirokazu; Molinas, Marta; Nomura, Shinichi; Tsuji-Iio, Shunji; Shimada, Ryuichi

    2000-01-01

    When we intend to operate the nuclear fusion power plant (NFPP) under the economically efficient conditions as an independent power plant, it is desirable that the generated electric power should be sent to network according to the power demand. With such strategy being expanded, some energy storage system is available. In this paper, NFPP equipped with the superconducting magnetic energy storage system (SMES) as electric power storage device is proposed. The advantages of NFPP equipped with SMES are discussed and a case study of 500 MW NFPP equipped with 6 GWh SMES is done with estimating its operational value. For SMES coil, the concept of Force Balanced Coil (FBC) is applied and 6 GWh class FBC is briefly designed

  9. Effects of upgrading systems on energy conversion efficiency of a gasifier - fuel cell - gas turbine power plant

    International Nuclear Information System (INIS)

    Pedrazzi, Simone; Allesina, Giulio; Tartarini, Paolo

    2016-01-01

    Highlights: • An advanced gasifier-SOFC-MGT system is modeled. • An overall electrical efficiency of 32.81% is reached. • Influence of all the sub-system modeled on the power plant efficiency is discussed. • Compression storage of syngas is taken into account. - Abstract: This work focuses on a DG-SOFC-MGT (downdraft gasifier - solid oxide fuel cell - micro gas turbine) power plant for electrical energy production and investigates two possible performance-upgrading systems: polyphenylene oxide (PPO) membrane and zeolite filters. The first is used to produce oxygen-enriched air used in the reactor, while the latter separates the CO_2 content from the syngas. In order to prevent power plant shutdowns during the gasifier reactor scheduled maintenance, the system is equipped with a gas storage tank. The generation unit consists of a SOFC-MGT system characterized by higher electrical efficiency when compared to conventional power production technology (IC engines, ORC and EFGT). Poplar wood chips with 10% of total moisture are used as feedstock. Four different combinations with and without PPO and zeolite filtrations are simulated and discussed. One-year energy and power simulation were used as basis for comparison between all the cases analyzed. The modeling of the gasification reactions gives results consistent with literature about oxygen-enriched processes. Results showed that the highest electrical efficiency obtained is 32.81%. This value is reached by the power plant equipped only with PPO membrane filtration. Contrary to the PPO filtering, zeolite filtration does not increase the SOFC-MGT unit performance while it affects the energy balance with high auxiliary electrical consumption. This solution can be considered valuable only for future work coupling a CO_2 sequestration system to the power plant.

  10. A proposal on siting counterplan of nuclear power plants

    International Nuclear Information System (INIS)

    Sasao, Hitoshi

    1980-01-01

    As for the nuclear power generation in Japan. 21 plants with 14.95 million kW capacity have started the operation in 14 years. It is equivalent to more than 12% of the total capacity of power stations. But the environment around the development of nuclear power generation becomes more and more strict recently, and the formation of the consensus of residents becomes a very large political problem. The lead time from the proposal of construction to the local community to the commencement of operation was 8 years and 1 month in the case of 10 nuclear power stations in operation, but it is extended to 15 years and 6 months in the case of 4 power stations under construction. The prefectures where nuclear power stations are located were seven at the end of 1970, and only three were added during 9 years thereafter. It shows the difficulty of the location of nuclear power stations in new prefectures. In order to attain 78 million kW of nuclear power generation by 1995, the location of 50 million kW must be decided in coming several years in view of the lead time. The progress of the studies in the Atomic Industrial Forum, the strengthening of security system in the sistricts concerned, the formation of open environment for informations, the improvement of the setup concerning the compensation to fishery and others, and the studies on the law concerning the special measures for the districts where nuclear facilities are located are discussed. (Kako, I.)

  11. Upgrade of the MAGIC telescopes single wavelength micro power LIDAR system

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, Dominik [Max-Planck-Institut fuer Physik, Muenchen (Germany); Collaboration: MAGIC-Collaboration

    2016-07-01

    Since 2011 a single wavelength LIDAR system is operated alongside the observations of the MAGIC telescopes. It is used for real-time monitoring of the atmospheric transmission and for detecting cloud layers within the field of view of MAGIC. The system uses a pulsed Nd:YAG laser with 532 nm wavelength and a pulse energy of 5 μJ as transmitter. The receiver is mounted to a 60 cm spherical single mirror telescope with a F/D ratio of 2.5. To compensate for the low light intensities a sensitive detector with the capability of single photon detection as well as charge integration is needed. For this purpose, a hybrid photo diode with a peak quantum efficiency of 55% an a pulse width of 2.5ns is used in a custom designed detector. The analog signal is recorded by a computer mounted 8-bit FADC with 200 MS/s. A signal analysis algorithm converts the LIDAR return signal into a number of single photoelectron counts per range bin. The atmospheric transmission is calculated by fitting a Rayleigh back-scattering model with a sliding window. The resulting transmission profile is used to correct the MAGIC gamma ray data for adverse weather conditions. After five years of data taking the MAGIC LIDAR system is upgraded with a stronger laser and a new detector unit in order to extend the measurement range and to optimize the operation.

  12. 76 FR 45551 - Post-2014 Resource Pool; Loveland Area Projects, Proposed Power Allocation

    Science.gov (United States)

    2011-07-29

    ... Proposed Power Allocation. SUMMARY: Western Area Power Administration (Western), a Federal power marketing... Pool Proposed Power Allocation developed under the requirements of the Power Marketing Initiative of... resulted in this Notice of Proposed Power Allocation. DATES: The comment period on this Notice of Proposed...

  13. Interpretation of the effects of electron cyclotron power absorption in pre-disruptive tokamak discharges in ASDEX Upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Nowak, S.; Lazzaro, E.; Granucci, G. [Associazione Euratom-CNR sulla Fusione, IFP-CNR, Via R. Cozzi 53, 20125 Milano (Italy); Esposito, B. [Associazione Euratom-CNR sulla Fusione, CR Frascati, C.P. 65, 00044 Frascati (Italy); Maraschek, M.; Zohm, H. [Max-Planck-Institut fuer Plasmaphysik, EURATOM Association, Boltzmannstr.2, 85748 Garching bei Munchen (Germany); Sauter, O.; Brunetti, D. [CRPP, Association Euratom-Confederation Suisse, EPFL, 1015 Lausanne (Switzerland); Collaboration: ASDEX Upgrade Team

    2012-09-15

    Tokamak disruptions are events of fatal collapse of the magnetohydrodynamic (MHD) confinement configuration, which cause a rapid loss of the plasma thermal energy and the impulsive release of magnetic energy and heat on the tokamak first wall components. The physics of the disruptions is very complex and non-linear, strictly associated with the dynamics of magnetic tearing perturbations. The crucial problem of the response to the effects of localized heat deposition and current driven by external (rf) sources to avoid or quench the MHD tearing instabilities has been investigated both experimentally and theoretically on the ASDEX Upgrade tokamak. The analysis of the conditions under which a disruption can be prevented by injection of electron cyclotron (EC) rf power, or, alternatively, may be caused by it, shows that the local EC heating can be more significant than EC current drive in ensuring neoclassical tearing modes (NTMs) stability, due to two main reasons: first, the drop of temperature associated with the island thermal short circuit tends to reduce the neoclassical character of the instability and to limit the EC current drive generation; second, the different effects on the mode evolution of both the location of the power deposition relative to the island separatrix and the island shape deformation lead to less strict requirements of precise power deposition focussing. A contribution to the validation of theoretical models of the events associated with NTM is given and can be used to develop concepts for their control, relevant also for ITER-like scenarios.

  14. A DC-DC Conversion Powering Scheme for the CMS Phase-1 Pixel Upgrade

    CERN Document Server

    Feld, Lutz Werner; Marcel Friedrichs; Richard Hensch; Karpinski, Waclaw; Klein, Katja; Sammet, Jan Domenik; Wlochal, Michael

    2012-01-01

    The powering scheme of the CMS pixel detector will be described, and the performance of prototype DC-DC buck converters will be presented, including power efficiency, system tests with DC-DC converters and pixel modules, thermal management, reliability at low temperature, and studies of potential frequency locking betwe...

  15. Development of a DC-DC conversion powering scheme for the CMS Phase-1 pixel upgrade

    CERN Document Server

    Feld, Lutz Werner; Karpinski, Waclaw; Klein, Katja; Lipinski, Martin; Preuten, Marius; Max Rauch; Rittich, David Michael; Sammet, Jan Domenik; Wlochal, Michael

    2014-01-01

    A novel powering scheme based on the DC-DC conversion technique will be exploited to power the CMS Phase-1 pixel detector. DC-DC buck converters for the CMS pixel project have been developed, based on the AMIS5 ASIC designed by CERN. The powering system of the Phase-1 pixel detector is described and the performance of the converter prototypes is detailed, including power efficiency, stability of the output voltage, shielding, and thermal management. Results from a test of the magnetic field tolerance of the DC-DC converters are reported. System tests with pixel modules using many components of the future pixel barrel system are summarized. Finally first impressions from a pre-series of 200 DC-DC converters are presented.

  16. Achieving safety/risk goals for less ATR backup power upgrades

    International Nuclear Information System (INIS)

    Atkinson, S.A.

    1995-01-01

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

  17. Cogeneration Power Plants: a Proposed Methodology for Unitary Production Cost

    International Nuclear Information System (INIS)

    Metalli, E.

    2009-01-01

    A new methodology to evaluate unitary energetic production costs in the cogeneration power plants is proposed. This methodology exploits the energy conversion factors fixed by Italian Regulatory Authority for Electricity and Gas. So it allows to settle such unitary costs univocally for a given plant, without assigning them a priori subjective values when there are two or more energy productions at the same time. Moreover the proposed methodology always ensures positive values for these costs, complying with the total generation cost balance equation. [it

  18. Superconducting Magnet Power Supply and Hard-Wired Quench Protection at Jefferson Lab for 12 GeV Upgrade

    International Nuclear Information System (INIS)

    Ghoshal, Probir K.; Bachimanchi, Ramakrishna; Fair, Ruben J.; Gelhaar, David; Kumar, Onish

    2017-01-01

    The superconducting magnet system in Hall B being designed and built as part of the Jefferson Lab 12 GeV upgrade requires powering two conduction cooled superconducting magnets - a torus and a solenoid. The torus magnet is designed to operate at 3770 A and solenoid at 2416 A. Failure Modes and Effects Analysis (FMEA) determined that voltage level thresholds and dump switch operation for magnet protection should be tested and analyzed before incorporation into the system. The designs of the quench protection and voltage tap sub-systems were driven by the requirement to use a primary hard-wired quench detection sub-system together with a secondary PLC-based protection. Parallel path voltage taps feed both the primary and secondary quench protection sub-systems. The PLC based secondary protection is deployed as a backup for the hard-wired quench detection sub-system and also acts directly on the dump switch. Here, we describe a series of tests and modifications carried out on the magnet power supply and quench protection system to ensure that the superconducting magnet is protected for all fault scenarios.

  19. Safety and upgrading of nuclear power plants with WWER-440/V-230; Voprosy bezopasnosti i modernizatsii AEhS s WWER-440 (V-230)

    Energy Technology Data Exchange (ETDEWEB)

    Melnikov, N [Opytno-Konstruktorskoe Byuro Gidropress, Podol` sk (Russian Federation)

    1996-12-31

    Modernization of WWER-440/V-230 reactors is considered according to the WANO project `Proposal for reconstruction of WWER-440/V-230 reactors` (1990). The main technical measures to be taken relate to: 1. Expanding the considered spectrum of design basis accidents; 2. Provision of first loop integrity; 3. Safety system structure and components reliability enhancement; 4. Reduction o initiating events probability; 5. Enhancement of hermeticity and integrity of the area surrounding the first loop; 6. Fire fighting system upgrade; 7. Radiation control system upgrade; 8. Provision of seismic resistance. Details of the recommended technical steps for some NPPs are presented. 1 tab.

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

    International Nuclear Information System (INIS)

    Zhu, L.H.

    1998-01-01

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

  1. Proposed advanced satellite applications utilizing space nuclear power systems

    International Nuclear Information System (INIS)

    Bailey, P.G.; Isenberg, L.

    1990-01-01

    A review of the status of space nuclear reactor systems and their possible applications is presented. Such systems have been developed over the past twenty years and are capable of use in various military and civilian applications in the 5-1000 kWe power range. The capabilities and limitations of the currently proposed nuclear reactor systems are summarized. Safety issues are shown to be identified, and if properly addressed should not pose a hindrance. Applications are summarized for the federal and civilian community. These applications include both low and high altitude satellite surveillance missions, communications satellites, planetary probes, low and high power lunar and planetary base power systems, broad-band global telecommunications, air traffic control, and high-definition television

  2. Developing Major Steps for a Feasibility Study for Upgrading I and C Systems in a Large Scale for an Operating Nuclear Power Plant

    International Nuclear Information System (INIS)

    Suh, Yong Suk; Keum, Jong Yong; Kim, Dong Hoon; Kang, Hyeon Tae; Sung, Chan Ho; Lee, Jae Ki; Cho, Chang Hwan

    2009-01-01

    According to the IAEA report as of Jan. 2008, 436 nuclear power reactors are in operation over the world and 368 nuclear power reactors exceed their operating ages by 20 years. The average I and C equipment's life span is 20 years comparing with that the average reactor's life time is 40 to 60 years. This means that a reactor must be faced with I and C equipment obsolescence problems once or twice during its operating years. The I and C equipment is replaced with new equipment only when the obsolescence problem occurs in a nuclear power plant. This is called an equipment basis upgrade in this paper. This replacement is such a general practice that occurs only when needed. We can assume that most of I and C equipment of a plant will meet with the obsolescence problem almost same time since it started operating. Although there must be a little time difference in the occurrence of the problems among I and C equipment, the replacement will be required in consecutive years. With this assumption, it is recommendable to upgrade the equipment, which is to meet with the problem at the same time, with new equipment at the same time. This is called a system basis upgrade in this paper. The system-basis replacement can be achieved in a large scale by coupling systems whose functions are related each other and replacing them together with a new upto- date platform. This paper focuses on the large scale upgrade of I and C systems for existing and operating NPPs. While performing a feasibility study for the large scale upgrade for Korea standard nuclear power plants (KSNPs), six major steps are developed for the study. This paper is to present what to perform in each step

  3. Density dependence of SOL power width in ASDEX upgrade L-Mode

    Directory of Open Access Journals (Sweden)

    B. Sieglin

    2017-08-01

    A recent study [4] with an open divertor configuration found an asymmetry of the power fall-off length between inner and outer target with a smaller power fall-off length λq,i on the inner divertor target. Measurements with a closed divertor configuration find a similar asymmetry for low recycling divertor conditions. It is found, in the experiment, that the in/out asymmetry λq,i/λq,o is strongly increasing with increasing density. Most notably the heat flux density at the inner divertor target is reducing with increasing λq,i whilst the total power onto each divertor target stays constant. It is found that λq,o exhibits no significant density dependence for hydrogen and deuterium but increases with about the square root of the electron density for helium. The difference between H,D and He could be due to the different recycling behaviour in the divertor. These findings may help current modelling attempts to parametrize the density dependence of the widening of the power channel and thus allow for detailed comparison to both divertor effects like recycling or increased upstream SOL cross field transport.

  4. 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)

  5. Upgrade of the NCSU PULSTAR instrumentation power channels. Final technical report, September 1, 1992 - August 31, 1994

    International Nuclear Information System (INIS)

    Perez, P.B.

    1998-01-01

    The Nuclear Reactor Program at North Carolina State University initiated an upgrade program at the NCSU PULSTAR Reactor in 1990. The originally supplied instrumentation has been replaced with solid-state and current technology equipment. The financial assistance from the US Department of Energy has been the primary source of support. This is the final report for the Instrumentation Upgrade

  6. Gradual instrumentation and control upgrades in U.S. nuclear power plants

    International Nuclear Information System (INIS)

    Welk, S.

    1997-01-01

    Since the late 1980s, US nuclear power plants have been struggling with the technical and licensing realities associated with installing digital protection and control systems into existing facilities. The industry, regulators and equipment vendors are finally reaching agreements regarding acceptable practices and requirements. The present paper explains the philosophy for gradual instrumentation and control replacements being pursued and the technical issues being addressed. It also describes some of the future challenges facing the industry. (author)

  7. License renewal and power upgrade of the Cornell University TRIGA reactor

    International Nuclear Information System (INIS)

    Aderhold, Howard C.

    1984-01-01

    The Cornell Mark II TRIGA reactor has been a principal facility for instruction and research in nuclear science and engineering at Cornell, and it has been extensively used by other departments at Cornell and by nearby universities and industries. Initially the fuel was low hydride, 8.5w/o 19%-enriched, aluminum clad; in 1974 it was changed to high-hydride, stainless-steel-clad. The maximum power has been 100 kW, with pulses to $2, and operation has been on a one-shift demand basis. Annual energy generation of 50 MWH has been typical. Standard features include a 4-inch tangential port and our 6-inch radial ports, a thermal column with hohlraum and vertical access, a central thimble, a 'rabbit', and a set of dry irradiation tubes, replacing the 'Lazy Susan'. The license was renewed and amended in November 1983; the new limits are 500 kW and $3 pulses. Physical changes to the facility included addition of a water-to-water heat exchanger and of a diffuser at the water outlet ∼ 60 cm above the core. The flow rate is 300 liters per minute in the primary (reactor) side of the heat exchanger. The temperature of the chilled water entering the secondary of the exchanger is ∼ 12?C; its flow rate is adjusted by a servo-controlled by-pass valve to maintain the desired range of pool water temperature. Steps taken to go to higher power included rearrangement of fuel elements to increase excess reactivity, recalibration of control rods, and power vs ion chamber current calibrations at successively higher power by comparing the rate of rise of pool temperature with a known rate using electrical heating elements. Steady-state operation has been done up to 480 kW (nominal) but pulsing at the newly allowed higher levels has not been tested as yet

  8. Upgrade of Control and Protection System of the Ignalina Nuclear Power Plant Units 1 and 2

    International Nuclear Information System (INIS)

    Wright, Ronald E.; Fletcher, Norman; Sidnev, Victor E.; Bickel, John H.; Vianello, Aldo; Pearsall, Raymond D.

    2003-01-01

    The Ignalina nuclear power plant (NPP) Units 1 and 2 are Soviet-designed, RBMK (Reaktor Bolshoi Moschnosti Kipyashchiy), channelized, large power-type reactors. The original-design electrical capacity for each unit was 1500 MW. Unit 1 began operating in 1983, and Unit 2 was started up in 1987. In 1994, the government of Lithuania agreed to accept grant support for the Ignalina NPP Safety Improvement Program with funding supplied by the Nuclear Safety Account of the European Bank for Reconstruction and Development (EBRD). As conditions for receiving this funding, the Ignalina NPP agreed to prepare a comprehensive safety analysis report that would undergo independent peer review after it was issued. The EBRD Safety Panel oversaw preparation and review of the report. In 1996, the safety analysis report for Unit 1 was completed and delivered to the EBRD. Part of the analyses covered anticipated transients without scram (ATWS). The analysis showed that some ATWS scenarios could lead to unacceptable consequences in <1 min. The EBRD Safety Panel recommended to the government of Lithuania that the Ignalina NPP develop and implement a program of compensatory measures for the control and protection system before the unit would be allowed to return to operation following its 1998 maintenance outage. A compensatory control and protection system that would mitigate the unacceptable consequences was designed, procured, manufactured, tested, and installed. The project was funded by U.S. Department of Energy

  9. Upgrading the Reactor Power Control Concept with a Modern Digital Control System

    International Nuclear Information System (INIS)

    Laengle, M.; Schildheuer, R.

    2011-01-01

    Within the framework of a retrofit project, a reactor power instrumentation and control system (REALL) - consisting of a limiting system and the respective reactor control systems - was retrofitted and modernized in a 1450-MW-nuclear-power-plant in Baden-Wuerttemberg. The REALL process control functions were implemented within a modern and completely digitized control system that has been designed for use in safety I and C applications. Along with the installation of the digital control system, the associated hardware was adapted to today's state of the art. At the same time, the given potential for improvement, as revealed during the plant's operation so far, was taken into account in the programming. In order to provide for transparent and quality-assured project management, the implementation was based on a stage plan consisting of several steps, along with specific milestones. Final commissioning of the modern digital control system took place during the 2008 plant overhaul. Despite the complex commissioning procedure, it was possible to avoid a major prolongation of the plant's downtime and to keep within a rough 4-week timeframe that had originally been defined for the plant overhaul to adequate structuring of the project, goal-oriented implementation of preparatory infrastructural measures and adequate scheduling of the coordinated activities of the installation and commissioning teams entrusted with the commissioning of the digital control system during the overhaul activities. (author)

  10. The Need for Strategic Planning for Nuclear Power Plant I and C Upgrades

    International Nuclear Information System (INIS)

    Hill, J. Douglas; Moore, Paul

    2002-01-01

    Nuclear power plants rely on Instrumentation and Control (I and C) systems for control, monitoring and protection of the plant. The original, analog designs used in most nuclear plants have become or soon will be obsolete, forcing plants to turn to digital technology. Many factors affect the design of replacement equipment, including long-term and short-term economics, regulatory issues, and the way the plant operates on a day-to-day basis. The first step to all modernization projects should involve strategic planning, to ensure that the overall long and short-term goals of the plant are met. Strategic planning starts with a thorough evaluation of the existing plant control systems, the available options, and the benefits and consequences of these options. (authors)

  11. Technical Proposal Salton Sea Geothermal Power Pilot Plant Program

    Energy Technology Data Exchange (ETDEWEB)

    None

    1975-03-28

    The proposed Salton Sea Geothermal Power Pilot Plant Program comprises two phases. The objective of Phase 1 is to develop the technology for power generation from high-temperature, high-salinity geothermal brines existing in the Salton Sea known geothermal resources area. Phase 1 work will result in the following: (a) Completion of a preliminary design and cost estimate for a pilot geothermal brine utilization facility. (b) Design and construction of an Area Resource Test Facility (ARTF) in which developmental geothermal utilization concepts can be tested and evaluated. Program efforts will be divided into four sub-programs; Power Generation, Mineral Extraction, Reservoir Production, and the Area Resources Test Facility. The Power Generation Subprogram will include testing of scale and corrosion control methods, and critical power cycle components; power cycle selection based on an optimization of technical, environmental and economic analyses of candidate cycles; preliminary design of a pilot geothermal-electric generating station to be constructed in Phase 2 of this program. The Mineral Extraction Subprogram will involve the following: selection of an optimum mineral recovery process; recommendation of a brine clean-up process for well injection enhancement; engineering, construction and operation of mineral recovery and brine clean-up facilities; analysis of facility operating results from environmental, economical and technical point-of-view; preliminary design of mineral recovery and brine clean-up facilities of sufficient size to match the planned pilot power plant. The Reservoir Production Subprogram will include monitoring the operation and maintenance of brine production, handling and injection systems which were built with private funding in phase 0, and monitoring of the brine characteristics and potential subsidence effects during well production and injection. Based on the above, recommendations and specifications will be prepared for production and

  12. Abnormal condition and events analysis for instrumentation and control systems. Volume 1: Methodology for nuclear power plant digital upgrades. Final report

    International Nuclear Information System (INIS)

    McKemy, S.; Marcelli, M.; Boehmer, N.; Crandall, D.

    1996-01-01

    The ACES project was initiated to identify a cost-effective methodology for addressing abnormal conditions and events (ACES) in digital upgrades to nuclear power plant systems, as introduced by IEEE Standard 7-4.3.2-1993. Several methodologies and techniques currently in use in the defense, aerospace, and other communities for the assurance of digital safety systems were surveyed, and although several were shown to possess desirable qualities, non sufficiently met the needs of the nuclear power industry. This report describes a tailorable methodology for performing ACES analysis that is based on the more desirable aspects of the reviewed methodologies and techniques. The methodology is applicable to both safety- and non-safety-grade systems, addresses hardware, software, and system-level concerns, and can be applied in either a lifecycle or post-design timeframe. Employing this methodology for safety systems should facilitate the digital upgrade licensing process

  13. Upgrade of DIII-D toroidal magnetic field power supply controls

    International Nuclear Information System (INIS)

    Petrach, P.M.; Rouleau, A.R.; McNulty, R.D.; Patrick, D.B.; Walin, J.L.

    1993-11-01

    The toroidal magnetic field power supply for the DIII-D tokamak is of the 12 pulse line commutated variety. It consists of four individual modules and a main system control cabinet which are combined to deliver 127,000 A and 1000 V to the toroidal field coil. The modules are connected in a series-parallel configuration but can be run alone or two at a time as well. Normally on DIII-D experiments, the series-parallel configuration is required. The original design provided each individual module with its own voltage and current control loop and a main control loop. A problem with this design was that the individual control loops would cause a current sharing imbalance in the parallel modules if the calibrated loops drifted by the slightest amount. It was determined that individual control loops were not needed and a single phase lock firing circuit was employed in the system cabinet with fiber optic links to the modules for gate drive signals. Since all four modules have to be on line for DIII-D to operate, a problem in any of the five E ampersand I control loops resulted in the supply, and, therefore, the tokamak, being idled. By reducing the number of control loops to one, the sharing problem was eliminated, as well as 4 out of 5 potential control failures. The original supply employed relay logic for sequence control and fault monitoring. There were over 130 relays in each module plus an additional 100 in the system cabinet. The combination of the number of relays with the required interconnecting wiring, the age of the supply, the vibrations of the cabinets and the harsh environment, resulted in a continuously escalating number of phantom, and often intermittent, faults. The fault and sequence logic relays were replaced by a new Programmable Logic Controller (PLC). All existing interconnect wire was removed and replaced with multiconductor cables that connect directly from fault sensors and input devices to the PLC

  14. Geothermal electric power generation in Iceland for the proposed Iceland/United Kingdom HVDC power link

    International Nuclear Information System (INIS)

    Hammons, T.J.; Palmason, G.; Thorhallsson, S.

    1991-01-01

    The paper reviews geothermal electric power potential in Iceland which could economically be developed to supplement hydro power for the proposed HVDC Power Link to the United Kingdom, and power intensive industries in Iceland, which are envisaged for development at this time. Technically harnessable energy for electricity generation taking account of geothermal resources down to an assumed base depth, temperature distribution in the crust, probable geothermal recovery factor, and accessibility of the field, has been assessed. Nineteen known high-temperature fields and 9 probable fields have been identified. Technically harnessable geo-heat for various areas is indicated. Data on high temperature fields suitable for geothermal electric power generation, and on harnessable energy for electric power generation within volcanic zones, is stated, and overall assessments are made. The paper then reviews how the potential might be developed, discussing preference of possible sites, and cost of the developments at todays prices. Cost of geothermal electric power generation with comparative costs for hydro generation are given. Possible transmission system developments to feed the power to the proposed HVDC Link converter stations are also discussed

  15. A novel powering scheme based on DC-DC conversion for the luminosity upgrades of the CMS tracking system at CERN

    International Nuclear Information System (INIS)

    Sammet, Jan

    2014-01-01

    The instantaneous luminosity of the LHC is expected to reach 2 x 10 34 s -1 cm -2 and 5 x 10 34 s -1 cm -2 around the years 2019 and 2024, respectively. After the second upgrade the LHC will be referred to as the High Luminosity LHC (HL-LHC). In order to benefit from the higher luminosities, CMS foresees to upgrade its pixel detector during an extended winter shutdown of the LHC at the end of 2016 and the beginning of 2017. During a long shutdown of the LHC over the years 2022 and 2023, it is foreseen to install a completely new tracking system in CMS. Both upgrades are expected to result in the need to provide more electric current to the detector. However, power losses in cables already contribute 50% to the power consumption of the present tracker and rise with the current squared. Since no more space is available for cables, and thicker cables within the tracking volume spoil the material budget of the detector, new powering schemes are considered mandatory. CMS foresees the use of radiation tolerant DC-DC converters on the front-end to reduce power losses on cables. This thesis describes the new powering scheme of the CMS pixel detector and discusses the options with respect to a new strip tracker. A radiation and magnetic field tolerant DC-DC converter prototype, the PIXV8A, is introduced and the research that led to its development is summarised. The PIXV8A has been developed for the application in the pixel upgrade and is also a first approach for a DC-DC converter for the later upgrade of the CMS tracking system. The PIXV8A makes use of the AMIS4 chip, which has been proven to stay operational for total ionising doses of up to 1 MGy and fluences of up to 10 15 n eq /cm 2 . With an input voltage of 10 V, the PIXV8A converter provides an efficiency of about 80% for output voltages of 2.5 V and 3.0 V. Within this thesis the robustness of the novel powering scheme and the qualification of the PIXV8A are demonstrated in several tests, including system test

  16. DCS upgrades for nuclear power plants: Saving money and reducing risk through virtual-stimulation control system checkout

    International Nuclear Information System (INIS)

    McKim, G.; Yeager, M.; Weirich, C.

    2006-01-01

    Nuclear power plant control systems of 1970's vintage have reached the end of their life: reliability is poor and spare parts are hard to come by. At First Energy Perry station, two costly feedwater system trips caused by an ailing analog control system led to the decision to replace it with a modern Foxboro I/A-series Distributed Control System. The simulator was also upgraded using the Virtual-Stim simulation of I/A, called FSIM. Virtual-Stim simulation allows the configuration and graphics from the plant to be downloaded onto the simulator as-is, using the same tools and operator interface as the plant, without imprecise translations, conversions, or other emulation. Advances in simulation technology and market forces have led to an open architecture design, allowing FSIM to be 'bridged' to Perry's existing Opensim simulator process model. This appears to be an industry-wide trend as more control system vendors offer Virtual Stimulation solutions for connection to third-party simulation products. Taking a cue from First Energy's Sammis Station FSIM simulator projects, the Perry simulator was used for dedicated control verification and tuning. Preventing forced outages caused by control configuration errors can result in enormous savings, and the simulator is now required to precede any plant modifications rather than just a training tool that lags the plant. This testing revealed several surprising results for a relatively straightforward control strategy, showing that simulator-based testing will be even more crucial in the future as the remain-der of the balance of plant is migrated to digital control. (author)

  17. Upgrade the intervention levels derived for water and foods, to be include in the PERE 607 procedure the external radiological emergency plan in the Laguna Verde nuclear power plant

    International Nuclear Information System (INIS)

    Llado Castillo, R.; Aguilar Pacheco, R.

    1998-01-01

    The work shows the results obtained in the upgrade the intervention levels derived for water and foods, to be include in the PERE 607 procedure the external radiological emergency plan in the Laguna Verde nuclear power plant

  18. Proposal of modification of the Atucha I nuclear power plant's emergency power supply system

    International Nuclear Information System (INIS)

    Palacio, Pedro; Dabove, Mario

    1989-01-01

    The emergency power supply system of Atucha I N.P.P. consists of three 50% diesel generators. During the transient from normal power supply to emergency power supply (approximately 15 seconds) an hydraulic generator takes care of the emergency system. By this way, the emergency busbars constitute themselves an interruption free system. The two emergency busbars work normally coupled. This proposal consists of the following modifications: 1) Add a new diesel generator in order to allow the operation with two diesel generators per busbar. 2) To work with the two emergency busbars not coupled as normal operation mode. 3) To eliminate the hydraulic generator from the emergency power supply system, in order to simplify the operation and to reduce the failure possibility. Without the hydraulic turbine generator, the emergency busbars loose the interruption free condition. For this reason, for the loads that are not able for this mode of operation and are connected to the emergency power supply system, two additional low-voltage interruption free busbars are necessary. Finally, this proposal is compared with the Atucha II N.P.P. emergency power supply system. (Author)

  19. Specification of requirements for upgrades using digital instrument and control systems. Report prepared within the framework of the international working group on nuclear power plant control and instrumentation

    International Nuclear Information System (INIS)

    1999-01-01

    The need to develop good specifications of requirements for instrument and control (I and C) systems applies throughout the world and is becoming more and more important as more upgrades are planned. Better guidance on how to develop good requirements specifications would support safer, more effective and more economical refits and upgrades. The need for this was pointed out by the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI). This report is the result of a series of advisory and consultants meetings held by the IAEA in 1997 and 1998 in Vienna. The scope of the activities described covers a methodology for the determination of requirements and the development of the necessary specifications and plans needed through the life-cycle of digital instrumentation and control systems. It is restricted to technical aspects and indicates subjects which should be included in specifications and plans at different phases

  20. Reflective memory recorder upgrade: an opportunity to benchmark PowerPC and Intel architectures for real time

    Science.gov (United States)

    Abuter, Roberto; Tischer, Helmut; Frahm, Robert

    2014-07-01

    quantitative comparison between the two implementations (PowerPC14 and Intel Multicore20, 15) under different workloads will be presented. In particular, the interrupt handling, the reflective memory access, DMA readout, and TCP stack performances will be compared. To test the limits of the new hardware, the separation, on the different cores, of each of the basic tasks, as the readout, the network transfer, etc, were implemented and throughput reevaluated. The result shows that the RMN recorder1 can extend its operational range from 10 KHz to above 16 KHz by moving from a PowerPC14 to Intel Multicore20, 15. In general, a reduction of latencies and computational delays of could be expected by upgrading applications to Intel Multicore20, 15 architectures.

  1. Environmental Assessment for Electrical Power System Upgrades at Los Alamos National Laboratory, Los Alamos, New Mexico - Final Document

    Energy Technology Data Exchange (ETDEWEB)

    N/A

    2000-03-09

    The ''National Environmental Policy Act of 1969'' (NEPA) requires Federal agency officials to consider the environmental consequences of their proposed actions before decisions are made. In complying with NEPA, the United States (U.S.) Department of Energy (DOE) follows the Council on Environmental Quality (CEQ) regulations (40 Code of Federal Regulations [CFR] 1500-1508) and DOE's NEPA implementing procedures (10 CFR 1021). The purpose of an Environmental Assessment (EA) is to provide Federal decision makers with sufficient evidence and analysis to determine whether to prepare an Environmental Impact Statement (EIS) or issue a Finding of No Significant Impact. In this case, the DOE decision to be made is whether to construct and operate a 19.5-mile (mi) (31-kilometer [km]) electric transmission line (power line) reaching from the Norton Substation, west across the Rio Grande, to locations within the Los Alamos National Laboratory (LANL) Technical Areas (TAs) 3 and 5 at Los Alamos, New Mexico. The construction of one electric substation at LANL would be included in the project as would the construction of two line segments less than 1,200 feet (ft) (366 meters [m]) long that would allow for the uncrossing of a portion of two existing power lines. Additionally, a fiber optics communications line would be included and installed concurrently as part of the required overhead ground conductor for the power line. The new power line would improve the reliability of electric service in the LANL and Los Aktrnos County areas as would the uncrossing of the crossed segments of the existing lines. Additionally, installation of the new power line would enable the LANL and the Los Alamos County electric grid, which is a shared resource, to be adapted to accommodate the future import of increased power when additional power service becomes available in the northern New Mexico area. Similarly, the fiber optics line would allow DOE to take advantage of

  2. Safety assessment of proposed improvements to RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1993-03-01

    The purpose of this report is to summarize the findings and recommendations of a Consultants Meeting convened by the IAEA in Vienna (27 October - 5 November 1992) to review new design features and modifications proposed or already implemented for RBMK reactors. This information was provided in four technical areas, namely: Core Monitoring and Control, Pressure Boundary Integrity, Accident Mitigation and Electric Power Supply. The report also presents the status of the modifications at the plants as given by the RBMK specialists. The limited information available and the time constraints did not allow the review to be conducted at the level of a peer review, and the findings and recommendations made reflect the limited scope of the review. More detailed reviews and analysis focusing on selected safety issues are required and should be conducted on a generic and plant specific basis as appropriate. In Chapters 2-5 of the report the main findings and recommendations for the four topical areas reviewed are summarized. Appendices I-IV reflect the results of the discussions held at the meeting and provide more detailed information on the review. 17 refs, 27 figs, 17 tabs

  3. The role of IAEA in the seismic assessment and upgrading of existing NPPs. Seismic safety of nuclear power plants in Eastern Europe

    Energy Technology Data Exchange (ETDEWEB)

    Guerpinar, A; Godoy, A [International Atomic Energy Agency, Vienna (IAEA). Div. of Nuclear Installation Safety

    1997-03-01

    This paper summarizes the work performed by the International Atomic Energy Agency in the areas of safety reviews and applied research in support of programmes for the assessment and enhancement of seismic safety in Eastern Europe and in particular WWER type nuclear power plants during the past seven years. Three major topics are discussed; engineering safety review services in relation to external events, technical guidelines for the assessment and upgrading of WWER type nuclear power plants, and the Coordinated Research Programme on `Benchmark study for the seismic analysis and testing of WWER type nuclear power plants`. These topics are summarized in a way to provide an overview of the past and present safety situation in selected WWER type plants which are all located in Eastern European countries. Main conclusion of the paper is that although there is now a thorough understanding of the seismic safety issues in these operating nuclear power plants, the implementation of seismic upgrades to structures, systems and components are lagging behind, particularly for those cases in which the re-evaluation indicated the necessity to strengthen the safety related structures or install new safety systems. (author)

  4. The role of IAEA in the seismic assessment and upgrading of existing NPPs. Seismic safety of nuclear power plants in Eastern Europe

    International Nuclear Information System (INIS)

    Guerpinar, A.; Godoy, A.; . Div. of Nuclear Installation Safety)

    1997-01-01

    This paper summarizes the work performed by the International Atomic Energy Agency in the areas of safety reviews and applied research in support of programmes for the assessment and enhancement of seismic safety in Eastern Europe and in particular WWER type nuclear power plants during the past seven years. Three major topics are discussed; engineering safety review services in relation to external events, technical guidelines for the assessment and upgrading of WWER type nuclear power plants, and the Coordinated Research Programme on 'Benchmark study for the seismic analysis and testing of WWER type nuclear power plants'. These topics are summarized in a way to provide an overview of the past and present safety situation in selected WWER type plants which are all located in Eastern European countries. Main conclusion of the paper is that although there is now a thorough understanding of the seismic safety issues in these operating nuclear power plants, the implementation of seismic upgrades to structures, systems and components are lagging behind, particularly for those cases in which the re-evaluation indicated the necessity to strengthen the safety related structures or install new safety systems. (author)

  5. Status of TMX upgrade diagnostics construction

    International Nuclear Information System (INIS)

    Hornady, R.S.; Davis, J.C.; Simonen, T.C.

    1981-01-01

    This report describes the status of the initial TMX Upgrade diagnostics and the state of development of additional diagnostics being prepared for later TMX Upgrade experiments. The initial diagnostic instrument set has been described in the TMX Upgrade Proposal. This set is required to get TMX Upgrade operational and to evaluate its initial performance. Additional diagnostic instruments are needed to then carry out the more detailed experiments outlined by the TMX Upgrade program milestones. The relation of these new measurements to the physics program is described in The TMX Upgrade Program Plan

  6. Initial assessment: electromagnetic compatibility aspects of proposed SPS Microwave Power Transmission System (MPTS) operations

    Energy Technology Data Exchange (ETDEWEB)

    1978-02-01

    An analysis of major concerns with regard to the effects on radio and electronic systems by the proposed Microwave Power Transmission System for transmitting power from a satellite solar power station to earth is presented. (LCL)

  7. PSI: Upgrading

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    The accelerator complex at the Paul Scherrer Institute in Villigen near Zurich (PSI - formed in 1988 by combining the Federal Institute for Reactor Research and the Swiss Institute for Nuclear Research) is in the throes of a major and lengthy upgrade

  8. PSI: Upgrading

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1992-09-15

    The accelerator complex at the Paul Scherrer Institute in Villigen near Zurich (PSI - formed in 1988 by combining the Federal Institute for Reactor Research and the Swiss Institute for Nuclear Research) is in the throes of a major and lengthy upgrade.

  9. The concept of underground nuclear heat and power plants (UNHPP) of upgraded safety, developed on the basis of ship-building technologies

    International Nuclear Information System (INIS)

    Pashin, V.M.; Petrov, Eh.L.; Shalik, G.P.; Khazov, B.S.; Malyshev, S.P.

    1996-01-01

    A concept of underground nuclear heat and power plants (UNHPP) of upgraded safety on the basis of ship-building technologies is considered, in which the priority is set to population security and environmental protection. Ways of realization of ziro radiation risk for the population residing in a close vicinity of UNHPP are substantiated. basic principles of the concept are formulated which envisage the use of ship propulsion reactor facilities that have been multiply tested in operation. The sources of economic competitiveness of UNHPPs, as compared with the existing NPPs, are shown

  10. ATLAS ITk Short Strip Prototype Module with Integrated DCDC Powering and Control Phase II Upgrade of the ATLAS Inner Tracker detector at the HL - LHC

    CERN Document Server

    Greenall, Ashley; The ATLAS collaboration

    2017-01-01

    The prototype Barrel module design, for the Phase II upgrade of the of the new Inner Tracker (ITk) detector at the LHC, has adopted an integrated low mass assembly featuring single-sided flexible circuits, with readout ASICs, glued to the silicon strip sensor. Further integration has been achieved by the attachment of module DCDC powering, HV sensor biasing switch and autonomous monitoring and control to the sensor. This low mass, integrated module approach benefits further in a reduced width stave structure to which the modules are attached. The results of preliminary electrical tests of such an integrated module will be presented.

  11. Pakistan upgrades PARR-1 and converts to LEU

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    The Pakistan Research Reactor, PARR-1, is a 5MW swimming pool type reactor originally designed to use MTR type fuel elements fabricated from uranium enriched to more than 90%. After about 24 years of satisfactory operation it is now planned to convert the reactor to use low enriched (20%) uranium fuel. The opportunity will also be taken to upgrade the reactor power to about 9MW. This power upgrading will meet the demand for higher neutron fluxes for experimental and radioisotope production as well as compensating for the neutron flux penalty arising from conversion from high enriched to low enriched fuel. During the process of conversion and upgrading it is also proposed to renovate existing services and associated systems and to add certain new safety related engineering. (author)

  12. Thermal power calibration of the TRIGA Mark I IPR-R1 reactor during the upgrading tests to 250 kW

    International Nuclear Information System (INIS)

    Mesquita, Amir Zacarias; Maretti, Fausto Junior; Rezende, Hugo Cesar

    2002-01-01

    This paper presents the results and the methodology used to calibrate the thermal power of the TRIGA MARK I IPR-R1 Reactor in CDTN, Belo Horizonte, Brazil. This calibration was realized during the operation tests carried out to allow the reactor power upgrade from the current 100 kW to 250 kW. The methodology consisted in the measurement of the inlet and outlet temperature and the water flow in the primary cooling loop. The thermal balance together with the thermal losses gave the thermal power. There were made three sequences of tests. The first rising of the thermal power was made with the usual configuration of the core (59 fuel elements). After the changing of the ion chambers position and the control rod and the increase of the number of fuels (63 fuel elements), a new evaluation of the thermal power was accomplished, having been obtained a thermal power of 234 kW, for an indication of 250 kW in the lineal channel. After the return of the core to the initial configuration (59 fuel elements), it took place a new test, getting back the reactor to the power level of 100 kW. (author)

  13. Skoda JS's proposal for Slovak nuclear power industry

    International Nuclear Information System (INIS)

    Borovec, J.

    2004-01-01

    In this presentation author deals with the structure and revenues of the Skoda JS, a.s., as well as productions of the company for nuclear power industry in the Czech Republic, Ukraine and the Slovak Republic

  14. Feasibility study of upgrading Byllesby and Buck power plants on the New River in the Commonwealth of Virginia

    Energy Technology Data Exchange (ETDEWEB)

    1979-05-01

    The feasibility of upgrading alternatives of the 66-year-old Byllesby and Buck hydroelectric developments located on the New River in Virginia was investigated. Evaluation of technical, economic and environmental factors led to the conclusion that modernization of the plants could result in an annual generation increase of 20.2 GWh at a cost of $6.1 million and with a benefit-cost ratio of 2.32. The recommended retrofitting includes replacing existing runners with new, more efficiently designed runners, modifying draft tube and wicker gate, and rewinding the generators. (LCL)

  15. Design, Fabrication and High Power RF Test of a C-band Accelerating Structure for Feasibility Study of the SPARC photo-injector energy upgrade

    CERN Document Server

    Alesini, D.; Di Pirro, G.; Di Raddo, R.; Ferrario, M.; Gallo, A.; Lollo, V.; Marcellini, F.; Higo, T.; Kakihara, K.; Matsumoto, S.; Campogiani, G.; Mostacci, A.; Palumbo, L.; Persichelli, S.; Spizzo, V.; Verdú-Andrés, S.

    2011-01-01

    The energy upgrade of the SPARC photo-injector from 160 to more than 260 MeV will be done by replacing a low gradient 3m S-Band structure with two 1.4m high gradient C-band structures. The structures are travelling wave, constant impedance sections, have symmetric waveguide input couplers and have been optimized to work with a SLED RF input pulse. A prototype with a reduced number of cells has been fabricated and tested at high power in KEK (Japan) giving very good performances in terms of breakdown rates (10^6 bpp/m) at high accelerating gradient (>50 MV/m). The paper illustrates the design criteria of the structures, the fabrication procedure and the high power RF test results.

  16. Some consideration on nuclear power development. Topics aroused by U.S. proposed 'Generation IV Nuclear Power System

    International Nuclear Information System (INIS)

    Wang Chuanying; Chen Shiqi

    2001-01-01

    U.S. proposed 'Generation IV Nuclear Power System' concept. Its origin and proposed goals for it are analyzed; goals are compared with requirements of URD. In particular, discussed issues on nuclear fuel cycle and Non-proliferation. A well-considered nuclear power development plan, paying close attention to international trend and considering comprehensively domestic situation, is expected

  17. LHCb: Fast Readout Control for the upgraded readout architecture of the LHCb experiment at CERN

    CERN Multimedia

    Alessio, F

    2013-01-01

    The LHCb experiment at CERN has proposed an upgrade towards a full 40 MHz readout system in order to run between five and ten times its initial design luminosity with an upgraded LHCb detector. As a consequence, the various LHCb sub-systems in the readout architecture will be upgraded to cope with higher sub-detector occupancies, higher rate, and higher readout load. The new architecture, new functionalities, and the first hardware implementation of a new LHCb Readout Control system (commonly referred to as S-TFC) for the upgraded LHCb experiment is here presented. Our attention is focused in describing solutions for the distribution of clock and timing information to control the entire upgraded readout architecture by profiting of a bidirectional optical network and powerful FPGAs, including a real-time mechanism to synchronize the entire system. Solutions and implementations are presented, together with first results on the simulation and the validation of the system.

  18. Proposal for the award of a contract, without competitive tendering, for the supply and upgrade of positioning sensors for the LHC

    CERN Document Server

    2004-01-01

    This document concerns the award of a contract, without competitive tendering, for the supply of 60 new Hydrostatic Leveling Systems (HLS sensors) and 25 new Wire Positioning Systems (WPS sensors) and for the upgrade of 63 existing sensors. For the reasons explained in this document, the Finance Committee is invited to agree to the negotiation of a contract with FOGALE NANOTECH (FR), for the supply and upgrade of HLS and WPS sensors for a total amount of 412 913 euros (631 757 Swiss francs), not subject to revision. The amount in Swiss francs has been calculated using the present rate of exchange.

  19. 75 FR 36659 - Proposed Collection; Comment Request; Brain Power! The NIDA Junior Scientist Program and the...

    Science.gov (United States)

    2010-06-28

    ... of the Brain Power! Program's ability to: Increase students' knowledge about the biology of the brain... Request; Brain Power! The NIDA Junior Scientist Program and the Companion Program, Brain Power! Challenge.... Proposed Collection: Title: Brain Power! The NIDA Junior Scientist Program, for grades K-5, and the...

  20. Sizewell: proposed site for Britain's first PWR power station

    International Nuclear Information System (INIS)

    1980-10-01

    The pamphlet covers the following points, very briefly: nuclear power - a success story; the Government's nuclear programme; why Sizewell; the PWR (with diagram); the PWR at Sizewell (with aerial view) (location; size; cooling water; road access; fuel transport; construction; employment; environment; screening; the next steps (licensing procedures, etc.); safety; further information). (U.K.)

  1. OMEGA Upgrade preliminary design

    International Nuclear Information System (INIS)

    Craxton, R.S.

    1989-10-01

    The OMEGA laser system at the Laboratory for Laser Energetics of the University of Rochester is the only major facility in the United States capable of conducting fully diagnosed, direct-drive, spherical implosion experiments. As such, it serves as the national Laser Users Facility, benefiting scientists throughout the country. The University's participation in the National Inertial Confinement Fusion (ICF) program underwent review by a group of experts under the auspices of the National Academy of Sciences (the Happer Committee) in 1985. The Happer Committee recommended that the OMEGA laser be upgraded in energy to 30 kJ. To this end, Congress appropriated $4,000,000 for the preliminary design of the OMEGA Upgrade, spread across FY88 and FY89. This document describes the preliminary design of the OMEGA Upgrade. The proposed enhancements to the existing OMEGA facility will result in a 30-kHJ, 351-nm, 60-beam direct-drive system, with a versatile pulse-shaping facility and a 1%--2% uniformity of target drive. The Upgrade will allow scientists to explore the ignition-scaling regime, and to study target behavior that is hydrodynamically equivalent to that of targets appropriate for a laboratory microfusion facility (LMF). In addition, it will be possible to perform critical interaction experiments with large-scale-length uniformly irradiated plasmas

  2. Proposed law concerning the phase-out of nuclear power

    International Nuclear Information System (INIS)

    1997-01-01

    This Government bill that will be presented to the Swedish Parliament, gives the Government the right to revoke the licence of operating a nuclear power plant at a certain time. The operator is given the right to a financial compensation when the licence is revoked, in line with the rules in the expropriation laws. Safety aspects of operation of nuclear installations are not regulated in this law, i.e. the law can not be used when the operating licence is revoked due to safety reasons

  3. Questions to the reactors power upgrade of the Nuclear Power Plant of Laguna Verde; Cuestionamientos al aumento de potencia de los reactores de la Central Nuclear de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Salas M, B., E-mail: salasmarb@yahoo.com.mx [UNAM, Facultad de Ciencias, Departamento de Fisica, Circuito exterior s/n, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2014-08-15

    The two reactors of the Nuclear Power Plant of Laguna Verde (NPP-L V) were subjected to power upgrade labors with the purpose of achieving 20% upgrade on the original power; these labors concluded in August 24, 2010 for the Reactor 1 and in January 16, 2011 for the Reactor 2, however in January of 2014, the NNP-L V has not received by part of the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) the new Operation License to be able to work with the new power, because it does not fulfill all the necessary requirements of safety. In this work is presented and analyzed the information obtained in this respect, with data provided by the Instituto Federal de Acceso a la Informacion Publica y Proteccion de Datos (IFAI) and the Comision Federal de Electricidad (CFE) in Mexico, as well as the opinion of some workers of the NPP-L V. The Governing Board of the CFE announcement that will give special continuation to the behavior on the operation and reliability of the NPP-L V, because the frequency of not announced interruptions was increased 7 times more in the last three years. (Author)

  4. Experience from design, prototyping and production of a DC-DC conversion powering scheme for the CMS Phase-1 Pixel Upgrade

    International Nuclear Information System (INIS)

    Feld, L.; Karpinski, W.; Klein, K.; Lipinski, M.; Preuten, M.; Rauch, M.; Schmitz, S.; Wlochal, M.

    2016-01-01

    The CMS collaboration has adopted a DC-DC conversion powering scheme for the Phase-1 Upgrade of its pixel detector. DC-DC buck converters with a conversion ratio of around 3 are installed on the support structures, outside of the sensitive tracking region, requiring a re-design of the low and high voltage distribution to the pixel modules. After several years of R and D, the project has entered the production phase. A total of 1800 DC-DC converters are being produced, and rigorous quality assurance and control is being employed during the production process. The testing program is outlined, results from mass production are presented and issues that have been encountered are described. In addition, two system level challenges, namely the choice of output voltage in the presence of large, load-dependent voltage drops, and the thermal management required to remove the heat load caused by the DC-DC converters, are discussed

  5. Upgrade of the AGS H- linac

    International Nuclear Information System (INIS)

    Alessi, J.G.; Buxton, W.; Kponou, A.; LoDestro, V.; Mapes, M.; McNerney, A.J.; Raparia, D.

    1994-01-01

    The AGS linac presently accelerates 25 mA of H - to 200 MeV at a 5 Hz rep-rate and 500 μs pulse width. The Booster takes 4 pulses every 3.8 seconds, and the remaining pulses are used for isotope production. The authors are in the process of upgrading the linac to increase the average current delivered for isotope production by more than a factor of two, while at the same time expecting to decrease linac downtime. Various aspects of this upgrade are discussed, including the upgrade of the control system, new high power transmission line, transport line vacuum, and rf power supply system upgrades

  6. High voltage multiplexing for the ATLAS Tracker Upgrade

    International Nuclear Information System (INIS)

    Villani, E G; Phillips, P; Matheson, J; Lynn, D; Hommels, L B A; Gregor, I; Bessner, M; Tackmann, K; Newcomer, F M; Spencer, E; Greenall, A

    2014-01-01

    The increased luminosity of the HL-LHC will require more channels in the upgraded ATLAS Tracker, as a result of the finer detector segmentation, stemming from the otherwise too high occupancy. Among the many technological challenges facing the ATLAS Tracker Upgrade there is more an efficient power distribution and HV biasing of the sensors. The solution adopted in the current ATLAS detector uses one HV conductor for each sensor, which makes it easy to disable malfunctioning sensors without affecting the others, but space constraints and material budget considerations renders this approach impractical for the Upgraded detector. A number of approaches, including the use of the same HV line to bias several sensors and suitable HV switches, along with their control circuitry, are currently being investigated for this purpose. The proposed solutions along with latest test results and measurements will be described

  7. Current radiography and tomography applications at Necsa and an envisaged upgrade towards a proposed South African national centre for radiography and tomography (SANCRAT)

    International Nuclear Information System (INIS)

    Radebe, M.J.; De Beer, F.C.

    2008-01-01

    An upgrade of the current Radiography and Tomography Research facilities is envisaged to enhance the group's support for Necsa's mission to undertake and support nuclear research and utilize penetrating radiation for the benefit of mankind. It is envisage that the SANCRAT will host neutron-, X-ray- and gamma ray penetrating radiation imaging infrastructures that can be utilized by researchers from industry as well as post graduate students from higher educational institutions. Modelling for the upgrade to a multifunctional neutron radiography and tomography facility has been underway. Upgrade plans and implementation has also begun for a 250 kV X-ray radiography set-up, that will exist independent from the neutron facility. Future expansion entails catering for a micro-focus X-ray -, and gamma ray radiography and tomography facilities. The current facilities available consist of one infrastructure facility based on two sources of penetrating radiation, i.e. SAFARI-1 research nuclear reactor as thermal neutron source and a 100 kV X-ray generator. This facility, which hosts the only operational neutron tomography R and D facility in the Southern Hemisphere and in Africa, are being extensively utilized by post graduate students and industry. The facility sees application in a wide range of scientific and engineering disciplines, amongst which is nuclear, geosciences, palaeontology, civil, mechanical, chemical, etc. This paper focus on case studies engaged at the current radiography and tomography facilities over the past 2 years as well as describing the envisaged upgrade initiatives to a fully equipped national centre. (authors)

  8. Current radiography and tomography applications at Necsa and an envisaged upgrade towards a proposed South African national centre for radiography and tomography (SANCRAT)

    Energy Technology Data Exchange (ETDEWEB)

    Radebe, M.J.; De Beer, F.C. [Necsa - South African Nuclear Energy Corporation Limited, P. O.Box 582, Pretoria, 0001 (South Africa)

    2008-07-01

    An upgrade of the current Radiography and Tomography Research facilities is envisaged to enhance the group's support for Necsa's mission to undertake and support nuclear research and utilize penetrating radiation for the benefit of mankind. It is envisage that the SANCRAT will host neutron-, X-ray- and gamma ray penetrating radiation imaging infrastructures that can be utilized by researchers from industry as well as post graduate students from higher educational institutions. Modelling for the upgrade to a multifunctional neutron radiography and tomography facility has been underway. Upgrade plans and implementation has also begun for a 250 kV X-ray radiography set-up, that will exist independent from the neutron facility. Future expansion entails catering for a micro-focus X-ray -, and gamma ray radiography and tomography facilities. The current facilities available consist of one infrastructure facility based on two sources of penetrating radiation, i.e. SAFARI-1 research nuclear reactor as thermal neutron source and a 100 kV X-ray generator. This facility, which hosts the only operational neutron tomography R and D facility in the Southern Hemisphere and in Africa, are being extensively utilized by post graduate students and industry. The facility sees application in a wide range of scientific and engineering disciplines, amongst which is nuclear, geosciences, palaeontology, civil, mechanical, chemical, etc. This paper focus on case studies engaged at the current radiography and tomography facilities over the past 2 years as well as describing the envisaged upgrade initiatives to a fully equipped national centre. (authors)

  9. Principles, Methods of Participatory Research: Proposal for Draft Animal Power

    Directory of Open Access Journals (Sweden)

    E. Chia

    2004-03-01

    Full Text Available The meeting of researchers, who question themselves on the efficiency of their actions when they accompany stakeholders during change processes, provides the opportunity to ponder on the research methods to develop when working together with the stakeholders: participative research, research-action, research-intervention… The author proposes to present the research-action approach as new. If the three phases of research-action are important, the negotiation phase is essential, because it enables contract formalization among partners (ethical aspect, development of a common language, and formalization of structuring efforts between researchers with various specialties and stakeholders. In the research-action approach, the managing set-ups (scientific committees… play a major role: they guarantee at the same time a solution to problems, production, and the legitimacy of the scientific knowledge produced. In conclusion, the author suggests ways to develop research-action in the field of animal traction in order to conceive new socio-technical and organizational innovations that will make the use of this technique easier.

  10. Tandem mirror experiment-upgrade neutral beam test stand: a powerful tool for development and quality assurance

    International Nuclear Information System (INIS)

    Hibbs, S.M.; Kane, R.J.; Kerr, R.G.; Poulsen, P.

    1983-01-01

    During construction of the Tandem Mirror Experiment-Upgrade (TMX-U), we assembled a test stand to develop electronics for the neutral beam system. In the first six months of test stand use we operated a few neutral beam injector modules and directed considerable effort toward improving the electronic system. As system development progressed, our focus turned toward improving the injector modules themselves. The test stand has proved to be the largest single contributor to the successful operation of neutral beams on TMX-U, primarily because it provides quality assurance andd development capability in conjunction with the scheduled activities of the main experiment. This support falls into five major categories: (1) electronics development, (2) operator training, (3) injector module testing and characterization, (4) injector module improvements, and (5) physics improvements (through areas affected by injector operation). Normal day-to-day operation of the test stand comes under the third category, testing and characterization, and comprises our final quality assurance activity for newly assembled or repaired modules before they are installed on TMX-U

  11. Tandem Mirror Experiment-Upgrade neutral beam test stand: A powerful tool for development and quality assurance

    International Nuclear Information System (INIS)

    Hibbs, S.M.; Kane, R.J.; Kerr, R.G.; Poulsen, P.

    1983-01-01

    During construction of the Tandem Mirror Experiment-Upgrade (TMX-U), a test stand was assembled to develop electronics for the neutral beam system. In the first six months of test stand use the authors operated a few neutral beam injector modules and directed considerable effort toward improving the electronic system. As system development progressed, the focus turned toward improving the injector modules themselves. The test stand has proved to be the largest single contributor to the successful operation of neutral beams on TMX-U, primarily because it provides quality assurance and development capability in conjunction with the scheduled activities of the main experiment. This support falls into five major categories: (1) electronics development, (2) operator training, (3) injector module testing and characterization, (4) injector module improvements, and (5) physics improvements (through areas affected by injector operation). Normal day-to-day operation of the test stand comes under the third category, testing and characterization, and comprises the final quality assurance activity for newly assembled or repaired modules before they are installed on TMX-U. They have also used the test stand to perform a series of physics experiments, including: reducing gas flow through valve and arc chamber characterization, reducing impurities by titanium gettering, and reducing streaming gas using apertures and collisional gas dynamics

  12. Proposal to market Provo River Project power, Salt Lake City area

    International Nuclear Information System (INIS)

    1995-01-01

    This report is an environmental assessment of the Western Area Power Administrations's proposal to change the way in which the power produced by the Provo River Project (PRP) is marketed. The topics of the report include the alternatives to the proposed action that have been considered, a description of the environmental consequences of the proposed action and the alternatives that were considered, and other environmental considerations

  13. Commissioning and operation of 130 kV/130 A switched-mode HV power supplies with the upgraded JET neutral beam injectors

    International Nuclear Information System (INIS)

    Edwards, D.C.; Bigi, M.; Brown, D.P.D.; Ganuza, D.; Garcia, F.; Hudson, Z.; Jones, T.T.C.; Perez, A.

    2005-01-01

    The design features, on-site testing, commissioning and operation are described of two new 130 kV/130 A HV power supply units serving four upgraded 130 kV/60 A positive ion neutral injectors (PINIs) on JET. Both units were factory tested at full power and pulse length into dummy resistive load. Following on-site installation, the factory tests were repeated. The transition from dummy-load testing to PINI operation required full integration of the HVPS within the overall JET control system, and rigorous testing of the co-ordinated actions and protections of all PINI power supplies (filament and arc for plasma source and negative suppression grid). The implementation of these functions is described. Extensive use was made of parasitic integrated test pulses, where the other PINIs could be operated normally, with the HVPS energised under full remote control together with the corresponding PINI plasma sources, but with the HVPS connected to dummy load. The amount of NB operation time dedicated to commissioning was thereby minimised, yet gave a high degree of confidence of readiness for HV energisation of the PINI, and first beam operation followed less than 24 h from HV connection to the PINI. The routine operating experience and performance, including load protection characteristics of the new HVPS units are also described

  14. Safety assessment of proposed modifications of Ignalina nuclear power plant. A publication of the extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1995-09-01

    The objective of the meeting was to further discuss previous findings and recommendations and their application to the particular situation of the Ignalina NPP. Since design information and a series of proposed modifications for INPP had been prepared by the main RBMK designer, Research and Development Institute for Power Engineering (RDIPE), it was considered appropriate to conduct the meeting in two parts, the first from 17 to 22 October 1994, at RDIPE headquarters in Moscow and the second from 24 to 28 October 1994, at the plant site in Lithuania. Twelve international experts and IAEA staff participated in the meetings, together with a large group of RDIPE specialists and plant staff. The review covered five topical areas: core monitoring and control; pressure boundary integrity; accident migration; safety and support systems and instrumentation and control. A summary of the reviews in each technical areas is given in this report. Appendices 1 and 5 present the records of the reviews and detailed findings and recommendations in each topical area. The experts strongly supported the effort to develop a new extended safety analysis report. They also stressed the need for close monitoring of the fuel channel conditions and the need for an integrated approach for the upgrading of the control and safety systems. Refs, figs, tabs

  15. The D0 upgrade

    International Nuclear Information System (INIS)

    Tuts, P.M.

    1992-10-01

    The original D0 detector was proposed in 1983, with a focus on high P T physics using precision measurements of e's, μ's, jets, and missing E T . This detector, as of the summer of 1992, has started data taking at the Fermilab Collider. However, by 1995/6 the luminosity will reach 10 31 cm -2 sec -1 , and the minimum bunch spacing will drop to 396ns from the present 3.5μs (by the Main Injector era, luminosities will approach 10 32 cm -2 sec -1 and minimum bunch spacings may reach 132ns). These changes in the accelerator conditions force us to upgrade or replace a number of detector subsystems in order to meet these new demands. In addition, the upgrade offers us the opportunity to expand the physics horizons to include not only the all important high P T physics menu, but also the low P T physics that has become increasingly important. In this paper we describe the D0 detector upgrade

  16. Actuator management for ECRH at ASDEX Upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Rapson, Christopher J., E-mail: chris.rapson@ipp.mpg.de; Reich, Matthias; Stober, Joerg; Treutterer, Wolfgang

    2015-10-15

    Highlights: • Real-time actuator management algorithm developed for ECRH at ASDEX Upgrade. • First use of a control hierarchy in a fusion experiment. • Cost function evaluates optimal combination of all gyrotrons to all possible targets. • Considers many factors e.g. mirror movement, power available, presence and mode number of NTMs. • Configurable, robust algorithm is ready for online testing. - Abstract: Automated actuator management will be necessary on long pulse fusion experiments to adjust to unforeseen plasma events and unpredictable actuator availability. However, as a control problem, actuator management is underdeveloped in the fusion community. This contribution proposes an algorithm based on a control hierarchy and a cost function to optimally allocate scarce actuator resources to various objectives in real-time. Details are given on the development and offline testing which have been completed ready for deployment at ASDEX Upgrade. Electron Cyclotron Resonance Heating (ECRH) is particularly relevant for actuator management due to its localised deposition which can flexibly target specific regions of the plasma for different effects such as non-inductive current drive, impurity regulation, control of MHD modes and of course heating. A further motivation is that automated actuator management will simplify the setup of ECRH, in keeping with the long term goal of integrating MHD control as a routine part of ASDEX Upgrade experiments.

  17. Actuator management for ECRH at ASDEX Upgrade

    International Nuclear Information System (INIS)

    Rapson, Christopher J.; Reich, Matthias; Stober, Joerg; Treutterer, Wolfgang

    2015-01-01

    Highlights: • Real-time actuator management algorithm developed for ECRH at ASDEX Upgrade. • First use of a control hierarchy in a fusion experiment. • Cost function evaluates optimal combination of all gyrotrons to all possible targets. • Considers many factors e.g. mirror movement, power available, presence and mode number of NTMs. • Configurable, robust algorithm is ready for online testing. - Abstract: Automated actuator management will be necessary on long pulse fusion experiments to adjust to unforeseen plasma events and unpredictable actuator availability. However, as a control problem, actuator management is underdeveloped in the fusion community. This contribution proposes an algorithm based on a control hierarchy and a cost function to optimally allocate scarce actuator resources to various objectives in real-time. Details are given on the development and offline testing which have been completed ready for deployment at ASDEX Upgrade. Electron Cyclotron Resonance Heating (ECRH) is particularly relevant for actuator management due to its localised deposition which can flexibly target specific regions of the plasma for different effects such as non-inductive current drive, impurity regulation, control of MHD modes and of course heating. A further motivation is that automated actuator management will simplify the setup of ECRH, in keeping with the long term goal of integrating MHD control as a routine part of ASDEX Upgrade experiments.

  18. Role of advanced RF/microwave technology and high power switch technology for developing/upgrading compact/existing accelerators

    International Nuclear Information System (INIS)

    Shrivastava, Purushottam

    2001-01-01

    With the advances in high power microwave devices as well as in microwave technologies it has become possible to go on higher frequencies at higher powers as well as to go for newer devices which are more efficient and compact and hence reducing the power needs as well as space and weight requirement for accelerators. New devices are now available in higher frequency spectrum for example at C-Band, X-band and even higher. Also new devices like klystrodes/Higher Order Mode Inductive Output Tubes (HOM IOTs) are now becoming competitors for existing tubes which are in use at present accelerator complexes. The design/planning of the accelerators used for particle physics research, medical accelerators, industrial irradiation, or even upcoming Driver Accelerators for Sub Critical Reactors for nuclear power generation are being done taking into account the newer technologies. The accelerators which use magnetrons, klystrons and similar devices at S-Band can be modified/redesigned with devices at higher frequencies like X-Band. Pulsed accelerators need high power high voltage pulsed modulators whereas CW accelerators need high voltage power supplies for functioning of RF / Microwave tubes. There had been a remarkable growth in the development and availability of solid state switches both for switching the pulsed modulators for microwave tubes as well as for making high frequency switch mode power supplies. Present paper discusses some of the advanced devices/technologies in this field as well as their capability to make advanced/compact/reliable accelerators. Microwave systems developed/under development at Centre for Advanced Technology are also discussed briefly along with some of the efforts done to make them compact. An overview of state of art vacuum tube devices and solid state switch technologies is given. (author)

  19. Addressing Obsolescence in Operating Power Stations by Implementation of Safety Related Digital Upgrades Paper for Spanish Nuclear Society

    Energy Technology Data Exchange (ETDEWEB)

    Legrand, R.

    2014-07-01

    Obsolescence of Instrumentation and Controls is a major problem facing operating Nuclear Power Stations globally. AREVA is the only supplier that has supported the successful licensing, engineering, procurement, installation and commissioning of a full-scope digital Instrumentation and Control (I and C) Protection System in the United States. (Author)

  20. The Bevalac Upgrade Project

    International Nuclear Information System (INIS)

    Alonso, J.R.; Dwinell, R.D.; Feinberg, B.

    1987-03-01

    This paper describes a proposed upgrade of the Bevalac accelerator complex in which the present Bevatron is replaced with a modern, strong-focusing 17 T-m synchrotron. This new ring is designed to accelerate all ions throughout the periodic table with intensities 100 to 1000 times higher than the present Bevatron. It will also provide a substantially improved beam spill structure and will reduce operating costs. A fast extraction capability can be used to inject a future heavy ion storage ring. Pulse-to-pulse switching of energy and ion species is an important goal. The existing injectors, shielding, experimental facilities and utilities of the present Bevalac will remain substantially intact

  1. Feasibility study of the university of Utah TRIGA reactor power upgrade - Part I: Neutronics-based study in respect to control rod system requirements and design

    Directory of Open Access Journals (Sweden)

    Ćutić Avdo

    2013-01-01

    Full Text Available We present a summary of extensive studies in determining the highest achievable power level of the current University of Utah TRIGA core configuration in respect to control rod requirements. Although the currently licensed University of Utah TRIGA power of 100 kW provides an excellent setting for a wide range of experiments, we investigate the possibility of increasing the power with the existing fuel elements and core structure. Thus, we have developed numerical models in combination with experimental procedures so as to assess the potential maximum University of Utah TRIGA power with the currently available control rod system and have created feasibility studies for assessing new core configurations that could provide higher core power levels. For the maximum determined power of a new University of Utah TRIGA core arrangement, a new control rod system was proposed.

  2. 78 FR 62361 - Green Mountain Power Corporation; Vermont; Otter Creek Hydroelectric Project; Notice of Proposed...

    Science.gov (United States)

    2013-10-21

    ... Power Corporation; Vermont; Otter Creek Hydroelectric Project; Notice of Proposed Restricted Service... issuance of a new license for the Otter Creek Hydroelectric Project No. 2558. The programmatic agreement... Agreement would be incorporated into any Order issuing a license. Green Mountain Power Corporation, as...

  3. Voltage and Frequency Control for Future Power Systems: the ELECTRA IRP Proposal

    DEFF Research Database (Denmark)

    D’hulst, R.; Merino Fernandez, J.; Rikos, E.

    2015-01-01

    In this paper a high level functional architecture for frequency and voltage control for the future (2030+) power system is presented. The proposal suggests a decomposition of the present organization of power system operation into a ”web of cells”. Each cell in this web is managed by a single...

  4. Proposed Georgia-Alabama-South Carolina system power marketing policy and subsequent contracts

    International Nuclear Information System (INIS)

    1994-01-01

    This is an Environmental Assessment (Assessment) (DOE/EA-0935) evaluating the Power Marketing Policy and Subsequent Contracts between Southeastern and its customers. The Assessment evaluates two alternatives and the no action alternative. The proposed action is to market the power and energy available in the Georgia-Alabama-South Carolina System during the next ten years, with new power sales contracts of ten-year durations, to the customers set forth in Appendix A of the Assessment. In addition to the proposed alternative, the Assessment evaluates the alternative of extending existing contracts under the current marketing policy

  5. Upgrading the BEPC control system

    International Nuclear Information System (INIS)

    Yang Liping; Wang Lizheng; Liu Shiyao

    1992-01-01

    The BEPC control system has been put into operation and operated normally since the end of 1987. Three years's experience shows this system can satisfy basically the operation requirements, also exhibits some disadvantages araised from the original centralized system architecture based on the VAX-VCC-CAMAC, such as slow response, bottle neck of VCC, less CPU power for control etc.. This paper describes the method and procedure for upgrading the BEPC control system which will be based on DEC net and DEC-WS, and thus intend to upgrade the control system architecture from the centralized to the distributed and improve the integral system performance. (author)

  6. Reflections on a digital upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Tadjalli, M.

    2013-07-01

    Upon receiving US NRC's approval in 2010, the first RPS/ESPS digital upgrade using TELEPERM® XS technology was successfully installed in Spring of 2011 at the first Unit of a three-unit station, followed by the 2nd Unit installation in spring of 2012. Both Units' systems have been operating flawlessly since installation. After about two years of operation, a reflection on digital upgrades and lessons learned, from a vendor perspective, provides valuable insight for the commercial nuclear power industry.

  7. LHCb DAQ network upgrade tests

    CERN Document Server

    Pisani, Flavio

    2013-01-01

    My project concerned the evaluation of new technologies for the DAQ network upgrade of LHCb. The first part consisted in developing and Open Flow-based Clos network. This new technology is very interesting and powerful but, as shown by the results, it still needs further improvements. The second part consisted in testing and benchmarking 40GbE network equipment: Mellanox MT27500, Chelsio T580 and Huawei Cloud Engine 12804. An event-building simulation is currently been performed in order to check the feasibility of the DAQ network upgrade in LS2. The first results are promising.

  8. Space Station Freedom power - A reliability, availability, and maintainability assessment of the proposed Space Station Freedom electric power system

    Science.gov (United States)

    Turnquist, S. R.; Twombly, M.; Hoffman, D.

    1989-01-01

    A preliminary reliability, availability, and maintainability (RAM) analysis of the proposed Space Station Freedom electric power system (EPS) was performed using the unit reliability, availability, and maintainability (UNIRAM) analysis methodology. Orbital replacement units (ORUs) having the most significant impact on EPS availability measures were identified. Also, the sensitivity of the EPS to variations in ORU RAM data was evaluated for each ORU. Estimates were made of average EPS power output levels and availability of power to the core area of the space station. The results of assessments of the availability of EPS power and power to load distribution points in the space stations are given. Some highlights of continuing studies being performed to understand EPS availability considerations are presented.

  9. Applicability of the proposed evaluation method for social infrastructures to nuclear power plants

    International Nuclear Information System (INIS)

    Ichimura, Tomiyasu

    2015-01-01

    This study proposes an evaluation method for social infrastructures, and verifies the applicability of the proposed evaluation method to social infrastructures by applying it to nuclear power plants, which belong to social infrastructures. In the proposed evaluation method for social infrastructures, the authors chose four evaluation viewpoints and proposed common evaluation standards for the evaluation indexes obtained from each viewpoint. By applying this system to the evaluation of nuclear power plants, the evaluation index examples were obtained from the evaluation viewpoints. Furthermore, when the level of the common evaluation standards of the proposed evaluation method was applied to the evaluation of the activities of nuclear power plants based on the regulations, it was confirmed that these activities are at the highest level. Through this application validation, it was clarified that the proposed evaluation method for social infrastructures had certain effectiveness. The four evaluation viewpoints are 'service,' 'environment,' 'action factor,' and 'operation and management.' Part of the application examples to a nuclear power plant are as follows: (1) in the viewpoint of service: the operation rate of the power plant, and operation costs, and (2) in the viewpoint of environment: external influence related to nuclear waste and radioactivity, and external effect related to cooling water. (A.O.)

  10. A proposed strategy for power optimization of a wind energy conversion system connected to the grid

    International Nuclear Information System (INIS)

    Taraft, S.; Rekioua, D.; Aouzellag, D.; Bacha, S.

    2015-01-01

    Highlights: • Wind energy conversion based doubly fed induction generator controlled by matrix converter. • Operation at both sub and super-synchronous regions is possible with the proposed drive system. • Double the power generated by the DFIG at a twice of speed rated. • Sliding mode control is used to achieve active and reactive power control. - Abstract: Many strategies have been developed in last decade to optimize power extracted from wind energy conversion system where many of them can produce only 30% more than the rated power. With the considered strategy, the generated wind power can reach twice its nominal value using a fast and reliable fully rugged electrical control. Indeed, by employing a suitable control technique where the produced power in super-synchronous mode is derived from both the stator and the rotor. Also, the rotor provided power in this case grows up 100% comparing to stator rated power. However, this solution permits to maintain the wind energy conversion system operation in its stable area. The considered system consists of a double fed induction generator whose stator is connected directly to the grid and its rotor is supplied by matrix converter. In this paper, the sliding mode approach to achieve active and reactive power control is used. This latter is combined with de Perturbation and Observation Maximum Power Point Tracking used in the second operation zone. The obtained simulations results are assessed and carried out using Matlab/Simulink package and show the performance and the effectiveness of the proposed control

  11. LHCb VELO Upgrade

    CERN Document Server

    van Beuzekom, Martin; Ketel, Tjeerd; Gershon, Timothy; Parkes, Christopher; Reid, Matthew

    2011-01-01

    The VErtex LOcator (VELO) is a vital piece of apparatus for allowing precision measurements in hadronic physics. It provides not only superb impact parameter resolutions but also excellent momentum resolution, both important discriminating tools for precision high energy physics. This poster focuses on the R&D going into the future LHCb VELO detector. At present there are two proposed options for the upgrade; pixel chips or strip detectors. The LHCb upgrade is designed with higher luminosities and increased yields in mind. In order to get more out of the LHCb detector changes to the front end electronics will have to be made. At present, the first level hardware trigger is sets a limiting factor on the maximum efficiency for hadronic channels. As the VELO is positioned so close the proton-proton interaction region, whatever the choice of sensor, we will require efficient cooling and some proposed solutions are outlined. The LHCb TimePix telescope has had a very successful years running, with various devic...

  12. Human factors design, verification, and validation for two types of control room upgrades at a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Boring, Laurids Ronald [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-10-01

    This paper describes the NUREG-0711 based human factors engineering (HFE) phases and associated elements required to support design, verification and validation (V&V), and implementation of a new plant process computer (PPC) and turbine control system (TCS) at a representative nuclear power plant. This paper reviews ways to take a human-system interface (HSI) specification and use it when migrating legacy PPC displays or designing displays with new functionality. These displays undergo iterative usability testing during the design phase and then undergo an integrated system validation (ISV) in a full scope control room training simulator. Following the successful demonstration of operator performance with the systems during the ISV, the new system is implemented at the plant, first in the training simulator and then in the main control room.

  13. Upgrading of refrigeration units in nuclear power plant: An optimized approach to do justice to governmental restrictions

    International Nuclear Information System (INIS)

    Gregor, Klaus; Reinhart, Anton

    1998-01-01

    Stringent regulations to reduce the use of chlorofluorocarbons (CFC) and halogenated chlorofluorocarbons (HCFC) have been set into force by many European countries. A ban for new plants containing HCFCs in 2005 and a total ban of HCFCs in 2020 are discussed within the European Community. Siemens-KWU and Sulzer Escher Wyss have developed a well-proofed procedure to solve the CFC problem for existing refrigeration systems in nuclear power plants. The new refrigerants are fluorinated hydrocarbons and for the centrifugal water chiller R134a is best suited. Prior to the market introduction toxicity, short and long term health effects, inflammability and stability of R134a have been investigated. The mechanical examination included wear, corrosion, lubrication and resistance to decomposition. A well-proven procedure was established which ensures the owner of the plant and the supplier best results

  14. Energy Efficiency Upgrades for the Clinic and the Tannery and Wind Energy for Power to the Tannery

    Energy Technology Data Exchange (ETDEWEB)

    Kakoona, Jane [Native Village of Shishmaref, AK (United States); Fredenberg, Connie [Native Village of Shishmaref, AK (United States)

    2017-05-08

    Under this grant agreement, the Native Village of Shishmaref (Shishmaref) will complete weatherization retrofits to two community buildings, the Clinic and the Tannery, based on recent energy audits. Located 5 miles from the mainland, 126 miles north of Nome and 100 miles south of Kotzebue, Shishmaref sits on Sarichef Island in the Chukchi Sea. As such, Shishmaref experiences a transitional climate between the frozen Arctic and the continental Interior. Summers can be foggy, with average temperatures ranging from 47 to 54 °F (Fahrenheit); winter temperatures average -12 to 2 °F. With heating fuel costs of almost $7/gallon, the goal of this project is to reduce energy costs at the Clinic and the Tannery by at least 30 to 50% through energy efficiency and weatherization measures and through the installation of a residential-size wind turbine to supplement power for the Tannery building.

  15. Human factors design, verification, and validation for two types of control room upgrades at a nuclear power plant

    International Nuclear Information System (INIS)

    Boring, Laurids Ronald

    2014-01-01

    This paper describes the NUREG-0711 based human factors engineering (HFE) phases and associated elements required to support design, verification and validation (V&V), and implementation of a new plant process computer (PPC) and turbine control system (TCS) at a representative nuclear power plant. This paper reviews ways to take a human-system interface (HSI) specification and use it when migrating legacy PPC displays or designing displays with new functionality. These displays undergo iterative usability testing during the design phase and then undergo an integrated system validation (ISV) in a full scope control room training simulator. Following the successful demonstration of operator performance with the systems during the ISV, the new system is implemented at the plant, first in the training simulator and then in the main control room.

  16. Physical protection upgrades in Ukraine

    International Nuclear Information System (INIS)

    Djakov, A.

    1998-01-01

    The U.S. DOE is providing nuclear material safeguards assistance in both material control and accountability and in physical protection to several facilities in Ukraine. This paper summarizes the types of physical protection upgrades that have been or are presently being implemented at these facilities. These facilities include the Kiev Institute for Nuclear Research, Kharkov Institute of Physics and Technology, Sevastopol Institute of Nuclear Energy and Industry, and the South Ukraine Nuclear Power Plant. Typical upgrades include: hardening of storage areas; improvements in access control, intrusion detection, and CCTV assessment; central alarm station improvements; and implementation of new voice communication systems. Methods used to implement these upgrades and problems encountered are discussed. Training issues are also discussed

  17. Recovery Act. Tapoco project. Cheoah upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Tran, Paul [Alcoa Inc., Alcoa Center, PA (United States)

    2013-10-02

    Under Funding Opportunity Announcement Number: DE-FOA-0000120, Recovery Act: Hydroelectric Facility Modernization, Alcoa Power Generating Inc. (APGI), a fully owned subsidiary of Alcoa Inc., implemented major upgrades at its Cheoah hydroelectric facility near Robbinsville, North Carolina.

  18. Safety upgrades of NPPs in Slovakia

    International Nuclear Information System (INIS)

    Ziakova, M.

    2013-01-01

    In this presentation Mrs. Marta Ziakova (Chairperson od Nuclear Regulatory Authority of the Slovak Republic) deals with the safety upgrades of nuclear power plants and radioactive wastes technologies in the Slovak Republic. Safety improvement activities are reviewed.

  19. The TACIS Nuclear Programme: Assistance in Upgrading Russian Nuclear Power Stations - An Overview of the Individual Projects in the Internet

    International Nuclear Information System (INIS)

    Bieth, Michel; Schoels, Hubert

    2006-01-01

    The European Union' TACIS1 programme has been established for the New Independent States (NIS), among them in the Russian Federation since 1991. One priority of TACIS funding is Nuclear Safety. The European Commission has made available a total of 944 Million Euros for nuclear safety programmes covering the period 1991-2003. The TACIS nuclear safety programme is devoted to the improvement of the safety of Soviet designed nuclear installations in providing technology and safety culture transfer. JRC is carrying out works in the following areas: On-Site Assistance for TACIS operating Nuclear Power Plants; Design Safety and Dissemination of TACIS results; Reactor Pressure Vessel Embrittlement for VVER; Regulatory Assistance; Industrial Waste Management; Nuclear Safeguards; All TACIS projects, dealing with these areas of activity are now available in so called Project Description Sheets (PDS) or Project Results Sheets (PRS) in the Internet for everybody. JRC has created in the Internet an easy to open and to browse database which contains the result of works in relation to the above mentioned nuclear activities. This presentation gives an on-line overview of the app. 430 projects which have been implemented so far since the outset of the TACIS Nuclear Programme in the Russian Federation, which is representative to the other CIS countries, benefiting from the TACIS. The presentation will mainly consist of an on-line-demonstration of the TACIS Nuclear WEB Page, created by JRC. (authors)

  20. Hydrogen assisted biological biogas upgrading

    DEFF Research Database (Denmark)

    Bassani, Ilaria

    Wind and biomass are promoted worldwide as sustainable forms of energy. Anaerobic digestion of biomass produces biogas with ∼50−70% CH4 and 30−50% CO2. However, biogas with >90% CH4 content has higher heating value, can be injected into the natural gas grid or used as alternative to natural gas...... as vehicle fuel. Methods currently available for biogas upgrading mainly consists of physicochemical CO2 removal, requiring the use of chemical substances and energy input and, thus, increasing process costs. This PhD project proposes an alternative to existing biogas upgrading technologies, where H2......, produced by water electrolysis, using excess of electricity from wind mills, is coupled with the CO2 contained in the biogas to convert them to CH4. This process is defined as biological biogas upgrading and is carried out by hydrogenotrophic methanogenic archaea that couples CO2 with H2 to produce...

  1. A strategy for upgrading management of spent fuel and radioactive waste at the Ignalina nuclear power plant

    International Nuclear Information System (INIS)

    Balan, V.; Penkov, V.; Bergman, C.; Gustafsson, B.

    2001-01-01

    The waste management strategy of the former Soviet Union, based on its Norms and Rules, was implemented at Ignalina nuclear power Plant (INPP). This means in brief that the spent nuclear fuel (SNF) should be reprocessed in the Soviet Union and the management of radioactive waste should be done in connection with the eventual decommissioning of the reactors, The major facilities for management of radioactive waste were evaporation of liquid waste and subsequent bitumenisation of the sludge, treatment of liquid with ion-exchange techniques and subsequent storage of the resins in tanks. Solid waste was sorted according to its activity content and stored on site. Following the independence of Lithuania in 1990, Lithuania is successively replacing the former Norms and Rules with Lithuanian laws and regulations. Lithuania has signed both the Convention of Nuclear Safety and the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The paper will give an overview of the work done, in progress and planned, primarily from an operational point of view. It will give examples of practical problems which have to be overcome and how very tough prioritisation has to be made because of lack of resources. Many of the problems are associated with the fact that the waste management strategy successively has to be changed at the same time as the generation of SNF and radioactive waste is continued. A lot has already been achieved, especially regarding the SNF. However, the main work is still to be done until the INPP can declare that its waste is properly managed in full compliance with a national waste management strategy which eventually will end with the disposal in licensed repositories. (author)

  2. ISTTOK control system upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Ivo S., E-mail: ivoc@ipfn.ist.utl.pt; Duarte, Paulo; Fernandes, Horácio; Valcárcel, Daniel F.; Carvalho, Pedro J.; Silva, Carlos; Duarte, André S.; Neto, André; Sousa, Jorge; Batista, António J.N.; Carvalho, Bernardo B.

    2013-10-15

    Highlights: •ISTTOK fast controller. •All real-time diagnostic and actuators were integrated in the control platform. •100 μs control cycle under the MARTe framework. •The ISTTOK control system upgrade provides reliable operation with an improved operational space. -- Abstract: The ISTTOK tokamak (Ip = 4 kA, BT = 0.5 T, R = 0.46 m, a = 0.085 m) is one of the few tokamaks with regular alternate plasma current (AC) discharges scientific programme. In order to improve the discharge stability and to increase the number of AC discharge cycles a novel control system was developed. The controller acquires data from 50 analog-to-digital converter (ADC) channels of real-time diagnostics and measurements: tomography, Mirnov coils, interferometer, electric probes, sine and cosine probes, bolometer, current delivered by the power supplies, loop voltage and plasma current. The system has a control cycle of 100 μs during which it reads all the diagnostics connected to the advanced telecommunications computing architecture (ATCA) digitizers and sends the control reference to ISTTOK actuators. The controller algorithms are executed on an Intel{sup ®} Q8200 chip with 4 cores running at 2.33 GHz and connected to the I/O interfaces through an ATCA based environment. The real-time control system was programmed in C++ on top of the Multi-threaded Application Real-Time executor (MARTe). To extend the duration of the AC discharges and the plasma stability a new magnetising field power supply was commissioned and the horizontal and vertical field power supplies were also upgraded. The new system also features a user-friendly interface based on HyperText Markup Language (HTML) and Javascript to configure the controller parameters. This paper presents the ISTTOK control system and the consequent update of real-time diagnostics and actuators.

  3. ISTTOK control system upgrade

    International Nuclear Information System (INIS)

    Carvalho, Ivo S.; Duarte, Paulo; Fernandes, Horácio; Valcárcel, Daniel F.; Carvalho, Pedro J.; Silva, Carlos; Duarte, André S.; Neto, André; Sousa, Jorge; Batista, António J.N.; Carvalho, Bernardo B.

    2013-01-01

    Highlights: •ISTTOK fast controller. •All real-time diagnostic and actuators were integrated in the control platform. •100 μs control cycle under the MARTe framework. •The ISTTOK control system upgrade provides reliable operation with an improved operational space. -- Abstract: The ISTTOK tokamak (Ip = 4 kA, BT = 0.5 T, R = 0.46 m, a = 0.085 m) is one of the few tokamaks with regular alternate plasma current (AC) discharges scientific programme. In order to improve the discharge stability and to increase the number of AC discharge cycles a novel control system was developed. The controller acquires data from 50 analog-to-digital converter (ADC) channels of real-time diagnostics and measurements: tomography, Mirnov coils, interferometer, electric probes, sine and cosine probes, bolometer, current delivered by the power supplies, loop voltage and plasma current. The system has a control cycle of 100 μs during which it reads all the diagnostics connected to the advanced telecommunications computing architecture (ATCA) digitizers and sends the control reference to ISTTOK actuators. The controller algorithms are executed on an Intel ® Q8200 chip with 4 cores running at 2.33 GHz and connected to the I/O interfaces through an ATCA based environment. The real-time control system was programmed in C++ on top of the Multi-threaded Application Real-Time executor (MARTe). To extend the duration of the AC discharges and the plasma stability a new magnetising field power supply was commissioned and the horizontal and vertical field power supplies were also upgraded. The new system also features a user-friendly interface based on HyperText Markup Language (HTML) and Javascript to configure the controller parameters. This paper presents the ISTTOK control system and the consequent update of real-time diagnostics and actuators

  4. Proposal of electric power generation from generators to water edge in the region of Sarapiqui

    International Nuclear Information System (INIS)

    Rodriguez Fallas, Cindy Veronica

    2013-01-01

    A proposed electric power generation is developed from generators to water edge in the region of Sarapiqui. The environmental characteristics, such as the hydrological network, hydrogeology, soil type, life zones, climatology, precipitation, temperature, evapotranspiration and water supply and demand, of rivers crossed by basin in the region of Sarapiqui, are determined by bibliographic consultations to implement the proposal. The most recent production statistics of the electric subsector of Costa Rica are described to reveal the growing annual demand and need for satisfaction. The zone of Sarapiqui is diagnosed as the right place to allow the generation of electric power from generators to water edge [es

  5. Future CO2 emissions and electricity generation from proposed coal-fired power plants in India

    Science.gov (United States)

    Fofrich, R.; Shearer, C.; Davis, S. J.

    2017-12-01

    India represents a critical unknown in global projections of future CO2 emissions due to its growing population, industrializing economy, and large coal reserves. In this study, we assess existing and proposed construction of coal-fired power plants in India and evaluate their implications for future energy production and emissions in the country. In 2016, India had 369 coal-fired power plants under development totaling 243 gigawatts (GW) of generating capacity. These coal-fired power plants would increase India's coal-fired generating capacity by 123% and would exceed India's projected electricity demand. Therefore, India's current proposals for new coal-fired power plants would be forced to retire early or operate at very low capacity factors and/or would prevent India from meeting its goal of producing at least 40% of its power from renewable sources by 2030. In addition, future emissions from proposed coal-fired power plants would exceed India's climate commitment to reduce its 2005 emissions intensity 33% - 35% by 2030.

  6. TCV divertor upgrade for alternative magnetic configurations

    Directory of Open Access Journals (Sweden)

    H. Reimerdes

    2017-08-01

    Full Text Available The Swiss Plasma Center (SPC is planning a divertor upgrade for the TCV tokamak. The upgrade aims at extending the research of conventional and alternative divertor configurations to operational scenarios and divertor regimes of greater relevance for a fusion reactor. The main elements of the upgrade are the installation of an in-vessel structure to form a divertor chamber of variable closure and enhanced diagnostic capabilities, an increase of the pumping capability of the divertor chamber and the addition of new divertor poloidal field coils. The project follows a staged approach and is carried out in parallel with an upgrade of the TCV heating system. First calculations using the EMC3-Eirene code indicate that realistic baffles together with the planned heating upgrade will allow for a significantly higher compression of neutral particles in the divertor, which is a prerequisite to test the power dissipation potential of various divertor configurations.

  7. Proposed revision of the Cumberland System Power Marketing Policy and subsequent contracts

    International Nuclear Information System (INIS)

    1992-01-01

    Southeastern Power Administration has prepared an Environmental Assessment (DOE/EA-0811) evaluating the proposed revision of the Cumberland System Power Marketing Policy and Subsequent Contracts. The findings of the Environmental Assessment (EA) are: the only significant change from the existing policy will be the term of the contracts executed under the revised policy; and there will be no addition of major new generation resources; there will be no new loads; there will be no major changes in the operating parameters of power generation resources. This paper discusses the need for action, the alternative and the environmental impacts

  8. 77 FR 14516 - Alabama Power Company, Martin Dam Hydroelectric Project; Notice of Proposed Revised Restricted...

    Science.gov (United States)

    2012-03-12

    ... Power Company, Martin Dam Hydroelectric Project; Notice of Proposed Revised Restricted Service List for... for inclusion in, the National Register of Historic Places at the Martin Dam Hydroelectric Project...)). The Commission's responsibilities pursuant to section 106 for the Martin Dam Hydroelectric Project...

  9. Upgrading Ukraine's nuclear power plants

    International Nuclear Information System (INIS)

    Tkhorzhevskyy, O.

    2001-01-01

    In the article the description of the historical process of Ukrainian NPP modernization is presented. The existed procedure of modernization implementation is described in details. The main features of this procedure are illustrated by several examples, such as ECCS sumps, improvements of hydrogen recombination system and development of RPS control rod revision program. (author)

  10. Proposal for implementation of alternative source term in the nuclear power plant of Laguna Verde

    International Nuclear Information System (INIS)

    Bazan L, A.; Lopez L, M.; Vargas A, A.; Cardenas J, J. B.

    2009-10-01

    In 2010 the nuclear power plant of Laguna Verde will implement the extended power upbeat in both units of the plant. Agree with methodology of NEDC-33004P-A, (constant pressure power up rate), and the source term of core, for accidents evaluations, were increased in proportion to the ratio of power level. This means that for the case of a design basis accident of loss of coolant an increase of power of 15% originated an increase of 15% in dose to main control room. Using the method of NEDC-33004P-A to extended power upbeat conditions was determined that the dose value to main control room is very near to regulatory limit established by SRP 6.4. By the above and in order to recover the margin, the nuclear power plant of Laguna Verde will calculate an alternative source term following the criteria established in RG 1.183 (alternative radiological source term for evaluating DBA at nuclear power reactor). This approach also have a more realistic dose value using the criterion of 10-CFR-50.67, in addition is predicted to get the benefit of additional operational flexibilities. This paper present the proposal of implementing the alternative source term in Laguna Verde. (Author)

  11. A proposed high-power UV industrial demonstration laser at CEBAF

    International Nuclear Information System (INIS)

    Benson, S.V.; Bisognano, J.J.; Bohn, C.L.

    1996-01-01

    The Laser Processing Consortium, a collaboration of industries, universities, and the Continuous Electron Beam Accelerator Facility (CEBAF) in Newport News, Virginia, has proposed building a demonstration industrial processing laser for surface treatment and micro-machining. The laser is a free-electron laser (FEL) with average power output exceeding 1 kW in the ultraviolet (UV). The design calls for a novel driver accelerator that recovers most of the energy of the exhaust electron beam to produce laser light with good wall-plug efficiency. The laser and accelerator design use technologies that are scalable to much higher power. The authors describe the critical design issues in the laser such as the stability, power handling, and losses of the optical resonator, and the quality, power, and reliability of the electron beam. They also describe the calculated laser performance. Finally progress to date on accelerator development and resonator modeling will be reported

  12. A proposed high-power UV industrial demonstration laser at CEBAF

    International Nuclear Information System (INIS)

    Benson, S.V.; Bisognano, J.J.; Bohn, C.L.

    1996-01-01

    The Laser Processing Consortium, a collaboration of industries, universities, and the Continuous Electron Beam Accelerator Facility (CEBAF) in Newport News, Virginia, has proposed building a demonstration industrial processing laser for surface treatment and micro-machining. The laser is a free-electron laser (FEL) with average power output exceeding 1 kW in the ultraviolet (UV). The design calls for a novel driver accelerator that recovers most of the energy of the exhaust electron beam to produce laser light with good wall-plug efficiency. The laser and accelerator design use technologies that are scalable to much higher power. The authors will describe the critical design issues in the laser such as the stability, power handling, and losses of the optical resonator, and the quality, power, and reliability of the electron beam. They will also describe the calculated laser performance. Finally progress to date on accelerator development and resonator modeling will be reported

  13. AliPDU Package Upgrade

    CERN Document Server

    "Martin, Michael

    2015-01-01

    "AliPDU Package" is a set of script, panels, and datapoints designed in WinCC to manage and monitor PDU's. PDU is an essential component in the data center, in order to make data center working properly through the monitoring of power distribution and environmental condition of the data center. In this project "AliPDU Package" is upgraded so it can be used to monitor environmental condition of data center using PDU's and external environmental sensor connected to PDU.

  14. AliPDU Package Upgrade

    CERN Document Server

    Martin, Michael

    2015-01-01

    AliPDU Package is a set of script, panels, and datapoints designed in WinCC to manage and monitor PDU's. PDU is an essential component in the data center, in order to make data center working properly through the monitoring of power distribution and environmental condition of the data center. In this project "AliPDU Package" is upgraded so it can be used to monitor environmental condition of data center using PDU's and external environmental sensor connected to PDU.

  15. Some retrofit considerations for revitalizing and upgrading the Oji-River coal-fired thermal power station for service in 21st century Nigeria

    Energy Technology Data Exchange (ETDEWEB)

    Oguejofor, G.C. [Nnamdi Azikiwe University, Awka (Nigeria). Faculty of Engineering & Technology, Dept. of Chemical Engineering

    2003-02-01

    The aim of this article is to show that in the context of sustainable development, coal and its downstream power generation industry could complement petroleum and hydroelectric industries in the national power generation scheme. The continued utilization of coal in power generation schemes in the world as well as environmental pollution caused by other fossil fuels were examined. These were presented as justifications for the proposed reintegration of coal as a complement to hydropower and oil/gas sources of electric energy in Nigeria. The scheme of power generation in the Oji-River thermal station was reviewed to enhance the appreciation of the retrofit models to be presented for the revitalization of the plant. Subsequently, two sustainable development retrofit models were considered for the revitalization of the Oji-River thermal power station and enhanced industrial civilization of the Oji neighbourhood. To ensure self-sufficiency, the paper shows how the two retrofit models depend on abundant locally available resources, namely, coal, limestone, water and air.

  16. Upgrade of the CSC Endcap Muon Port Card at CMS

    International Nuclear Information System (INIS)

    Matveev, M; Padley, P

    2010-01-01

    The Muon Port Card (MPC) provides optical transmission of Level 1 Trigger primitives from 60 Endcap peripheral crates to the Track Finder (TF) crate within the CMS Cathode Strip Chamber (CSC) sub-detector at the CMS experiment at CERN. The system has been in operation since 2008 and comprises 180 1.6 Gbps optical links. The proposed Super-LHC (SLHC) upgrade implies higher data volumes to be transmitted through the trigger chain and more sophisticated trigger algorithms. We expect to upgrade the MPC boards within the next few years to accommodate these requirements. The paper presents the first results of simulation and prototyping with the goal of improving the sorting algorithms and using parallel 12-channel optical links and a more powerful Virtex-5 FPGA.

  17. The potential environmental impacts and the siting of proposed nuclear power plants in China

    International Nuclear Information System (INIS)

    Shi Zhongqi

    1986-01-01

    This paper reviews briefly the methodology of assessing environmental impacts from the nuclear power plants and analyses the potential radiological impacts on the environment from proposed nuclear power plants in China. Preliminary studies show that the environmental impacts of the effluents of routine release from PWRs to the proposed sites are extremely small, even if nuclear power plants are constructed either on the Bohai Sea shore with a narrow mouth or in the densely populated regions of Sunan. Thus, the suitability of sites depends mainly on the acceptability of possible exposure to the residents following postulated accidental release of radioactive materials. The paper also discusses relations between the nuclear plant siting and population distribution around the site and compares the distribution of the proposed sites in China with that of other countries sites in according to China actual situation, it is reasonable to adopt a prudent policy that the first series of nuclear power plants in China should be built in relatively low population areas

  18. Future CO2 emissions and electricity generation from proposed coal-fired power plants in India

    Science.gov (United States)

    Shearer, Christine; Fofrich, Robert; Davis, Steven J.

    2017-04-01

    With its growing population, industrializing economy, and large coal reserves, India represents a critical unknown in global projections of future CO2 emissions. Here, we assess proposed construction of coal-fired power plants in India and evaluate their implications for future emissions and energy production in the country. As of mid-2016, 243 gigawatts (GW) of coal-fired generating capacity are under development in India, including 65 GW under construction and an additional 178 GW proposed. These under-development plants would increase the coal capacity of India's power sector by 123% and, when combined with the country's goal to produce at least 40% of its power from non-fossil sources by 2030, exceed the country's projected future electricity demand. The current proposals for new coal-fired plants could therefore either "strand" fossil energy assets (i.e., force them to retire early or else operate at very low capacity factors) and/or ensure that the goal is not met by "locking-out" new, low-carbon energy infrastructure. Similarly, future emissions from the proposed coal plants would also exceed the country's climate commitment to reduce its 2005 emissions intensity 33% to 35% by 2030, which—when combined with the commitments of all other countries—is itself not yet ambitious enough to meet the international goal of holding warming well below 2°C relative to the pre-industrial era.

  19. Five TWh saved on profitable upgrading

    International Nuclear Information System (INIS)

    Bakken, Stein Arne.

    1999-01-01

    Article. In Norway, a project is planned to evaluate the upgrading potential of the hydroelectric power sector. The article criticizes the authorities for not supporting the upgrading of hydroelectric power plants in their eager to promote the development of wind power. An important contribution of the planned project will be a book from which the utilities may get advice on measures of upgrading. Generators and control systems account for 80% of the faults and interruptions in the power utilities. The turbine technology has made important progress in the 1990s. By pure upgrading measures alone, the turbine efficiencies may be increased enough for an additional 3 TWh to be taken out from the Norwegian hydroelectric power system. Today, the price of imported carbon-based Danish power determines whether the utilities find it profitable to rehabilitate the hydroelectric plants. The energy potential of upgrading is estimated to be 5 TWh. This energy can be generated with known technology and with no serious consequences for the environment

  20. The D0 Upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Abachi, S.; D0 Collaboration

    1995-07-01

    In this paper we describe the approved DO Upgrade detector, and its physics capabilities. The DO Upgrade is under construction and will run during the next Fermilab collider running period in early 1999 (Run II). The upgrade is designed to work at the higher luminosities and shorter bunch spacings expected during this run. The major elements of t he upgrade are: a new tracking system with a silicon tracker, scintillating fiber tracker, a 2T solenoid, and a central preshower detector; new calorimeter electronics; new muon trigger and tracking detectors with new muon system electronics; a forward preshower detector; new trigger electronics and DAQ improvements to handle the higher rates.

  1. Citizens' views about the proposed Hartsville Nuclear Power Plant: a preliminary report of potential social impacts

    International Nuclear Information System (INIS)

    Schuller, C.R.; Fowler, J.R.; Mattingly, T.J. Jr.; Sundstrom, E.; Lounsbury, J.; Passino, E.M.; Dowell, D.A.; Hutton, B.J.

    1975-05-01

    Preliminary results of a survey of public attitudes toward a proposed nuclear power plant facility at Hartsville, Tennessee are summarized. The purpose of the study was to aid in developing better methods for understanding the social consequences of energy facility development. The report is based on data obtained in interviews with 350 randomly selected respondents administered in Trousdale County, Tennessee during February 1975. (U.S.)

  2. Basic facts concerning the proposed nuclear power plant at Akkuyu in Turkey

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    This booklet attempts to explain to non-experts the results of the preparatory studies carried out regarding proposed nuclear powe plant at Akkuyu. The information presented here has been organized in four parts;Part 1-Introduction Part 2-IAEA work in Relation to the Seismic Safety of Akkuyu(Turkey) Nuclear Power Plant Site Part 3-Seismic conditions at the Akkuyu Site Part 4-Possible Consequences of a Hypothetical Severe Accident at Akkuyu Part 5-Conclusions. 20 refs.

  3. Basic facts concerning the proposed nuclear power plant at Akkuyu in Turkey

    International Nuclear Information System (INIS)

    2000-01-01

    This booklet attempts to explain to non-experts the results of the preparatory studies carried out regarding proposed nuclear powe plant at Akkuyu. The information presented here has been organized in four parts;Part 1-Introduction Part 2-IAEA work in Relation to the Seismic Safety of Akkuyu(Turkey) Nuclear Power Plant Site Part 3-Seismic conditions at the Akkuyu Site Part 4-Possible Consequences of a Hypothetical Severe Accident at Akkuyu Part 5-Conclusions. 20 refs

  4. MAST Upgrade – Construction Status

    Energy Technology Data Exchange (ETDEWEB)

    Milnes, Joe, E-mail: Joe.Milnes@ccfe.ac.uk; Ayed, Nizar Ben; Dhalla, Fahim; Fishpool, Geoff; Hill, John; Katramados, Ioannis; Martin, Richard; Naylor, Graham; O’Gorman, Tom; Scannell, Rory

    2015-10-15

    Highlights: • Outlines unique capability of MAST-U, including divertor and diagnostic capability. • Describes progress made in the manufacture and assembly of key MAST-U components. • Highlights the design challenges that have been overcome. • Lists the key lessons learned thus far in the project. - Abstract: The Mega Amp Spherical Tokamak (MAST) is the centre piece of the UK fusion research programme. In 2010, a MAST Upgrade programme was initiated with three primary objectives, to contribute to: (1) testing reactor concepts (in particular exhaust solutions via a flexible divertor allowing Super-X and other extended leg configurations); (2) adding to the knowledge base for ITER (by addressing important plasma physics questions and developing predictive models to help optimise ITER performance of ITER) and (3) exploring the feasibility of using a spherical tokamak as the basis for a fusion Component Test Facility. With the project mid-way through its construction phase, progress will be reported on a number of the critical subsystems. This will include manufacture and assembly of the coils, armour and support structures that make up the new divertors, construction of the new set coils that make up the centre column, installation of the new power supplies for powering the divertor coils and enhanced TF coil set, progress in delivering the upgraded diagnostic capability, the modification and upgrading of the NBI heating systems and the complete overhaul of the machine control infrastructure, including a new control room with full remote participation facilities.

  5. Safety upgrading of Bohunice V1 NPP

    International Nuclear Information System (INIS)

    2001-01-01

    This CD is multimedia presentation of programme safety upgrading of Bohunice V1 NPP. It consist of next chapters: (1) Introductory speeches; (2) Nuclear power plant WWER 440; (3) Safety improvement; (4) Bohunice Nuclear power plants subsidiary; (5) Siemens; (6) REKON; (7) VUJE Trnava, Inc. - Engineering, Design and Research Organisation; (8) Album

  6. Instrumentation and control upgrade evaluation methodology: Final report. Volume 2: Workbook

    Energy Technology Data Exchange (ETDEWEB)

    Bliss, M.; Brown, E.; Florio, F.; Stofko, M.

    1996-07-01

    This workbook accompanies the methodology manual (EPRI TR-104963-V1) which describes how to develop an Upgrade Evaluation Report (UER). A UER is an evaluation that is performed by a nuclear power plant to decide the most cost-effective upgrade to perform (if any) for a previously identified Upgrade Candidate System. A UER defines the utility`s mission and objectives in regards to upgrade candidates, as well as the systems initial costs, benefits to each upgrade, and an initial upgrade schedule to cost-effectively implement system upgrades.

  7. A kernel plus method for quantifying wind turbine performance upgrades

    KAUST Repository

    Lee, Giwhyun; Ding, Yu; Xie, Le; Genton, Marc G.

    2014-01-01

    Power curves are commonly estimated using the binning method recommended by the International Electrotechnical Commission, which primarily incorporates wind speed information. When such power curves are used to quantify a turbine's upgrade

  8. Original seismic and similar severe external loading design basis for WWER type nuclear power plants in Czech and Slovak Republics and actual issues of their upgrading

    International Nuclear Information System (INIS)

    Masopust, R.

    1993-01-01

    The WWER type NPPs located in Czech and Slovak republics have many seismic vulnerabilities similar to those recognized in many of the US NPPs prior to late seventies. They are mostly caused by underestimation of these problems in the design phases, sometimes due to inadequate performance and poor quality of works and some incompatibilities between the original Russian design and current international design bases and safety requirements. It is believed that the structures and equipment of these NPPs can be seismically upgraded at a moderate cost. It is also believed that the IAEA Benchmark study for seismic analysis and testing of WWER NPPs will develop recommendations to effective seismic upgrading of the existing plants

  9. NSLS control system upgrade

    International Nuclear Information System (INIS)

    Smith, J.D.; Ramamoorthy, Susila; Tang, Y.N.

    1994-01-01

    The NSLS consists of two storage rings, a booster and a linac. A major upgrade of the control system (installed in 1978) was undertaken and has been completed. The computer architecture is being changed from a three level star-network to a two level distributed system. The microprocessor subsystem, host computer and workstations, communication link and the main software components are being upgraded or replaced. Since the NSLS rings operate twenty four hours a day a year with minimum maintenance time, the key requirement during the upgrade phase is a non-disruptive transition with minimum downtime. Concurrent with the upgrade, some immediate improvements were required. This paper describes the various components of the upgraded system and outlines the future plans. ((orig.))

  10. NSLS control system upgrade

    International Nuclear Information System (INIS)

    Smith, J.D.; Ramamoorthy, S.; Tang, Yong N.

    1995-01-01

    The NSLS consists of two storage rings, a booster and a linac. A major upgrade of the control system (installed in 1978) was undertaken and has been completed. The computer architecture is being changed from a three level star-network to a two level distributed system. The microprocessor subsystem, host computer and workstations, communication link and the main software components are being upgraded or replaced. Since the NSLS rings operate twenty four hours a day a year with minimum maintenance time, the key requirement during the upgrade phase is a non-disruptive transition with minimum downtime. Concurrent with the upgrade, some immediate improvements were required. This paper describes the various components of the upgraded system and outlines the future plans

  11. CANDU Digital Control Computer upgrade options

    International Nuclear Information System (INIS)

    De Jong, M.S.; De Grosbois, J.; Qian, T.

    1997-01-01

    This paper reviews the evolution of Digital Control Computers (DCC) in CANDU power plants to the present day. Much of this evolution has been to meeting changing control or display requirements as well as the replacement of obsolete, or old and less reliable technology with better equipment that is now available. The current work at AECL and Canadian utilities to investigate DCC upgrade options, alternatives, and strategies are examined. The dependence of a particular upgrade strategy on the overall plant refurbishment plans are also discussed. Presently, the upgrade options range from replacement of individual obsolete system components, to replacement of the entire DCC hardware without changing the software, to complete replacement of the DCCs with a functionally equivalent system using new control computer equipment and software. Key issues, constraints and objectives associated with these DCC upgrade options are highlighted. (author)

  12. A Proposal for more Effective Training in Countries Developing Nuclear Power

    International Nuclear Information System (INIS)

    Abdel-Halim, A.; Durst, P.C.; Witkin, A.L.

    2010-01-01

    The expanded use of nuclear power is being driven in today's world, because nuclear power provides high density base-load power, produces waste in a manageable and compact form, and does not emit carbon based 'green-house gases' that could be altering the world's climate. For these reasons, there is a veritable renaissance in the construction of nuclear power reactors of inherently safer designs, as well as an expansion in worldwide uranium mining, and construction of associated fuel cycle facilities. It is important to recognize that this expansion and revisiting of nuclear power is not just limited to the industrialized countries of North America, Europe, and Asia, but is also occurring in states developing their first nuclear power plant. In particular, the United Arab Emirates (UAE), Turkey, Egypt, Jordan, and Indonesia have all contracted the construction of nuclear power plants, or are planning to do so. The authors of this paper believe that all of these programs could benefit from enhanced training in the use and operation of nuclear power reactors and fuel cycle facilities, through the more effective transfer of knowledge. In particular, the authors propose the greater use of retired nuclear reactor and fuel cycle engineers, experts, and former senior staff members from the International Atomic Energy Agency (IAEA) as one way to transfer this knowledge more effectively. The transfer of nuclear knowledge between senior experts and students, young engineers and professionals in training would help bridge the significant gap that exists in today's nuclear engineering curriculum between academic instruction and the real world of industry. The need for more effective knowledge transfer is particularly acute in the areas of nuclear safety, nuclear safeguards, and security. One only has to recall the nuclear accidents at the Chernobyl nuclear power plant in the Ukraine, Three Mile Island in the United States, and the JCO uranium conversion plant in Japan, to

  13. To upgrade or not to upgrade

    DEFF Research Database (Denmark)

    Rasmussen, Torben Valdbjørn; Rose, Jørgen

    2017-01-01

    This paper identifies the key indicators that owners need to take into account in order to choose the most affordable extent of upgrading of a typical post-1945 building. The exterior look of the building is not to be changed. Indicators include measures, risk assessment related to the changes in...

  14. 76 FR 47180 - Pick-Sloan Missouri Basin Program-Eastern Division-2021 Power Marketing Initiative Proposal

    Science.gov (United States)

    2011-08-04

    ... marketing plan principles. The comment period for the proposed 2021 PMI ended on May 4, 2011. Western... customers the opportunity to review current marketing plan principles and provide informal input to Western... Division--2021 Power Marketing Initiative Proposal AGENCY: Western Area Power Administration, DOE. ACTION...

  15. Proposed high voltage power supply for the ITER relevant lower hybrid current drive system

    International Nuclear Information System (INIS)

    Sharma, P.K.; Kazarian, F.; Garibaldi, P.; Gassman, T.; Artaud, J.F.; Bae, Y.S.; Belo, J.; Berger-By, G.; Bernard, J.M.; Cara, Ph.; Cardinali, A.; Castaldo, C.; Ceccuzzi, S.; Cesario, R.; Decker, J.; Delpech, L.; Ekedahl, A.; Garcia, J.; Goniche, M.; Guilhem, D.

    2011-01-01

    In the framework of the EFDA task HCD-08-03-01, the ITER lower hybrid current drive (LHCD) system design has been reviewed. The system aims to generate 24 MW of RF power at 5 GHz, of which 20 MW would be coupled to the plasmas. The present state of the art does not allow envisaging a unitary output of the klystrons exceeding 500 kW, so the project is based on 48 klystron units, leaving some margin when the transmission lines losses are taken into account. A high voltage power supply (HVPS), required to operate the klystrons, is proposed. A single HVPS would be used to feed and operate four klystrons in parallel configuration. Based on the above considerations, it is proposed to design and develop twelve HVPS, based on pulse step modulator (PSM) technology, each rated for 90 kV/90 A. This paper describes in details, the typical electrical requirements and the conceptual design of the proposed HVPS for the ITER LHCD system.

  16. Proposed quantitative approach to safety for nuclear power plants in Canada

    International Nuclear Information System (INIS)

    1995-07-01

    A set of quantitative risk and frequency limits plus required processes is proposed to help ensure that a nuclear power plant in Canada meets the qualitative safety objectives defined in ACNS-2 and in IAEA 75-INSAG-3. As emphasized in this report, risks and hence doses are to be reduced below the limits using ALARA (As Low as Reasonably Achievable, economic and social factors being taken into account) or VIA (value-impact analysis) processes unless, in general, calculated risks and hence doses are below recommended de minimis levels. An updated version of ACNS-4, which will be issued as ACNS-21, will incorporate a statement of these limits and objectives as well as assessment criteria and procedures that will facilitate their application. The quantitative approach proposed here is consistent with a growing consensus on the need for, and the elements of, a quantitative approach to risk management of all major activities in an advanced industrial society. The ACNS recommends that the Atomic Energy Control Board adopt the proposed approach as a rational and coherent basis for nuclear power plant safety policy and requirements in Canada. (author). 68 refs., 4 tabs., 1 fig

  17. Proposed quantitative approach to safety for nuclear power plants in Canada

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    A set of quantitative risk and frequency limits plus required processes is proposed to help ensure that a nuclear power plant in Canada meets the qualitative safety objectives defined in ACNS-2 and in IAEA 75-INSAG-3. As emphasized in this report, risks and hence doses are to be reduced below the limits using ALARA (As Low as Reasonably Achievable, economic and social factors being taken into account) or VIA (value-impact analysis) processes unless, in general, calculated risks and hence doses are below recommended de minimis levels. An updated version of ACNS-4, which will be issued as ACNS-21, will incorporate a statement of these limits and objectives as well as assessment criteria and procedures that will facilitate their application. The quantitative approach proposed here is consistent with a growing consensus on the need for, and the elements of, a quantitative approach to risk management of all major activities in an advanced industrial society. The ACNS recommends that the Atomic Energy Control Board adopt the proposed approach as a rational and coherent basis for nuclear power plant safety policy and requirements in Canada. (author). 68 refs., 4 tabs., 1 fig.

  18. Performance analysis of a complete adiabatic logic system driven by the proposed power clock generator

    International Nuclear Information System (INIS)

    Kanungo, Jitendra; Dasgupta, S.

    2014-01-01

    We analyze the energy performance of a complete adiabatic circuit/system including the Power Clock Generator (PCG) at the 90 nm CMOS technology node. The energy performance in terms of the conversion efficiency of the PCG is extensively carried out under the variations of supply voltage, process corner and the driver transistor's width. We propose an energy-efficient singe cycle control circuit based on the two-stage comparator for the synchronous charge recovery sinusoidal power clock generator (PCG). The proposed PCG is used to drive the 4-bit adiabatic Ripple Carry Adder (RCA) and their simulation results are compared with the adiabatic RCA driven by the reported PCG. We have also simulated the logically equivalent static CMOS RCA circuit to compare the energy saving of adiabatic and non-adiabatic logic circuits. In the clock frequency range from 25 MHz to 1GHz, the proposed PCG gives a maximum conversion efficiency of 56.48%. This research work shows how the design of an efficient PCG increases the energy saving of adiabatic logic. (semiconductor integrated circuits)

  19. Hydrogen alternatives for a regional upgrader

    International Nuclear Information System (INIS)

    Bailey, R.T.; Padamsey, R.

    1991-01-01

    For a proposed regional upgrader in Alberta, hydrogen will be needed to upgrade the bitumen and heavy oil to be processed by that facility. The upgrader will rely on high conversion hydrocracking which consumes 3.4 wt % hydrogen to produce a 106% volume yield of high quality synthetic crude. The costs of producing hydrogen via steam reforming of methane, partial oxidation of coal or upgrading residues, and electrolysis are compared, showing that steam reforming is the cheapest. However, an even cheaper source of hydrogen is available in the Edmonton and Fort Saskatchewan area as byproducts from petrochemical plants. An economic analysis is presented of a proposed scheme to capture, purify, compress, and transfer hydrogen from one or two such plants to a nearby regional upgrader. The two plants could supply a total of 126.6 million ft 3 /d of hydrogen at a total installed capital cost of about half of that of a steam reforming plant of equivalent size. When operating costs are added (including the cost of replacing the hydrogen, currently used as fuel at the two plants, with natural gas), the total cost of hydrogen is substantially less than the costs for a hydrogen plant within the upgrader. 3 refs., 5 figs., 4 tabs

  20. Superhilac upgrade project

    International Nuclear Information System (INIS)

    Feinberg, B.; Brown, I.G.

    1985-05-01

    This project will increase the uranium output of the Bevalac heavy-ion facility from the currently available 10 7 to 5 x 10 7 ions/pulse, allowing accurate Lamb shift measurements to be made in U 90+ and U 91+ with important applications to the testing of quantum electrodynamics and the development of an x-ray laser. The injected beam intensity will be increased to make better use of the 10emA output space-charge limit of the Wideroe linac. Components will include a new high current MEtal Vapor Vacuum Arc (MEVVA) ion source along with an improved high current, high voltage Cockcroft-Walton power supply to handle the increased beam current. The Low Energy Beam Transport (LEBT) line will be upgraded with additional focusing to manage the increased space-charge forces and with an improved vacuum to reduce charge exchange losses. Finally, the phase matching between the 23MHz Wideroe linac and the 70MHz Alvarez linac will be improved by the addition of the appropriate buncher cavities. Physics design is underway and detailed engineering is scheduled to begin in October 1985, with installation slated for the 1986 summer shutdown

  1. A proposal to pulse the Bevatron/Bevalac main guide field magnet with SCR power supplies

    International Nuclear Information System (INIS)

    Frias, B.; Alonso, J.; Dwinell, R.; Lothrop, F.

    1989-01-01

    The Bevatron/Bevalac Main Guide Field Power Supply was originally designed to provide a 15,250 Volt DC. at sign 8400 Ampere peak magnet pulse. Protons were accelerated to 6.2 Gev. The 128 Megawatt (MW) pulse required two large motor-generator (MG) sets with 67 ton flywheels to store 680 Megajoules of energy. Ignitron rectifiers are used to rectify the generator outputs. Acceleration of heavy ions results in an operating schedule with a broad range of peak fields. The maximum field of 12.5 kilogauss requires a peak pulse of 80 MW. Acceleration of ions to 1.0 kilogauss requires an 8 MW peak pulse. One MG set can provide pulses below 45 MW. Peak pulses of less than 15 MW are now a large block of the operating schedule. A proposal has been made to replace the existing MG system with eight SCR power supplies for low field operation. The SCR supplies will be powered directly from the Lawrence Berkeley Laboratory's 12.3 KV. power distribution system. This paper describes the many advantages of the plan. 4 refs., 3 figs., 3 tabs

  2. U.S. regulators reject proposal to subsidize nuclear and coal power prices

    International Nuclear Information System (INIS)

    Kraemer, Jay R.

    2018-01-01

    On January 8, 2018, the U.S. Federal Energy Regulatory Commission (''FERC'') unanimously rejected a rulemaking proposed by Secretary of Energy Rick Perry designed to enable the owners of coal and nuclear power plants to charge higher prices for their output, and thereby to prevent further premature retirements of such plants. The FERC has exclusive authority, under the Federal Power Act, to establish rules for interstate wholesale sales of electricity. Although the FERC simultaneously initiated a new proceeding to consider how to enhance the resilience of electricity supply and delivery in the U.S., that proceeding seems unlikely to offer near-term relief to nuclear plants that are approaching closure due to their inability to compete economically both with facilities fueled by low-priced natural gas and with renewable power sources benefitting from favorable tax provisions. Accordingly, the American nuclear power industry will probably have to look elsewhere for relief from its present dire economic circumstances.

  3. Social Life Cycle Assessment of a Concentrated Solar Power Plant in Spain: A Methodological Proposal

    DEFF Research Database (Denmark)

    Corona, Blanca; Bozhilova-Kisheva, Kossara Petrova; Olsen, Stig Irving

    2017-01-01

    of sustainability, namely, economy, environment, and society. Social life cycle assessment (S-LCA) is a novel methodology still under development, used to cover the social aspects of sustainability within LCSA. The aim of this article is to provide additional discussion on the practical application of S...... generation in a concentrated solar power plant in Spain. The inventory phase was completed by using the indicators proposed by the United Nations Environment Program/Society for Environmental Toxicology and Chemistry (UNEP/SETAC) Guidelines on S-LCA. The impact assessment phase was approached by developing...... a social performance indicator that builds on performance reference points, an activity variable, and a numeric scale with positive and negative values. The social performance indicator obtained (+0.42 over a range of –2 to +2) shows that the deployment of the solar power plant increases the social welfare...

  4. Public perspectives on proposed license renewal regulations for nuclear power plants

    International Nuclear Information System (INIS)

    Ligon, D.; Hughes, A.; Seth, S.

    1991-01-01

    On 17 July 1990, the U.S Nuclear Regulatory Commission (NRC) issued for public comment its proposed rule for renewing the operating licenses of nuclear power plants (55 FR 29043). This solicitation marked the fourth time that NRC has Invited public comments on its efforts to develop regulatory requirements for re licensing nuclear power plants. Previously, NRC solicited public comments on establishing a policy statement on plant life extension, and on the issues and options for license renewal discussed in NUREG-1317. On 13-14 November 1989, NRC held a public workshop where the NRC staff discussed a conceptual approach to the rule and solicited written comments on the regulatory philosophy, conceptual rule, and on certain questions. NRC is taking into account all comments received in its development of the final rule which is scheduled for issuance in the summer of 1991

  5. A passive cooling system proposal for multifunction and high-power displays

    Science.gov (United States)

    Tari, Ilker

    2013-03-01

    Flat panel displays are conventionally cooled by internal natural convection, which constrains the possible rate of heat transfer from the panel. On one hand, during the last few years, the power consumption and the related cooling requirement for 1080p displays have decreased mostly due to energy savings by the switch to LED backlighting and more efficient electronics. However, on the other hand, the required cooling rate recently started to increase with new directions in the industry such as 3D displays, and ultra-high-resolution displays (recent 4K announcements and planned introduction of 8K). In addition to these trends in display technology itself, there is also a trend to integrate consumer entertainment products into displays with the ultimate goal of designing a multifunction device replacing the TV, the media player, the PC, the game console and the sound system. Considering the increasing power requirement for higher fidelity in video processing, these multifunction devices tend to generate very high heat fluxes, which are impossible to dissipate with internal natural convection. In order to overcome this obstacle, instead of active cooling with forced convection that comes with drawbacks of noise, additional power consumption, and reduced reliability, a passive cooling system relying on external natural convection and radiation is proposed here. The proposed cooling system consists of a heat spreader flat heat pipe and aluminum plate-finned heat sink with anodized surfaces. For this system, the possible maximum heat dissipation rates from the standard size panels (in 26-70 inch range) are estimated by using our recently obtained heat transfer correlations for the natural convection from aluminum plate-finned heat sinks together with the surface-to-surface radiation. With the use of the proposed passive cooling system, the possibility of dissipating very high heat rates is demonstrated, hinting a promising green alternative to active cooling.

  6. 76 FR 22128 - Notice of Intent To Accept Proposals, Select One Lessee, and Contract for Hydroelectric Power...

    Science.gov (United States)

    2011-04-20

    ... for Hydroelectric Power Development at the Granby Dam Outlet, a Feature of the Colorado-Big Thompson... Reclamation, will consider proposals for non-Federal development of hydroelectric power at Granby Dam Outlet of the C-BT, Colorado. Reclamation is considering such hydroelectric power development under a lease...

  7. Upgrading during difficult times

    International Nuclear Information System (INIS)

    Tiefenbach, K.

    1993-01-01

    The Co-op Upgrader is part of an integrated refinery and upgrader complex in Regina, Saskatchewan. The upgrader processes 50,000 bbl/d heavy sour crude oil, mostly Fosterton and dilute Lloydminster crude, via hydrogen addition and carbon rejection, desulfurization, demetallization, and denitrification to yield a synthetic crude blend. The synthetic crude is refined to produce gasoline and diesel fuel. Byproducts from the integrated operation include 100,000 tonnes/y of petroleum coke, 65,000 tonnes/y of sulfur, propane, butane, fuel oil, and metals (Ni and V) in the form of spent catalysts. Recent operational and economic challenges faced by the upgrader are reviewed. Technical challenges include operating the upgrader's high-temperature high-pressure heavy oil hydrotreating unit and distillate hydrogenation unit, removal and replacement of the desulfurization catalyst, waste management, and producing coke of sufficient quality. Economic challenges include the shrinking differential between light and heavy oil, higher prices for natural gas (the main raw material for hydrogen production for upgrading), seasonal changes in product specifications, and lower prices for sulfur and metal byproducts. The upgrader is also affected by interest rates since borrowing costs are the single largest expenditure after crude oil purchases. 4 figs

  8. The Green Stamp in Power Supply Contracts - A proposal for the Brazilian Electricity Market

    Energy Technology Data Exchange (ETDEWEB)

    Estrocio, Joao Paulo

    2010-09-15

    The insertion of a certification mechanism for discriminatory energy supply contracts aiming to make it possible to contract exclusively clean and renewable energy is presented. With the increasing interest for sustainability and carbon emissions reduction, there's a growing demand for clean energy reflected in people's choices for cleaner products. Electricity in a power grid, however, is result of a set of sources or plants, and its operation or dispatch. A proposal for clean energy contracts is presented, providing the market and the clients with the ability to choose to buy exclusively renewable energy through the grid.

  9. A proposal for human factors education in a power plant company

    International Nuclear Information System (INIS)

    Hikono, Masaru

    2004-01-01

    The author was asked by a power plant company to investigate how to change the actual education system concerning human factor education for the plant staff. First, the problems faced by actual education system were investigated based on the results of a large number of surveys conducted in educational fields, and various documents. In the present paper, the author describes the newly proposed educational program., using as illustration a case study. The findings of the present study suggests that, concerning the content of the educational program, it is indispensable for each company to develop a curriculum based on its specific needs. (author)

  10. A proposal of a benchmark for calculation of the power distribution next to the absorber

    International Nuclear Information System (INIS)

    Temesvari, E.; Hordosy, G.; Maraczy, Cs.; Hegyi, Gy.; Kereszturi, A.

    1999-01-01

    A proposal of a new benchmark problem was formulated to consider the characteristics of the VVER-440 fuel assembly with enrichment zoning, i. e. to study the space dependence of the power distribution near to a control assembly. A quite detailed geometry and the material composition of the fuel and the control assemblies were modeled by the help of MCNP calculations in AEKI. The results of the MCNP calculations were built in the KARATE code system as the new albedo matrices. The comparison of the KARATE calculation results and the MCNP calculations for this benchmark is presented. (Authors)

  11. Community attitudes toward a proposed nuclear power generating facility as a function of expected outcomes

    International Nuclear Information System (INIS)

    Sundstrom, E.; Lounsbury, J.W.; Schuller, C.R.; Fowler, J.R.; Mattingly, T.J. Jr.

    1977-01-01

    The relationship between attitudes toward a proposed nuclear power generating facility and the outcomes expected to accompany it are examined. In a survey of 350 residents of a small rural community, approximately 2/3 expressed favorable attitudes toward the proposed nuclear plant. A principal components factor analysis of the anticipated likelihoods of outcomes of the plant revealed five factors: hazards, economic growth, lower costs, social disruption, and community visibility. Using these factors as predictors, a simple multiple regression equation accounted for 52% of the variation in attitudes toward the plant. The strongest predictor was the perceived likelihood of hazards. These findings are discussed in terms of the relationship between attitudes and expectations, and in relation to decisions regarding public policy

  12. RANT Building Upgrade Pre-Proposal Meeting

    Energy Technology Data Exchange (ETDEWEB)

    Thompson, Melinda Ann [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Meadows, Darren W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rodriguez, Roger R. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); MacFarlane, Eric Robert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ortega, Adan Eduardo [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Lopez Escobedo, Gabriela Maria [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-07-31

    This presentation is designed to provide an overview of the project scope and RFP; discuss interfaces for the construction project; highlight key expectations and deliverables from the subcontractor; and address questions and provide clarification of the project scope.

  13. QPS upgrade and machine protection during LS1

    International Nuclear Information System (INIS)

    Denz, R.

    2012-01-01

    The presentation will explain all the proposed changes and discuss the impact on other shutdown activities. The upgrade of the LHC Quench Protection System QPS during LS1 with respect to radiation to electronics will concern the re-location of equipment and installation of new radiation tolerant hardware. The mid-term plan for further R2E upgrades will be addressed. The protection systems for insertion region magnets and inner triplets will be equipped with a dedicated bus-bar splice supervision including some additional modifications in order to improve the EMC immunity. The extension of the supervision capabilities of the QPS will concern the quench heater circuits, the earth voltage feelers and some tools to ease the system maintenance. The protection of the undulators will be revised in order to allow more transparent operation. The installation of snubber capacitors and arc chambers for the main quad circuits will complete the upgrade of the energy extraction systems. Finally the re-commissioning of the protection systems prior to the powering tests will be addressed. (author)

  14. Proposed Nuclear Power Plants in the UK-Potential Radiological Implications for Ireland

    Energy Technology Data Exchange (ETDEWEB)

    McMahon, C.; Kelleher, K.; McGinnity, P.; Organo, C.; Smith, K.; Currivan, L.; Ryan, T.

    2013-05-15

    The UK Government has identified up to eight locations for the construction of new nuclear power plants by 2025. Five of these locations are on the Irish Sea coast. The Radiological Protection Institute of Ireland, RPII was requested by the Minister for the Environment, Community and Local Government to undertake an assessment of the potential radiological impacts on Ireland from this New Build Programme. This report presents the findings of the potential impacts on Ireland of both the anticipated routine radioactive discharges and of a range of postulated nuclear accident scenarios. The following points are the principal findings of the report. Given the prevailing wind direction in Ireland, radioactive contamination in the air, either from routine operation of the proposed nuclear power plants or accidental releases, will most often be transported away from Ireland. The routine operation of the proposed nuclear power plants will have no measurable radiological impact on Ireland or the Irish marine environment. The severe accident scenarios assessed ranged in their estimated frequency of occurrance from 1 in 50,000 to 1 in 33 million per year. The assessment used a weather pattern that maximised the transfer of radioactivity to Ireland. For the severe accident scenarios assessed, food controls or agriculture protective measures would generally be required in Ireland to reduce exposure of the population so as to mitigate potential long-term health effects. In the accident scenario with an estimated 1 in 33 million chance of occurring, short-term measures such as staying indoors would also be advised as a precautionary measure. In general, the accidents with higher potential impact on Ireland are the ones least likely to occur. Regardless of the radiological impact, any accident at the proposed nuclear power plants leading to an increase of radioactivity levels in Ireland would have a socio-economic impact on Ireland. A major accidental release of radioactivity to

  15. Proposed Nuclear Power Plants in the UK-Potential Radiological Implications for Ireland

    International Nuclear Information System (INIS)

    McMahon, C.; Kelleher, K.; McGinnity, P.; Organo, C.; Smith, K.; Currivan, L.; Ryan, T.

    2013-05-01

    The UK Government has identified up to eight locations for the construction of new nuclear power plants by 2025. Five of these locations are on the Irish Sea coast. The Radiological Protection Institute of Ireland, RPII was requested by the Minister for the Environment, Community and Local Government to undertake an assessment of the potential radiological impacts on Ireland from this New Build Programme. This report presents the findings of the potential impacts on Ireland of both the anticipated routine radioactive discharges and of a range of postulated nuclear accident scenarios. The following points are the principal findings of the report. Given the prevailing wind direction in Ireland, radioactive contamination in the air, either from routine operation of the proposed nuclear power plants or accidental releases, will most often be transported away from Ireland. The routine operation of the proposed nuclear power plants will have no measurable radiological impact on Ireland or the Irish marine environment. The severe accident scenarios assessed ranged in their estimated frequency of occurrance from 1 in 50,000 to 1 in 33 million per year. The assessment used a weather pattern that maximised the transfer of radioactivity to Ireland. For the severe accident scenarios assessed, food controls or agriculture protective measures would generally be required in Ireland to reduce exposure of the population so as to mitigate potential long-term health effects. In the accident scenario with an estimated 1 in 33 million chance of occurring, short-term measures such as staying indoors would also be advised as a precautionary measure. In general, the accidents with higher potential impact on Ireland are the ones least likely to occur. Regardless of the radiological impact, any accident at the proposed nuclear power plants leading to an increase of radioactivity levels in Ireland would have a socio-economic impact on Ireland. A major accidental release of radioactivity to

  16. The LHCb Muon Upgrade

    CERN Multimedia

    Cardini, A

    2013-01-01

    The LHCb collaboration is currently working on the upgrade of the experiment to allow, after 2018, an efficient data collection while running at an instantaneous luminosity of 2x10$^{33}$/cm$^{-2}$s$^{-1}$. The upgrade will allow 40 MHz detector readout, and events will be selected by means of a very flexible software-based trigger. The muon system will be upgraded in two phases. In the first phase, the off-detector readout electronics will be redesigned to allow complete event readout at 40 MHz. Also, part of the channel logical-ORs, used to reduce the total readout channel count, will be removed to reduce dead-time in critical regions. In a second phase, higher-granularity detectors will replace the ones installed in highly irradiated regions, to guarantee efficient muon system performances in the upgrade data taking conditions.

  17. Bi-Provincial Upgrader

    International Nuclear Information System (INIS)

    1997-01-01

    Husky Oil's Bi-Provincial Upgrader is located in the rural municipality of Wilton, east of Lloydminster, Saskatchewan. It is jointly owned by Husky Oil and the Saskatchewan government. The upgrader is designed to produce 7.300 m 3 /cd of synthetic crude from 8.440 m 3 /cd of diluted Lloyd blend and distillates from the existing Lloydminster refinery. The designed coke and sulphur production is 415 t/day and 240 t/day respectively. Chronology of the Bi-Provincial Upgrader project was presented, along with details of the heavy oil feedstock properties for Cold Lake, Lloydminster and Lloyd Blend. Upgrader production history since start-up, synthetic crude oil customers, and the evolution of prices for Edmonton light vs. Husky LLB at Hardisty were also reviewed. 3 tabs., 9 figs

  18. LEP is upgraded

    CERN Multimedia

    1995-01-01

    A superconducting radio-frequency cavity is installed on the Large Electron-Positron (LEP) collider. This upgrade, known as LEP-2, allowed the accelerator to reach new, higher energies and so investigate new areas of physics.

  19. Proposal on nuclear information Hub in Asia. Placing stress on nuclear power utilization

    International Nuclear Information System (INIS)

    Nakasugi, Hideo

    2008-01-01

    Recently, several countries in Asia expressed official interest in nuclear power introduction toward 2020s. In designing the nuclear power introduction, estimation of required amount of resources, i.e. workload, personnel, facilities and budget corresponding to them, based upon indigenous conditions of the country, is a matter of great importance. For objective estimation, use of reliable information is indispensable, and from this point databases play essential role. However, it is not easy to reach suitable information for the purpose, due to reliability, significance, and freshness of data, and due to troublesomeness to retrieve key-words among similar data in a great quantity. For easier use, Japan Atomic Industrial Forum, Inc. (JAIF) would like to propose the information system which includes 'Asian Nuclear Information Web-Site' and 'Nuclear Information Database in Asia'. Expected participants of this system are: 1) country or area with official commitment or interest in nuclear power, and 2) organization with capacity for information provision. JAIF provisionally desires Australia, Bangladesh, China, India, Indonesia, Japan, Kazakhstan, Republic of Korea, Malaysia, Myanmar, Mongolia, Pakistan, the Philippines, Taiwan Area, Thailand, Uzbekistan, and Vietnam, for a start, to support this system. Cooperation, including publishing newsletter and holding study or symposia, could be carried out. (author)

  20. Ichthyoplankton entrainment at Wylfa power station, Anglesey and implications for a further siting proposal

    International Nuclear Information System (INIS)

    Dempsey, C.H.; Rogers, S.I.

    1989-07-01

    A 12 month survey of ichthyoplankton in the cooling water system of Wylfa Power Station and the surrounding 40 km 2 of sea, was carried out between October 1986 and September 1987. The larvae of 31 species and the eggs of 8 species were identified in the survey. Samples taken from the cooling water system and by boat from offshore were largely similar in respect of species diversity and density. Estimates of annual losses due to entrainment are given both in terms of immediate losses and consequential losses of adults to the population. Estimates of losses of six commercially exploited species are considered in terms of loss to the commercial fishery. Assuming the 'worst case' of a 100% mortality of eggs and larvae passing through the cooling system, losses of ichthyoplankton due to entrainment at the existing 'magnox' nuclear power station at Wylfa Point are small and could have no significant adverse effect on fish populations of those species entrained. The operation of the proposed 'pressurised water reactor' nuclear power station on the same site would increase losses by up to 100%. Such an increase would still not alter the existing situation. No significant adverse effect is likely. (author)

  1. LHC Status and Upgrade Challenges

    Science.gov (United States)

    Smith, Jeffrey

    2009-11-01

    The Large Hadron Collider has had a trying start-up and a challenging operational future lays ahead. Critical to the machine's performance is controlling a beam of particles whose stored energy is equivalent to 80 kg of TNT. Unavoidable beam losses result in energy deposition throughout the machine and without adequate protection this power would result in quenching of the superconducting magnets. A brief overview of the machine layout and principles of operation will be reviewed including a summary of the September 2008 accident. The current status of the LHC, startup schedule and upgrade options to achieve the target luminosity will be presented.

  2. ECRH experiments in ASDEX Upgrade

    International Nuclear Information System (INIS)

    Leuterer, F.; Guenter, S.; Hobirk, J.; Kirov, K.; Ryter, F.; Wolf, R.; Zohm, H.; Gantenbein, G.

    2001-01-01

    In ASDEX Upgrade ECRH and ECCD with a power of up to 2 MW has been used. With counter ECCD in discharges with an internal transport barrier we achieved an electron temperature of ≅13 keV. In low density ohmic plasmas we obtained an rf driven current of ≅80% both in co- and counter directions. Neoclassical tearing modes have been completly stabilised by driving a current on the resonant q-surface. Electron heat transport has been studied in standard L- and H-mode plasmas and can be described by a dependence on a critical electron temperature gradient

  3. Experiences in controlling the upgrading of TRIGA 2000 Bandung reactor

    International Nuclear Information System (INIS)

    Huda, K.; Wibowo, Y.W.; Suprawhardana, M.S.

    2001-01-01

    TRIGA 2000 Bandung Reactor was established in 1961 for research, education and isotope production purposes. The reactor reached its first criticality in October 1964 and operated at nominal power of 250 kW until 1971. In 1971 the reactor was upgraded to the power level of 1000 kW. In order to raise the capacity of isotope production, the reactor has been upgraded again to the power level of 2000 kW. During the modification of the reactor, the Center for Research and Development of Nuclear Techniques (CRDNT) was management of the reactor as it faced many problems, either technical or non-technical ones. This caused the upgrading activities to take a long time. At this time, the reactor upgrading has almost finished, and the nuclear commissioning is going on. Several aspects and problems associated with the upgrading process have been reviewed and the results are discussed in the present paper. (author)

  4. Status of the Upgrade of the CERN PS Booster

    CERN Document Server

    Hanke, K; Angoletta, M; Bartmann, W; Bartolome, S; Benedetto, E; Bertone, C; Blas, A; Bonnal, P; Borburgh, J; Bozzini, D; Butterworth, A; Carli, C; Carlier, E; Cole, J; Dahlen, P; Delonca, M; Dobers, T; Findlay, A; Froeschl, R; Hansen, J; Hay, D; Jensen, S; Lacroix, J; Le Roux, P; Lopez Hernandez, L; Maglioni, C; Masi, A; Mason, G; Mathot, S; Mikulec, B; Muttoni, Y; Newborough, A; Nisbet, D; Olek, S; Paoluzzi, M; Perillo-Marcone, A; Pittet, S; Puccio, B; Raginel, V; Riffaud, B; Ruehl, I; Sarrió Martínez, A; Tan, J; Todd, B; Venturi, V; Weterings, W

    2013-01-01

    The CERN PS Booster (PSB) is presently undergoing an ambitious consolidation and upgrade program within the frame of the LHC Injectors Upgrade (LIU) project. This program comprises a new injection scheme for H- ions from CERN’s new Linac4, the replacement of the main RF systems and an energy upgrade of the PSB rings from 1.4 to 2 GeV which includes the replacement of the main magnet power supply as well as the upgrade of the extraction equipment. This paper describes the status and plans of this work program.

  5. High efficiency H6 single-phase transformerless grid-tied PV inverter with proposed modulation for reactive power generation

    Science.gov (United States)

    Almasoudi, Fahad M.; Alatawi, Khaled S.; Matin, Mohammad

    2017-08-01

    Implementation of transformerless inverters in PV grid-tied system offer great benefits such as high efficiency, light weight, low cost, etc. Most of the proposed transformerless inverters in literature are verified for only real power application. Currently, international standards such as VDE-AR-N 4105 has demanded that PV grid-tied inverters should have the ability of controlling a specific amount of reactive power. Generation of reactive power cannot be accomplished in single phase transformerless inverter topologies because the existing modulation techniques are not adopted for a freewheeling path in the negative power region. This paper enhances a previous high efficiency proposed H6 trnasformerless inverter with SiC MOSFETs and demonstrates new operating modes for the generation of reactive power. A proposed pulse width modulation (PWM) technique is applied to achieve bidirectional current flow through freewheeling state. A comparison of the proposed H6 transformerless inverter using SiC MOSFETs and Si MOSFTEs is presented in terms of power losses and efficiency. The results show that reactive power control is attained without adding any additional active devices or modification to the inverter structure. Also, the proposed modulation maintains a constant common mode voltage (CM) during every operating mode and has low leakage current. The performance of the proposed system verifies its effectiveness in the next generation PV system.

  6. GTHTR300 cost reduction through design upgrade and cogeneration

    Energy Technology Data Exchange (ETDEWEB)

    Yan, Xing L., E-mail: yan.xing@jaea.go.jp; Sato, Hiroyuki; Kamiji, Yu; Imai, Yoshiyuki; Terada, Atsuhiko; Tachibana, Yukio; Kunitomi, Kazuhiko

    2016-09-15

    Japan Atomic Energy Agency began design and development of the Gas Turbine High Temperature Reactor of 300MWe nominal output (GTHTR300) in 2001. The reactor baseline design completed three years later was based on 850 °C core outlet temperature and a direct cycle gas turbine balance of plant. It attained 45.6% net power generation efficiency and 3.5 US¢/kW h cost of electricity. The cost was estimated 20% lower than LWR. The latest design upgrade has incorporated several major technological advances made in the past ten years to both reactor and balance of plant. As described in this paper, these advances have enabled raising the design basis reactor core outlet temperature to 950 °C and increasing power generating efficiency by nearly 5% point. Further implementation of seawater desalination cogeneration is made through employing a newly-proposed multi-stage flash process. Through efficient waste heat recovery of the reactor gas turbine power conversion cycle, a large cost credit is obtained against the conventionally produced water prices. Together, the design upgrade and the cogeneration are shown to reduce the GTHTR300 cost of electricity to under 2.7 US¢/kW h.

  7. GTHTR300 cost reduction through design upgrade and cogeneration

    International Nuclear Information System (INIS)

    Yan, Xing L.; Sato, Hiroyuki; Kamiji, Yu; Imai, Yoshiyuki; Terada, Atsuhiko; Tachibana, Yukio; Kunitomi, Kazuhiko

    2014-01-01

    Japan Atomic Energy Agency began design and development of the Gas Turbine High Temperature Reactor of 300MWe nominal output (GTHTR300) in 2001. The reactor baseline design completed three years later was based on 850°C core outlet temperature and a direct cycle gas turbine balance of plant. It attained 45.6% net power generation efficiency and 3.5US¢/KWh cost of electricity. The cost was estimated 20% lower than LWR. The latest design upgrade has incorporated several major technological advances made in the past ten years to both reactor and balance of plant. As described in this paper, these advances have enabled raising the design basis reactor core outlet temperature to 950°C and increasing power generating efficiency by nearly 5% point. Further implementation of seawater desalination cogeneration is made through employing a newly-proposed multi-stage flash process. Through efficient waste heat recovery of the reactor gas turbine power conversion cycle, a large cost credit is obtained against the conventionally produced water prices. Together, the design upgrade and the cogeneration are shown to reduce the GTHTR300 cost of electricity to under 2.7 US¢/KWh. (author)

  8. Analysis of public comments on the proposed rule on nuclear power plant license renewal

    International Nuclear Information System (INIS)

    1991-12-01

    This report provides a summary and analysis of public comments on the proposed license renewal rule for the nuclear power plants (10 CFR Part 54) published in the Federal Register on 17 July 1990. It also documents the NRC's resolution of the issues raised by the commenters. Comments from 121 organizations and 76 individuals were reviewed and analyzed to identify the issues, including those pertaining to the adequacy of the licensing basis, the performance of an integrated plant assessment, backfit considerations, and need for public hearings. The analysis included grouping of commenters' views according to the issues raised. The public comments analyzed in this report were taken into consideration in the development of the final rule and revisions to the supporting documents

  9. Technical evaluation of the proposed changes in the technical specifications for emergency power sources for the Big Rock Point nuclear power plant

    International Nuclear Information System (INIS)

    Latorre, V.R.

    1979-12-01

    The technical evaluation is presented for the proposed changes to the Technical Specifications for emergency power sources for the Big Rock Point nuclear power plant. The criteria used to evaluate the acceptability of the changes include those delineated in IEEE Std-308-1974, and IEEE Std-450-1975 as endorsed by US NRC Regulatory Guide 1.129

  10. Possible neutral beam requirements for TFTR upgrades

    International Nuclear Information System (INIS)

    Prichard, B.A. Jr.; Little, R.; Post, D.E.; Schmidt, J.A.

    1977-01-01

    A discussion is provided of possible neutral beam requirements and constraints for a TFTR upgrade. The time scale is the early 80s and beams of 250 keV D 0 , probably using 65 ampere negative ion sources, existing power supplies and vacuum enclosures would be required

  11. Cuba: Juragua NPP. Upgrades. Modifications and improvements. Annex 5A

    International Nuclear Information System (INIS)

    Gonzales Aguilera, H.

    1999-01-01

    This annex deals with upgrades - modifications and improvements. Planning for resumption of work at Juragua NPP is under way, and a strategic plan of upgrades and modifications has been prepared. The proposed improvements were categorized, reviewed by the regulatory body and generally approved. This annex outlines the format of the plan. (author)

  12. Towards Optimum Material Choices for HL-LHC Collimator Upgrade

    CERN Document Server

    Quaranta, E.; Biancacci, N.; Bruce, R.; Carra, F.; Métral, E.; Redaelli, S.; Rossi, A.; Salvant, B.

    2016-01-01

    properties that address different limitations of the present collimation system, solutions have been found to fulfil various upgrade challenges. This paper describes the proposed staged approach to deploy new materials in the upgraded HL-LHC collimation system. Beam tests at the CERN HiRadMat facility were also performed to benchmark simulation methods and constitutive material models.

  13. Proposed Suitable Methods to Detect Transient Regime Switching to Improve Power Quality with Wavelet Transform

    Directory of Open Access Journals (Sweden)

    Javad Safaee Kuchaksaraee

    2016-10-01

    Full Text Available The increasing consumption of electrical energy and the use of non-linear loads that create transient regime states in distribution networks is increasing day by day. This is the only reason due to which the analysis of power quality for energy sustainability in power networks has become more important. Transients are often created by energy injection through switching or lightning and make changes in voltage and nominal current. Sudden increase or decrease in voltage or current makes characteristics of the transient regime. This paper shed some lights on the capacitor bank switching, which is one of the main causes for oscillatory transient regime states in the distribution network, using wavelet transform. The identification of the switching current of capacitor bank and the internal fault current of the transformer to prevent the unnecessary outage of the differential relay, it propose a new smart method. The accurate performance of this method is shown by simulation in EMTP and MATLAB (matrix laboratory software.

  14. Proposals for Enhancing Frequency Control in Weak and Isolated Power Systems: Application to the Wind-Diesel Power System of San Cristobal Island-Ecuador

    Directory of Open Access Journals (Sweden)

    Danny Ochoa

    2018-04-01

    Full Text Available Wind-diesel hybridization has been emerging as common practice for electricity generation in many isolated power systems due to its reliability and its contribution in mitigating environmental issues. However, the weakness of these kind of power systems (due to their small inertia makes the frequency regulation difficult, particularly under high wind conditions, since part of the synchronous generation has to be set offline for ensuring a suitable tracking of the power demand. This reduces the power system’s ability to absorb wind power variations, leading to pronounced grid frequency fluctuations under normal operating conditions. This paper proposes some corrective actions aimed at enhancing the frequency control capability in weak and isolated power systems: a procedure for evaluating the system stability margin intended for readjusting the diesel-generator control gains, a new wind power curtailment strategy, and an inertial control algorithm implemented in the wind turbines. These proposals are tested in the San Cristobal (Galapagos Islands-Ecuador hybrid wind-diesel power system, in which many power outages caused by frequency relays tripping were reported during the windiest season. The proposals benefits have been tested in a simulation environment by considering actual operating conditions based on measurement data recorded at the island.

  15. The ALICE TPC Upgrad

    Science.gov (United States)

    Castro, Andrew; Alice-Usa Collaboration; Alice-Tpc Collaboration

    2017-09-01

    The Time Projection Chamber (TPC) currently used for ALICE (A Large Ion Collider Experiment at CERN) is a gaseous tracking detector used to study both proton-proton and heavy-ion collisions at the Large Hadron Collider (LHC) In order to accommodate the higher luminosit collisions planned for the LHC Run-3 starting in 2021, the ALICE-TPC will undergo a major upgrade during the next LHC shut down. The TPC is limited to a read out of 1000 Hz in minimum bias events due to the intrinsic dead time associated with back ion flow in the multi wire proportional chambers (MWPC) in the TPC. The TPC upgrade will handle the increase in event readout to 50 kHz for heavy ion minimum bias triggered events expected with the Run-3 luminosity by switching the MWPCs to a stack of four Gaseous Electron Multiplier (GEM) foils. The GEM layers will combine different hole pitches to reduce the dead time while maintaining the current spatial and energy resolution of the existing TPC. Undertaking the upgrade of the TPC represents a massive endeavor in terms of design, production, construction, quality assurance, and installation, thus the upgrade is coordinated over a number of institutes worldwide. The talk will go over the physics motivation for the upgrade, the ALICE-USA contribution to the construction of Inner Read Out Chambers IROCs, and QA from the first chambers built in the U.S

  16. 75 FR 1408 - Pick-Sloan Missouri Basin Program, Eastern and Western Division Proposed Project Use Power Rate

    Science.gov (United States)

    2010-01-11

    ... of Proposed Pick-Sloan Missouri Basin Program, Eastern and Western Divisions, Project Use Power Rate...) for Project Use Power for the Pick-Sloan Missouri Basin Program (P-SMBP), Eastern and Western... DEPARTMENT OF THE INTERIOR Bureau of Reclamation Pick-Sloan Missouri Basin Program, Eastern and...

  17. Experience from design, prototyping and production of a DC–DC conversion powering scheme for the CMS Phase-1 Pixel Upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Feld, Lutz, E-mail: Lutz.Feld@cern.ch; Karpinski, Waclaw; Klein, Katja; Lipinski, Martin; Preuten, Marius; Rauch, Max; Schmitz, Stefan; Wlochal, Michael

    2017-02-11

    The CMS pixel detector will be replaced during the technical stop 2016/2017. To allow the new pixel detector to be powered with the legacy cable plant and power supplies, a novel powering scheme based on DC–DC conversion will be employed. After the successful conclusion of an extensive development and prototyping phase, mass production of 1800 DC–DC converters as well as motherboards and other power PCBs has now been completed. This contribution reviews the lessons learned from the development of the power system for the Phase-1 pixel detector, and summarizes the experience gained from the production phase.

  18. ATLAS Upgrade Programme

    CERN Document Server

    Hillier, S J; The ATLAS collaboration

    2012-01-01

    With the already outstanding LHC luminosity performance, and planned LHC upgrades in the upcoming shutdowns, it is expected that within a short time-scale, the general purpose LHC experiments will have to cope with luminosities beyond their original design. In order to maintain detector performance and sensitivity to expected and new physics processes, ATLAS has defined a continuous upgrade programme which foresees staged enhancements during the next 10 years of operation, and then more widespread changes before the transition to the highest luminosities after 2022. This talk will describe several components of the ATLAS upgrade, focusing in particular on the Inner Detector and Trigger. The Inner Detector faces two challenges in the higher luminosity environment: high particle multiplicities and increased radiation dose. These will be addressed in the short term by a new layer of Pixel detectors, and in the long term by a complete replacement. The Trigger faces an increasingly difficult task of distinguishing...

  19. Upgradation of Apsara reactor

    International Nuclear Information System (INIS)

    Mammen, S.; Mukherjee, P.; Bhatnagar, A.; Sasidharan, K.; Raina, V.K.

    2009-01-01

    Apsara is a 1 MW swimming pool type research reactor using high enriched uranium as fuel with light water as coolant and moderator. The reactor is in operation for more than five decades and has been extensively used for basic research, radioisotope production, neutron radiography, detector testing, shielding experiments etc. In view of its long service period, it is planned to carry out refurbishment of the reactor to extend its useful life. During refurbishment, it is also planned to upgrade the reactor to a 2 MW reactor to improve its utilization and to upgrade the structure, system and components in line with the current safety standards. This paper gives a brief account of the design features and safety aspects of the upgraded Apsara reactor. (author)

  20. The CDF SVX II detector upgrade

    International Nuclear Information System (INIS)

    Skarha, J.E.

    1993-10-01

    The proposed CDF SVX II detector upgrade for secondary vertex detection during the Fermilab Tevatron Run II collider run is described. The general design and important features of this silicon vertex detector are presented. The CDF physics goals which are addressed by this detector are also given

  1. Survey of radionuclide emissions from coal-fired power plants and examination of impacts from a proposed circulating fluidized bed boiler power plant

    International Nuclear Information System (INIS)

    Steiner, C.P.; Militana, L.M.; Harvey, K.A.; Kinsey, G.D.

    1995-01-01

    This paper presents the results of a literature survey that examined radionuclide emissions from coal-fired power plants. Literature references from both the US and foreign countries are presented. Emphasis is placed on references from the US because the radionuclide emissions from coal-fired power plants are related to radionuclide concentrations in the coal, which vary widely throughout the world. The radionuclides were identified and quantified for various existing power plants reported in the literature. Applicable radionuclide emissions criteria discovered in the literature search were then applied to a proposed circulating fluidized bed boiler power plant. Based upon the derived radionuclide emission rates applied to the proposed power plant, an air quality modeling analysis was performed. The estimated ambient concentrations were compared to the most relevant existing regulatory ambient levels for radionuclides

  2. Tackling Chinese Upgrading through Experimentalism and Pragmatism

    DEFF Research Database (Denmark)

    Kirkegaard, Julia Kirch

    2017-01-01

    This paper examines the development of China’s wind turbine industry, shedding light on the Chinese mode of disruptive industrial upgrading through policy pragmatism and fragmented, experimental governance. Based on a historical analysis of China’s wind turbine industry, the paper highlights three...... distinct phases, which are all marked by their own inbuilt and potentially self-disruptive impasses and associated crises. In turn, these impasses have forced the Chinese government into radical and flexible interventions, which have spurred on Chinese companies to creatively find new ways to develop...... and upgrade. The paper illustrates the transformation of Sino–foreign relations by China’s non-linear upgrading approach, particularly during the Chinese wind power industry’s quality crisis, and its development model. It also discusses the implications this examination of China’s approach has...

  3. The UKIRT Upgrades Programme

    Science.gov (United States)

    Adamson, Andy; Davies, John; Robson, Ian

    Tim Hawarden presented this paper to the 30th anniversary workshop, just a month before his untimely death. The editors have done their best to convert his talk into this paper, and gratefully acknowledge the assistance of Nick Rees (a member of the Upgrades team, now at Diamond Light Source). Tim's discussion concerned the UKIRT Upgrades Project, which ran through the 1990s and transformed the telescope and made it truly competitive on the world stage for operation into the twenty-first century. The reference list at the end of the paper is comprehensive; some of these are referred to in the paper itself and some are included for completeness only.

  4. AGS intensity upgrades

    International Nuclear Information System (INIS)

    Roser, T.

    1995-01-01

    After the successful completion of the AGS Booster and several upgrades of the AGS, a new intensity record of 6.3 x 10 13 protons per pulse accelerated to 24 GeV was achieved. The high intensity slow-extracted beam program at the AGS typically serves about five production targets and about eight experiments including three rare Kaon decay experiments. Further intensity upgrades are being discussed that could increase the average delivered beam intensity by up to a factor of four

  5. OMEGA upgrade staging options

    International Nuclear Information System (INIS)

    Kelly, J.H.; Shoup, M.J.; Smith, D.L.

    1989-01-01

    The authors discuss how they are designing an upgrade to its 24-beam OMEGA laser system, OMEGA is a frequency tripled, all-rod system capable of producing 2 kJ at 0.8 ns on target. Important direct-drive-target-ignition physics could be investigated with an upgraded system capable of producing a shaped pulse consisting of a long (5ns) low-intensity, foot, smoothly transitioning into a short (0.5 ns), intense, compression pulse. The total pulse energy is 30 kJ, which, from target-irradiation uniformity considerations, must be distributed over 60 beams

  6. Climate balance of biogas upgrading systems

    International Nuclear Information System (INIS)

    Pertl, A.; Mostbauer, P.; Obersteiner, G.

    2010-01-01

    One of the numerous applications of renewable energy is represented by the use of upgraded biogas where needed by feeding into the gas grid. The aim of the present study was to identify an upgrading scenario featuring minimum overall GHG emissions. The study was based on a life-cycle approach taking into account also GHG emissions resulting from plant cultivation to the process of energy conversion. For anaerobic digestion two substrates have been taken into account: (1) agricultural resources and (2) municipal organic waste. The study provides results for four different upgrading technologies including the BABIU (Bottom Ash for Biogas Upgrading) method. As the transport of bottom ash is a critical factor implicated in the BABIU-method, different transport distances and means of conveyance (lorry, train) have been considered. Furthermore, aspects including biogas compression and energy conversion in a combined heat and power plant were assessed. GHG emissions from a conventional energy supply system (natural gas) have been estimated as reference scenario. The main findings obtained underlined how the overall reduction of GHG emissions may be rather limited, for example for an agricultural context in which PSA-scenarios emit only 10% less greenhouse gases than the reference scenario. The BABIU-method constitutes an efficient upgrading method capable of attaining a high reduction of GHG emission by sequestration of CO 2 .

  7. VISIR upgrade overview and status

    Science.gov (United States)

    Kerber, Florian; Käufl, Hans Ulrich; Baksai, Pedro; Dobrzycka, Danuta; Finger, Gert; Ives, Derek; Jakob, Gerd; Lagadec, Eric; Lundin, Lars; Mawet, Dimitri; Mehrgan, Leander; Moerchen, Margaret; Momany, Yazan; Moreau, Vincent; Pantin, Eric; Riquelme, Miguel; Siebenmorgen, Ralf; Silber, Armin; Smette, Alain; Taylor, Julian; van den Ancker, Mario; Venema, Lars; Weilenmann, Ueli; Yegorova, Irina

    2012-09-01

    We present an overview of the VISIR upgrade project. VISIR is the mid-infrared imager and spectrograph at ESO's VLT. The project team is comprised of ESO staff and members of the original VISIR consortium: CEA Saclay and ASTRON. The project plan is based on input from the ESO user community with the goal of enhancing the scientific performance and efficiency of VISIR by a combination of measures: installation of improved hardware, optimization of instrument operations and software support. The cornerstone of the upgrade is the 1k by 1k Si:As Aquarius detector array (Raytheon) which has demonstrated very good performance (sensitivity, stability) in the laboratory IR detector test facility (modified TIMMI 2 instrument). A prism spectroscopic mode will cover the N-band in a single observation. New scientific capabilities for high resolution and high-contrast imaging will be offered by sub-aperture mask (SAM) and phase-mask coronagraphic (4QPM/AGPM) modes. In order to make optimal use of favourable atmospheric conditions a water vapour monitor has been deployed on Paranal, allowing for real-time decisions and the introduction of a userdefined constraint on water vapour. Improved pipelines based on the ESO Reflex concept will provide better support to astronomers. The upgraded VISIR will be a powerful instrument providing background limited performance for diffraction-limited observations at an 8-m telescope. It will offer synergy with facilities such as ALMA, JWST, VLTI and SOFIA, while a wealth of targets is available from survey work (e.g. VISTA, WISE). In addition it will bring confirmation of the technical readiness and scientific value of several aspects of potential mid-IR instrumentation at Extremely Large Telescopes. The intervention on VISIR and installation of hardware has been completed in July and commissioning will take place during July and August. VISIR is scheduled to be available to the users starting Oct 2012.

  8. Upgrade of the CMS hardron calorimeter for an upgraded LHC

    OpenAIRE

    Anderson, Jake

    2012-01-01

    The CMS barrel and endcap hadron calorimeters (Hcal) upgrading the current photo-sensors are hybrid photodiodes (HPDs) to meet the demands of the upgraded luminosity of the LHC. A key aspect of the Hcal upgrade is to add longitudinal segmentation to improve background rejection, energy resolution, and electron isolation at L1 trigger. The increased segmentation can be achieved by replacing the HPD's with multi-pixel Geiger-mode avalanche photodiodes. The upgraded electron...

  9. A proposal of safety indicators aggregation to assess the safety management effectiveness of nuclear power plants

    International Nuclear Information System (INIS)

    Carvalho, Jose Antonio B.; Saldanha, Pedro L.C.; Melo, Paulo F.F. Frutuoso e

    2009-01-01

    Safety management has changed with the evolution of management methods, named Quality Systems, moving from Quality Control, where the focus was the product, passing through Quality Assurance, which takes care of the whole manufacturing process and reaching the Total Quality Management, where policies and goals are established. Nowadays, there is a trend towards Management Systems, which integrate all different aspects related to the management of an organization (safety, environment, security, quality, costs and, etc), but it is necessary to have features to establish and assure that safety overrides the remaining aspects. The most usual way to reach this goal is to establish a policy where safety is a priority, but its implementation and the assessment of its effectiveness are no so simple. Nuclear power plants usually have over a hundred safety indicators in many processes dedicated to prevent and detect problems, although a lot of them do not evaluate these indicators in an integrated manner or point out degradation trends of organizational aspects, which can affect the plant safety. This work develops an aggregation of proactive and reactive safety indicators in order to evaluate the effectiveness of nuclear power plant safety management and to detect, at early stages, signs of process degradation or activities used to establish, maintain and assure safety conditions. The aggregation integrates indicators of the usual processes and is based on the manner the management activities have been developed in the last decades, that is: Planning, Doing, Checking and Acting - known as PDCA cycle - plus a fifth element related to the capability of those who perform safety activities. The proposed aggregation is in accordance to Brazilian standards and international recommendations and constitutes a friendly link between the top management level and the daily aspects of the organization. (author)

  10. A proposal of safety indicators aggregation to assess the safety management effectiveness of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Jose Antonio B.; Saldanha, Pedro L.C. [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Coordenacao-Geral de Reatores e Ciclo Combustivel], e-mail: jantonio@cnen.gov.br, e-mail: saldanha@cnen.gov.br; Melo, Paulo F.F. Frutuoso e [Coordenacao dos Programas de Pos-graduacao de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear], e-mail: frutuoso@con.ufrj.br

    2009-07-01

    Safety management has changed with the evolution of management methods, named Quality Systems, moving from Quality Control, where the focus was the product, passing through Quality Assurance, which takes care of the whole manufacturing process and reaching the Total Quality Management, where policies and goals are established. Nowadays, there is a trend towards Management Systems, which integrate all different aspects related to the management of an organization (safety, environment, security, quality, costs and, etc), but it is necessary to have features to establish and assure that safety overrides the remaining aspects. The most usual way to reach this goal is to establish a policy where safety is a priority, but its implementation and the assessment of its effectiveness are no so simple. Nuclear power plants usually have over a hundred safety indicators in many processes dedicated to prevent and detect problems, although a lot of them do not evaluate these indicators in an integrated manner or point out degradation trends of organizational aspects, which can affect the plant safety. This work develops an aggregation of proactive and reactive safety indicators in order to evaluate the effectiveness of nuclear power plant safety management and to detect, at early stages, signs of process degradation or activities used to establish, maintain and assure safety conditions. The aggregation integrates indicators of the usual processes and is based on the manner the management activities have been developed in the last decades, that is: Planning, Doing, Checking and Acting - known as PDCA cycle - plus a fifth element related to the capability of those who perform safety activities. The proposed aggregation is in accordance to Brazilian standards and international recommendations and constitutes a friendly link between the top management level and the daily aspects of the organization. (author)

  11. Proposal and Development of a High Voltage Variable Frequency Alternating Current Power System for Hybrid Electric Aircraft

    Science.gov (United States)

    Sadey, David J.; Taylor, Linda M.; Beach, Raymond F.

    2017-01-01

    The development of ultra-efficient commercial vehicles and the transition to low-carbon emission propulsion are seen as strategic thrust paths within NASA Aeronautics. A critical enabler to these paths comes in the form of hybrid electric propulsion systems. For megawatt-class systems, the best power system topology for these hybrid electric propulsion systems is debatable. Current proposals within NASA and the Aero community suggest using a combination of alternating current (AC) and direct current (DC) for power generation, transmission, and distribution. This paper proposes an alternative to the current thought model through the use of a primarily high voltage AC power system, supported by the Convergent Aeronautics Solutions (CAS) Project. This system relies heavily on the use of doubly-fed induction machines (DFIMs), which provide high power densities, minimal power conversion, and variable speed operation. The paper presents background on the activity along with the system architecture, development status, and preliminary results.

  12. La superación del profesorado en educación intercultural: una propuesta para la universidad cubana actual / Teacher’s upgrading on intercultural education. A proposal of the cuban contemporary university

    Directory of Open Access Journals (Sweden)

    Cabrera Ruiz, Isaac Iran

    2008-08-01

    article we present a diplomat as a suggestion of a course for the cultural upgrading of a pedagogical staff of the academic year, featured by its flexibility, use of the New Technologies of Communication and contextualization. This proposal is also conceived with the distant - learning method which is a research result from the Medical University within the years 2006 -2007.

  13. LHC Interaction Region Upgrade Phase I

    CERN Document Server

    Ostojic, R

    2009-01-01

    The LHC is starting operation with beam in 2008. The primary goal of CERN and the LHC community is to ensure that the collider is operated efficiently, maximizing its physics reach, and to achieve the nominal performance in the shortest term. Since several years the community has been discussing the directions for upgrading the experiments, in particular ATLAS and CMS, the LHC machine and the CERN proton injector complex. A well substantiated and coherent scenario for the first phase of the upgrade, which is foreseen in 2013, is now approved by CERN Council. In this paper, we present the goals and the proposed conceptual solution for the Phase-I upgrade of the LHC interaction regions. This phase relies on the mature Nb-Ti superconducting magnet technology, with the target of increasing the luminosity by a factor of 2-3 with respect to the nominal luminosity of 1034 cm-2s-1, while maximising the use of the existing infrastructure.

  14. Upgrading Probability via Fractions of Events

    Directory of Open Access Journals (Sweden)

    Frič Roman

    2016-08-01

    Full Text Available The influence of “Grundbegriffe” by A. N. Kolmogorov (published in 1933 on education in the area of probability and its impact on research in stochastics cannot be overestimated. We would like to point out three aspects of the classical probability theory “calling for” an upgrade: (i classical random events are black-and-white (Boolean; (ii classical random variables do not model quantum phenomena; (iii basic maps (probability measures and observables { dual maps to random variables have very different “mathematical nature”. Accordingly, we propose an upgraded probability theory based on Łukasiewicz operations (multivalued logic on events, elementary category theory, and covering the classical probability theory as a special case. The upgrade can be compared to replacing calculations with integers by calculations with rational (and real numbers. Namely, to avoid the three objections, we embed the classical (Boolean random events (represented by the f0; 1g-valued indicator functions of sets into upgraded random events (represented by measurable {0; 1}-valued functions, the minimal domain of probability containing “fractions” of classical random events, and we upgrade the notions of probability measure and random variable.

  15. Water quality around proposed nuclear power plant at Gorakhpur Haryana, India

    International Nuclear Information System (INIS)

    Singh, Kuldeep; Yadav, Anoop; Garg, V.K.; Bishnoi, Mukul; Pal, Jitender; Pulhani, Vandana; Narayanan, Usha

    2012-01-01

    The surface and ground water are being polluted by natural as well as anthropogenic activities. Natural pollutants include acid rain and salts from rocks. Pollution added by anthropogenic activities include sewage and other wastes, industrial effluent as hardly 5% of total industries have adequate measures for the treatment of effluents. Water quality was assessed for its suitability for drinking purposes around proposed Nuclear Plant Site at Dist. Hisar/Fatehabad, Haryana. The study was undertaken to established baseline levels of water parameters during pre-operational phase of the proposed nuclear power plant. A total 103 samples were have been collected from different sampling locations around of around proposed Nuclear Plant Site. Water samples were collected from the bore-wells, wells, municipal water supplies, ponds, canal and hand pumps were analyzed for the various physico-chemical parameters including pH, Electrical Conductivity (EC), Total Dissolved Salts (TDS), Total Hardness (TH), Total Alkalinity (TA), Sodium, Potassium, Calcium, Magnesium, Carbonate, Bicarbonate, Chloride, Fluoride, Sulphate, Nitrate and phosphate. The samples were collected and analysed as per standard methods within 24h of sampling. The results indicate considerable variations in physic-chemical properties of the analysed water samples. The pH was neutral to alkaline at all the studied locations, ranging from 7.0-9.7 at different locations. Salinity ranged from 0.1-0.63 mg/l and Total alkalinity (as CaCO 3 ) ranged from 43.2-528 mg/l. Most of the samples were slightly to moderately hard. Total hardness content (as CaCO 3 ) ranged from 1.7-1512 mg/l. Fluoride content in the groundwater of the study area ranged from 0.4-2.1 mg/l for fluoride. Majority of the samples do not comply with Indian as well as WHO standards for most of the water quality parameters measured. Mostly, surface water (canal water) is supplied to the general public by the public water supply department for

  16. Treat upgrade fuel fabrication

    International Nuclear Information System (INIS)

    Davidson, K.V.; Schell, D.H.

    1979-01-01

    An extrusion and thermal treatment process was developed to produce graphite fuel rods containing a dispersion of enriched UO 2 . These rods will be used in an upgraded version of the Transient Reactor Test Facility (TREAT). The improved fuel provides a higher graphite matrix density, better fuel dispersion and higher thermal capabilities than the existing fuel

  17. ATLAS Pixel Detector Upgrade

    CERN Document Server

    Flick, T; The ATLAS collaboration

    2009-01-01

    The first upgrade for higher luminosity at LHC for the ATLAS pixel detector is the insertion of a forth layer, the IBL. The talk gives an overview about what the IBL is and how it will be set up, as well as to give a status of the research and develoment work.

  18. Upgrading Undergraduate Biology Education

    Science.gov (United States)

    Musante, Susan

    2011-01-01

    On many campuses throughout the country, undergraduate biology education is in serious need of an upgrade. During the past few decades, the body of biological knowledge has grown exponentially, and as a research endeavor, the practice of biology has evolved. Education research has also made great strides, revealing many new insights into how…

  19. Upgrade of telephone exchange

    CERN Multimedia

    2006-01-01

    As part of the upgrade of telephone services, work will be carried out on the CERN switching centre between Monday 23 October 8.00 p.m. and Tuesday 24 October 2.00 a.m. Telephone services may be disrupted and possibly even interrupted during this operation. We apologise in advance for any inconvenience this may cause. CERN TELECOM Service

  20. Nuclear Power Plant Life Management - Challenges and Proposal for a Unified Model Integrating Safety and Economics

    International Nuclear Information System (INIS)

    Contri, Paolo; Elsing, Bernhard

    2011-01-01

    In recent years many electric utilities and nuclear power plants adopted policies for improved coordination of both safety and non-safety programs, called plant life management (PLIM), also in view on plant life extension programs, but mainly for an optimisation of operating costs. The implementation of PLIM programs has followed many different approaches, being intrinsically dependent on the national regulatory framework and technical traditions. In Countries with some experience, the PLIM program proved very convenient, especially when coupled with Maintenance, Surveillance an Inspection (MS and I) optimization: average savings are reported in the range of 20-30% of total (maintenance) costs. A unified European model for PLIM was developed at the JRC-Institute for Energy with the support of a network of stakeholders (SENUF), and validated at some EU nuclear plants. This paper provides a summary of the model features, the result of its validation at some plants and summarises the perceived scientific/technological challenges on which JRC proposes to focus, based upon its competencies and skills, having in mind both the European and world-wide context and its potential evolution. (author)

  1. Heavy water upgrader of 'Fugen'

    International Nuclear Information System (INIS)

    Matsushita, Tadashi; Sasaki, Shigeo

    1980-01-01

    The nuclear power station of the advanced thermal prototype reactor ''Fugen'' has continued the smooth operation since it started the fullscale operation in March, 1979. Fugen is the first heavy water-moderated, boiling light water-cooled reactor in Japan, and its outstanding feature is the use of heavy water as the moderator. The quantity of heavy water retained in Fugen is about 140 m 3 , and the concentration is 99.8 wt.%. This heavy water had been made is USA, and was imported from F.R. of Germany where it had been used. Heavy water is an internationally regulated material, and it is very expensive and hard to purchase. Therefore in order to prevent the deterioration of heavy water and to avoid its loss as far as possible, the management of the quantity and the control of the water quality have been carried out carefully and strictly. The generation of deteriorated heavy water occurs from the exchange of ion exchange resin for poison removal and purification. The heavy water upgrader reconcentrates the deteriorated heavy water of high concentration and returns to the heavy water system, and it was installed for the purpose of reducing the purchase of supplementary heavy water. The outline of the heavy water upgrader, its construction, the performance test and the operation are described. (Kako, I.)

  2. SRS control system upgrade requirements

    International Nuclear Information System (INIS)

    Hill, L.F.

    1998-01-01

    This document defines requirements for an upgrade of the Sodium Removal System (SRS) control system. The upgrade is being performed to solve a number of maintainability and operability issues. The upgraded system will provide the same functions, controls and interlocks as the present system, and in addition provide enhanced functionality in areas discussed in this document

  3. Performing instrumentation and controls upgrades

    International Nuclear Information System (INIS)

    Kessler, F. M.; Connell, T. J.; Ryan, M. P.

    1992-01-01

    I and C upgrades are comprised of a varying range of content, complexity, expansiveness, and criticality. There are common threads in all upgrades which can be simplified by the development of a long term I and C upgrade plan. The development of a such a plan can establish effective ground rules for upgrades, large and small. It can be the basis from which to begin an upgrade evaluation and the standard which is used to compare the degree of compliance of any upgrade regarding the plan or to define the differences from the plan and an individual upgrade. Primary motivation for I and C upgrades are obsolescence and unavailability of spare parts. Numerous other areas of consideration are also involved in an upgrade. Today's technology results in most upgrades largely or totally utilizing digital equipment. The use of digital equipment is fairly new in many I and C applications and requires an elaborate evaluation from functional, qualification, operational, and licensing perspectives as well as others. A well defined upgrade plan developed as a basis for I and C upgrades is a significant start to ensuring an effective upgrade process. Properly developed and implemented, the plan will support I and C upgrade efforts to ensure that the intricacies associated with such tasks eliminate the existing problems which require the upgrade to be performed. The upgrade plan also results in ensuring the maximum benefit from all perspectives of the plant enhancements being carried out and considered for future implementation. Instrumentation and controls aging and replacement are issues of growing importance due to the potential for significant impact on plant operation and efficiency. Obsolescence and unavailability of spare parts are major drivers towards evaluating the cost benefits of upgrading current equipment. In addition to these two primary factors, the advantages of utilizing digital equipment have also become of prime importance when evaluating instrumentation and

  4. Development of resilience evaluation method for nuclear power plant. Part 1. Proposal of resilience index for assessment of safety of nuclear power plant under severe accident

    International Nuclear Information System (INIS)

    Demachi, Kazuyuki; Suzuki, Masaaki; Itoi, Tatsuya

    2016-01-01

    In this research, a new index 'The Resilience Index' was proposed to evaluate the capability of nuclear power plant to recover from the situation of safety function lost. Three elements assumed to evaluate the resilience index are the achievement rate, necessary time, and probability of success of each accident management activity. The resilience index is expected to visualize the improvement of safety of each nuclear power plant against severe accidents. (author)

  5. Technical evaluation of the proposed deletion of a reactor trip on a turbine trip below 50-percent power for the Beaver Valley nuclear power plant, Unit 1

    International Nuclear Information System (INIS)

    Reeves, W.E.

    1979-12-01

    This report documents the technical evaluation of the Duquesne Light Company's proposed license amendment for the deletion of a reactor trip on a turbine trip below 50% power for the Beaver Valley nuclear power plant, Unit 1. This report is supplied as part of the Selected Electrical, Instrumentation, and Control Systems Issues Program being conducted for the US Nuclear Regulatory Commission by Lawrence Livermore Laboratory

  6. Psychiatric Power and Responsibility: Abuse and Abdication, A Proposed Corrective Conference.

    Science.gov (United States)

    Lehrman, Nathaniel S.

    1980-01-01

    Touches upon problems which result from abuses of governmental power--as, for example, in the case of governments diagnosing political dissenters as insane. Relates issues of power and responsibility to civil liberties and human rights. (Author/CK)

  7. Proposal for the Award of a Contract for the Supply of the Power Units for LHC Thyristor Power Converters

    CERN Document Server

    2003-01-01

    This document concerns the award of a contract for the supply of 12 power units of thyristor power converters rated from 365 to 770 kW for the LHC. Following a market survey carried out among 98 firms in nineteen Member States, a call for tenders (IT-3003/SL/LHC) was sent on 25 October 2002 to six firms in four Member States. By the closing date, CERN had received five tenders from five firms in four Member States. The Finance Committee is invited to agree to the negotiation of a contract with OCEM (IT), the lowest bidder, for the supply of 12 power units of thyristor power converters for a total amount of 981 484 Swiss francs not subject to revision, with options for three additional units of the power part of thyristor power converters, for an additional amount of 249 681 Swiss francs, subject to revision for inflation from 1 August 2006, bringing the total amount to 1 231 165 Swiss francs. The firm has indicated the following distribution by country of the contract value covered by this adjudication propos...

  8. 76 FR 46840 - Time Extension To Accept Proposals, Select One Lessee, and Contract for Hydroelectric Power...

    Science.gov (United States)

    2011-08-03

    ... Lessee, and Contract for Hydroelectric Power Development at the Pueblo Dam River Outlet, a Feature of the... Lessee, and Contract for Hydroelectric Power Development at the Pueblo Dam River Outlet, a feature of the... considered timely only if it is received in the office of the Lease of Power Privilege Coordinator by or...

  9. Environmental Assessment for Central Power and Light Company`s proposed Military Highway-CFE tie 138/69-kV transmission line project Brownsville, Cameron County, Texas

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-01

    Central Power and Light Company (CPL) intends to upgrade its existing transmission line ties with the Commision Federal de Electricidad (CFE) system in Mexico. CPL currently has a single 69-kilovolt (kV) transmission line in the Brownsville area which connects CPL`s system with the system of CFE. This existing line runs between the Brownsville Switching Station, located on Laredo Road in Brownsville, Cameron County, Texas, and an existing CFE 69-kV line at the Rusteberg Bend of the Rio Grande in Cameron County. Under current conditions of need, the existing 69-kV line does not possess sufficient capability to engage in appropriate power exchanges. Therefore, CPL is proposing to build a new line to link up with CFE. This proposed line would be a double-circuit line, which would (1) continue (on a slightly relocated route) the existing 69-kV tie from CPL`s Brownsville Switching Station to CFE`s facilities, and (2) add a 138-kV tie from the Military Highway Substation, located on Military Highway (US Highway 281), to CFE`s facilities. The proposed 138/69-kV line, which will be constructed and operated by CPL, will be built primarily on steel single-pole structures within an average 60-foot (ft) wide right-of-way (ROW). It will be approximately 6900--9200 ft (1.3--1.7 miles) in length, depending on the alternative route constructed.

  10. Upgrade of the LLNL Nova laser for inertial confinement fusion

    International Nuclear Information System (INIS)

    Murray, J.R.; Trenholme, J.B.; Hunt, J.T.; Frank, D.N.; Lowdermilk, W.H.; Storm, E.

    1991-01-01

    The Lawrence Livermore National Laboratory has proposed to construct an upgrade to the Nova glass laser facility to give an output energy of 1.5-2 megajoules at 350 nanometers wavelength in a nominally 3--5 nanosecond shaped pulse. The Nova Upgrade will be suitable for driving inertial fusion targets to ignition. This paper reviews the design proposed for the laser. 14 refs., 10 figs., 1 tab

  11. A new proposed approach for future large-scale de-carbonization coal-fired power plants

    International Nuclear Information System (INIS)

    Xu, Gang; Liang, Feifei; Wu, Ying; Yang, Yongping; Zhang, Kai; Liu, Wenyi

    2015-01-01

    The post-combustion CO 2 capture technology provides a feasible and promising method for large-scale CO 2 capture in coal-fired power plants. However, the large-scale CO 2 capture in conventionally designed coal-fired power plants is confronted with various problems, such as the selection of the steam extraction point and steam parameter mismatch. To resolve these problems, an improved design idea for the future coal-fired power plant with large-scale de-carbonization is proposed. A main characteristic of the proposed design is the adoption of a back-pressure steam turbine, which extracts the suitable steam for CO 2 capture and ensures the stability of the integrated system. A new let-down steam turbine generator is introduced to retrieve the surplus energy from the exhaust steam of the back-pressure steam turbine when CO 2 capture is cut off. Results show that the net plant efficiency of the improved design is 2.56% points higher than that of the conventional one when CO 2 capture ratio reaches 80%. Meanwhile, the net plant efficiency of the improved design maintains the same level to that of the conventional design when CO 2 capture is cut off. Finally, the match between the extracted steam and the heat demand of the reboiler is significantly increased, which solves the steam parameter mismatch problem. The techno-economic analysis indicates that the proposed design is a cost-effective approach for the large-scale CO 2 capture in coal-fired power plants. - Highlights: • Problems caused by CO 2 capture in the power plant are deeply analyzed. • An improved design idea for coal-fired power plants with CO 2 capture is proposed. • Thermodynamic, exergy and techno-economic analyses are quantitatively conducted. • Energy-saving effects are found in the proposed coal-fired power plant design idea

  12. Free Switzerland from fossil energy sources - Clear proposals for the building, transportation and electrical power sectors

    International Nuclear Information System (INIS)

    Nordmann, R.

    2010-10-01

    A comprehensive review of the current situation of energy resources and consumption and of the prevailing framework like climate change is given, with a focus on Switzerland. The author, a member of the Lower House of the Swiss Parliament, presents facts and figures in a simple language, illustrated by tables and diagrams, in a well structured, easy-to-read book, with detailed indications of his data sources. Starting from the limited character of fossil energy sources, 'peak-oil' and the necessary reduction of greenhouse gas emissions, the author states that nuclear energy is not the solution. Action is absolutely needed, but which policy should be adopted? A global strategy is required that includes the stabilization of the world population as a key factor. An international agreement signed by as many states as possible should create stringent commitments. The developed countries have to demonstrate that prosperity and high life standard are compatible with an economy based on renewable energy sources. This will give to the most ambitious countries a significant advantage on new markets created by renewable energy use and energy efficiency. The author goes on by describing the current status of the technologies needed. What regards the particular case of Switzerland, this country is strongly dependent on energy import - mainly fossil - and CO 2 emissions arise mainly from the building and transportation sectors. A 50% efficiency improvement until 2030 is needed in fossil energy use. Electricity use has to become more efficient as well. Electricity generation - today about 60% renewable - shall move towards 100% renewable. The next chapters discuss clear realistic proposals on how to achieve these goals in the transportation sector ('Intelligent mobility'), the building sector ('Retrofitting the buildings to get them up-to-date') and the electrical power sector ('Entirely renewable electricity'). The title of the conclusion chapter: 'Focus again on the general

  13. ATR Technical Specification Upgrade Program

    International Nuclear Information System (INIS)

    McCracken, R.T.; Durney, J.L.; Freund, G.A.

    1990-01-01

    The Advanced Test Reactor (ATR) is a 250 MW, uranium-aluminum fueled test reactor which began full power operation in 1969. The initial operation was controlled by an Operating Limits document based on the original Safety Analysis Report. Additional safety bases were later developed to support Technical Specifications which were approved and implemented in 1977. The Technical Specifications which were initially developed with content and format specified in ANSI/ANS--15.1, ''The Development of Technical Specifications for Research Reactors.'' The safety basis documentation and the Technical Specifications have been updated as required to maintain them current with the ATR facility configuration. All revisions have been made with a content, format and style consistent with the original. A major, two-phase program to upgrade the content, format and style is in progress. This paper describes the first phase of this program

  14. A proposed national wind power R and D program. [offshore wind power system for electric energy supplies

    Science.gov (United States)

    Heronemus, W.

    1973-01-01

    An offshore wind power system is described that consists of wind driven electrical dc generators mounted on floating towers in offshore waters. The output from the generators supplies underwater electrolyzer stations in which water is converted into hydrogen and oxygen. The hydrogen is piped to shore for conversion to electricity in fuel cell stations. It is estimated that this system can produce 159 x 10 to the ninth power kilowatt-hours per year. It is concluded that solar energy - and that includes wind energy - is the only way out of the US energy dilemma in the not too distant future.

  15. CORE DESIGNS OF ABWR FOR PROPOSED OF THE FIRST NUCLEAR POWER PLANT IN INDONESIA

    Directory of Open Access Journals (Sweden)

    Yohannes Sardjono

    2015-04-01

    Full Text Available Indonesia as an archipelago has been experiencing high growth industry and energy demand due to high population growth, dynamic economic activities. The total population is around 230 million people and 75 % to the total population is living in Java. The introduction of Nuclear Power Plant on Java Bali electricity grid will be possible in 2022 for 2 GWe, using proven technology reactor like ABWR or others light water reactor with nominal power 1000 MWe. In this case, the rated thermal power for the equilibrium cycles is 3926 MWt, the cycle length is 18 month and overall capacity factor is 87 %. The designs were performed for an 872-fuel bundles ABWR core using GE-11 fuel type in an 9×9 fuel rod arrays with 2 Large Central Water Rods (LCWR. The calculations were divided into two steps; the first is to generate bundle library and the other is to make the thermal and reactivity limits satisfied for the core designs. Toshiba General Electric Bundle lattice Analysis (TGBLA and PANACEA computer codes were used as designs tools. TGBLA is a General Electric proprietary computer code which is used to generate bundle lattice library for fuel designs. PANACEA is General Electric proprietary computer code which is used as thermal hydraulic and neutronic coupled BWR core simulator. This result of core designs describes reactivity and thermal margins i.e.; Maximum Linear Heat Generation rate (MLHGR is lower than 14.4 kW/ft, Minimum Critical Power Ratio (MCPR is upper than 1.25, Hot Excess Reactivity (HOTXS is upper than 1 %Dk at BOC and 0.8 %Dk at 200 MWD/ST and Cold Shutdown Margin Reactivity (CSDM is upper than 1 %Dk. It is concluded that the equilibrium core design using GE-11 fuel bundle type satisfies the core design objectives for the proposed of the firs Indonesia ABWR Nuclear Power Plant. Keywords: The first NPP in Indonesia, ABWR-1000 MWe, and core designs.   Indonesia adalah sebagai negara kepulauan yang laju pertumbuhan industri, energi, penduduk

  16. CMS pixel upgrade project

    CERN Document Server

    Kaestli, Hans-Christian

    2010-01-01

    The LHC machine at CERN finished its first year of pp collisions at a center of mass energy of 7~TeV. While the commissioning to exploit its full potential is still ongoing, there are plans to upgrade its components to reach instantaneous luminosities beyond the initial design value after 2016. A corresponding upgrade of the innermost part of the CMS detector, the pixel detector, is needed. A full replacement of the pixel detector is planned in 2016. It will not only address limitations of the present system at higher data rates, but will aggressively lower the amount of material inside the fiducial tracking volume which will lead to better tracking and b-tagging performance. This article gives an overview of the project and illuminates the motivations and expected improvements in the detector performance.

  17. CMS pixel upgrade project

    CERN Document Server

    INSPIRE-00575876

    2011-01-01

    The LHC machine at CERN finished its first year of pp collisions at a center of mass energy of 7 TeV. While the commissioning to exploit its full potential is still ongoing, there are plans to upgrade its components to reach instantaneous luminosities beyond the initial design value after 2016. A corresponding upgrade of the innermost part of the CMS detector, the pixel detector, is needed. A full replacement of the pixel detector is planned in 2016. It will not only address limitations of the present system at higher data rates, but will aggressively lower the amount of material inside the fiducial tracking volume which will lead to better tracking and b-tagging performance. This article gives an overview of the project and illuminates the motivations and expected improvements in the detector performance.

  18. Performance of the first ASDEX Upgrade neutral beam injector

    International Nuclear Information System (INIS)

    Staebler, A.; Vollmer, O.; Feist, J.H.; Speth, E.; Heinemann, B.; Melkus, W.; Obermayer, S.; Riedl, R.; Schaerich, W.; Wittenbecher, K.

    1995-01-01

    Plasmas of the ASDEX Upgrade tokamak have been heated with H 0 beams of up to 7 MW and D 0 beams of up to 10 MW. Beam modulation allows to inject at any power level between zero and full power. Measurements characterizing the NBI system performance, the power accountability, and the operational experience obtained so far are discussed. (orig.)

  19. Design works organization during the IandC system upgrading on an operating VVER power plant from the general designer's standpoint

    International Nuclear Information System (INIS)

    Krepel, V.

    1997-01-01

    Two replacements of nuclear power plant instrumentation and control systems have already been implemented according to the project design of Energoprojekt: at the Mochovce WWER-440 and the Temelin WWER-1000 plants. In the present contribution the design problems encountered during the replacement are described, the causes of the problems are discussed, and a policy of organizing project design work for an instrumentation and control system replacement at an operating WWER power plant is established such as would avoid these problems. (A.K.)

  20. The CDF upgrade

    International Nuclear Information System (INIS)

    Newman-Holmes, C.

    1995-01-01

    The Collider Detector at Fermilab (CDF) has been used to study proton-antiproton collisions at the Fermilab Tevatron since 1985. Over the years, the detector has evolved steadily to increase its physics capability and to keep pace with improvements to the Tevatron. Fermilab is currently building a new Main Injector accelerator which will lead to even larger luminosity values. This paper describes upgrades to CDF that will allow one to exploit the higher luminosity of the Main Injector

  1. LHCb VELO upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Hennessy, Karol

    2017-02-11

    The upgrade of the LHCb experiment, scheduled for LHC Run-III, scheduled to start in 2021, will transform the experiment to a trigger-less system reading out the full detector at 40 MHz event rate. All data reduction algorithms will be executed in a high-level software farm enabling the detector to run at luminosities of 2×10{sup 33} cm{sup −2} s{sup −1}. The Vertex Locator (VELO) is the silicon vertex detector surrounding the interaction region. The current detector will be replaced with a hybrid pixel system equipped with electronics capable of reading out at 40 MHz. The upgraded VELO will provide fast pattern recognition and track reconstruction to the software trigger. The silicon pixel sensors have 55×55 μm{sup 2} pitch, and are read out by the VeloPix ASIC, from the Timepix/Medipix family. The hottest region will have pixel hit rates of 900 Mhits/s yielding a total data rate of more than 3 Tbit/s for the upgraded VELO. The detector modules are located in a separate vacuum, separated from the beam vacuum by a thin custom made foil. The foil will be manufactured through milling and possibly thinned further by chemical etching. The material budget will be minimised by the use of evaporative CO{sub 2} coolant circulating in microchannels within 400 μm thick silicon substrates. The current status of the VELO upgrade is described and latest results from operation of irradiated sensor assemblies are presented.

  2. To Control the Abuses of Government: The Veto and the Separation of Powers. A Guide for Discussion of Proposals to Institute Item and Legislative Veto Powers.

    Science.gov (United States)

    O'Connor, Alice; Henze, Mary L.

    A discussion guide, one of a series on constitutional reform issues by The Jefferson Foundation as part of The Jefferson Meeting on the Constitution project, examines proposals to institute item and legislative veto power. The first section discusses the historical background surrounding the formative debate on veto legislation. The separation of…

  3. The LHCb VELO upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Dosil Suárez, Álvaro, E-mail: alvaro.dosil@usc.es

    2016-07-11

    The upgrade of the LHCb experiment, planned for 2019, will transform the experiment to a trigger-less system reading out the full detector at 40 MHz event rate. All data reduction algorithms will be executed in a high-level software farm. The upgraded detector will run at luminosities of 2×10{sup 33} cm{sup −2} s{sup −1} and probe physics beyond the Standard Model in the heavy flavour sector with unprecedented precision. The Vertex Locator (VELO) is the silicon vertex detector surrounding the interaction region. The current detector will be replaced with a hybrid pixel system equipped with electronics capable of reading out at 40 MHz. The detector comprises silicon pixel sensors with 55×55 μm{sup 2} pitch, read out by the VeloPix ASIC, based on the TimePix/MediPix family. The hottest region will have pixel hit rates of 900 Mhits/s yielding a total data rate more than 3 Tbit/s for the upgraded VELO. The detector modules are located in a separate vacuum, separated from the beam vacuum by a thin custom made foil. The detector halves are retracted when the beams are injected and closed at stable beams, positioning the first sensitive pixel at 5.1 mm from the beams. The material budget will be minimised by the use of evaporative CO{sub 2} coolant circulating in microchannels within 400 μm thick silicon substrates.

  4. ATLAS Upgrade Plans

    CERN Document Server

    Hopkins, W; The ATLAS collaboration

    2014-01-01

    After the successful LHC operation at the center-of-mass energies of 7 and 8 TeV in 2010-2012, plans are actively advancing for a series of upgrades of the accelerator, culminating roughly ten years from now in the high-luminosity LHC (HL-LHC) project, delivering of the order of five times the LHC nominal instantaneous luminosity along with luminosity leveling. The final goal is to extend the dataset from about few hundred fb−1 expected for LHC running to 3000/fb by around 2035 for ATLAS and CMS. In parallel, the experiments need to be keep lockstep with the accelerator to accommodate running beyond the nominal luminosity this decade. Current planning in ATLAS envisions significant upgrades to the detector during the consolidation of the LHC to reach full LHC energy and further upgrades. The challenge of coping with the HL-LHC instantaneous and integrated luminosity, along with the associated radiation levels, requires further major changes to the ATLAS detector. The designs are developing rapidly for a new...

  5. The LHCb VELO upgrade

    International Nuclear Information System (INIS)

    Rodríguez Pérez, Pablo

    2013-01-01

    LHCb is a forward spectrometer experiment dedicated to the study of new physics in the decays of beauty and charm hadrons produced in proton collisions at the Large Hadron Collider (LHC) at CERN. The VErtex LOcator (VELO) is the microstrip silicon detector surrounding the interaction point, providing tracking and vertexing measurements. The upgrade of the LHCb experiment, planned for 2018, will increase the luminosity up to 2×10 33 cm −2 s −1 and will perform the readout as a trigger-less system with an event rate of 40 MHz. Extremely non-uniform radiation doses will reach up to 5×10 15 1 MeV n eq /cm 2 in the innermost regions of the VELO sensors, and the output data bandwidth will be increased by a factor of 40. An upgraded detector is under development based in a pixel sensor of the Timepix/Medipix family, with 55×55μm 2 pixels. In addition a microstrip solution with finer pitch, higher granularity and thinner than the current detector is being developed in parallel. The current status of the VELO upgrade program will be described together with recent testbeam results

  6. The LHCb VELO Upgrade

    CERN Document Server

    de Capua, Stefano

    2016-01-01

    The upgrade of the LHCb experiment, scheduled for LHC Run-3, will transform the experiment to a triggerless system reading out the full detector at 40 MHz event rate. All data reduction algorithms will be executed in a high-level software farm, enabling the detector to run at luminosities of 2×1033 cm−2 s −1 . The Vertex Locator (VELO) is the silicon vertex detector surrounding the interaction region. The current strip detector will be replaced with a hybrid pixel system equipped with electronics capable of reading out at 40 MHz. The upgraded VELO will allow for fast pattern recognition and track reconstruction in the software trigger. The silicon pixel sensors have 55×55 µm2 pitch, and are read out by the VeloPix ASIC. The VeloPix builds on the currently available Timepix3, modified to deliver a radiation hard design capable of an order of magnitude increase in output rate. The hottest regions will have pixel hit rates of 900 Mhits/s, yielding a total data rate more than 3 Tbit/s for the upgraded VELO...

  7. LHCb VELO Upgrade

    CERN Document Server

    Hennessy, Karol

    2016-01-01

    The upgrade of the LHCb experiment, scheduled for LHC Run-III, scheduled to start in 2021, will transform the experiment to a trigger-less system reading out the full detector at 40 MHz event rate. All data reduction algorithms will be executed in a high-level software farm enabling the detector to run at luminosities of $2\\times10^{33} \\mathrm{cm}^{-2}\\mathrm{s}^{-1}$. The Vertex Locator (VELO) is the silicon vertex detector surrounding the interaction region. The current detector will be replaced with a hybrid pixel system equipped with electronics capable of reading out at 40 MHz. The upgraded VELO will provide fast pattern recognition and track reconstruction to the software trigger. The silicon pixel sensors have $55\\times55 \\mu m^{2}$ pitch, and are read out by the VeloPix ASIC, from the Timepix/Medipix family. The hottest region will have pixel hit rates of 900 Mhits/s yielding a total data rate of more than 3 Tbit/s for the upgraded VELO. The detector modules are located in a separate vacuum, separate...

  8. Nuclear Power and Resource Efficiency—A Proposal for a Revised Primary Energy Factor

    Directory of Open Access Journals (Sweden)

    Ola Eriksson

    2017-06-01

    Full Text Available Measuring resource efficiency can be achieved using different methods, of which primary energy demand is commonly used. The primary energy factor (PEF is a figure describing how much energy from primary resources is being used per unit of energy delivered. The PEF for nuclear power is typically 3, which refers to thermal energy released from fission in relation to electricity generated. Fuel losses are not accounted for. However; nuclear waste represents an energy loss, as current plans for nuclear waste management mostly include final disposal. Based on a literature review and mathematical calculations of the power-to-fuel ratio for nuclear power, PEF values for the open nuclear fuel cycle (NFC option of nuclear power and different power mixes are calculated. These calculations indicate that a more correct PEF for nuclear power would be 60 (range 32–88; for electricity in Sweden (41% nuclear power PEF would change from 1.8 to 25.5, and the average PEF for electricity in the European Union (EU would change from 2.5 to 18. The results illustrate the poor resource efficiency of nuclear power, which paves the way for the fourth generation of nuclear power and illustrates the policy implication of using PEFs which are inconsistent with current waste management plans.

  9. Recent ECRH results in ASDEX upgrade

    International Nuclear Information System (INIS)

    Leuterer, F.; Dux, R.; Gantenbein, G.

    2003-01-01

    This paper provides an overview on recent experimental results obtained in ASDEX Upgrade using electron cyclotron heating and current drive. The following topics are covered: determination of the power deposition profile, modulated power deposition, studies of the electron heat transport via power balance and heat wave analysis and a comparison with turbulent transport theory, generation of an internal transport barrier for the electron heat flux, impact of electron cyclotron resonance heating (ECRH) on particle and impurity transport, and studies related to neoclassical tearing modes and to sawteeth. (author)

  10. Demographic survey around proposed nuclear power plant site in Haryana covering 30 km radius area from the site

    International Nuclear Information System (INIS)

    Garg, V.K.

    2013-01-01

    This study was planned to have a demographic survey of the households living within 30 km radius of the proposed site. Objectives of the present study were to attain the quantitative baseline demographic data around (within 30 km radius) the proposed site of nuclear power plant, zone-wise and sector-wise distribution of the population around proposed site up to a distance of 30 km from the site, to obtain the data on socio-economic, cultural, and religious perspectives of the target populations, to obtain the data on disease/illness pattern in the target population, health status and mortality rate

  11. 77 FR 17099 - Proposed Extension of Existing Information Collection; Diesel-Powered Equipment for Underground...

    Science.gov (United States)

    2012-03-23

    ... to underground coal miners who work in mines that use diesel-powered equipment. Diesel equipment can... provide important safety protections to underground coal miners who work in mines that use diesel-powered... maintenance of fire suppression systems on the equipment and at fueling stations; exhaust gas sampling...

  12. Proposed new regulations for the limitation of releases of radioactive substances from nuclear power stations with light water reactors

    International Nuclear Information System (INIS)

    1975-07-01

    In this publication the Swedish National Institute of Radiation Protection presents a proposed version of new regulations concerning the way in which the release of radioactive substances from nuclear power stations is to be limited. The regulations come into force on 1st January 1976. (Auth.)

  13. 78 FR 8493 - Foreign-Trade Zone 45-Portland, OR; Notification of Proposed Production Activity; SoloPower Inc...

    Science.gov (United States)

    2013-02-06

    ...; Notification of Proposed Production Activity; SoloPower Inc. (Thin Film Photovoltaic Solar Panels); Portland... of FTZ 45. The facility is used for the production of thin film photovoltaic solar panels. Pursuant... procedures that applies to the thin film solar panels (duty-free) for the foreign status inputs noted below...

  14. Kongiganak Wind Turbine Replacement and System Upgrade Project

    Energy Technology Data Exchange (ETDEWEB)

    Boonstra, Patrick [Intelligent Energy Systems, Anchorage, AK (United States)

    2016-12-13

    The Native Village of Kongiganak, Alaska was awarded a grant to upgrade the braking systems on five wind turbines and upgrade the monitoring and data collection unit to insure that enough energy is available to power the utility. The project manager for this award is Intelligent Energy Systems, LLC located in Anchorage, Alaska. In addition to accomplishing these upgrades, it was the intent for a local wind tech crew to be trained in Kongiganak so that routine maintenance and future repairs will be made by local workers.

  15. CORRECTION SYSTEMS UPGRADE FOR THE SNS RING

    International Nuclear Information System (INIS)

    PAPAPHILIPPOU, Y.; GARDNER, C.J.; LEE, Y.Y.; WEI, J.

    2001-01-01

    In view of the changes in the design of the SNS ring from the original FODO lattice [l] to the 220m hybrid lattice [2] and finally 1.3GeV compatible 248m ring [3], complementary studies have been undertaken, in order to upgrade its correction packages. We review the evolution of the correction systems and present the accelerator physics studies for the adopted schemes and powering plan

  16. Upgrade of the CMS Global Muon Trigger

    CERN Document Server

    Lingemann, Joschka; Sakulin, Hannes; Jeitler, Manfred; Stahl, Achim

    2015-01-01

    The increase in center-of-mass energy and luminosity for Run 2 of the Large Hadron Collider pose new challenges for the trigger systems of the experiments. To keep triggering with a similar performance as in Run 1, the CMS muon trigger is currently being upgraded. The new algorithms will provide higher resolution, especially for the muon transverse momentum and will make use of isolation criteria that combine calorimeter with muon information already in the level-1 trigger. The demands of the new algorithms can only be met by upgrading the level-1 trigger system to new powerful FPGAs with high bandwidth I/O. The processing boards will be based on the new microTCA standard. We report on the planned algorithms for the upgraded Global Muon Trigger (GMT) which combines information from the muon trigger sub-systems and assigns the isolation variable. The upgraded GMT will be implemented using a Master Processor 7 card, built by Imperial College, that features a large Xilinx Virtex 7 FPGA. Up to 72 optical links at...

  17. Upgrading nuclear regulatory infrastructure in Armenia

    International Nuclear Information System (INIS)

    Martirosyan, A.; Amirjanyan, A.; Kacenelenbogen, S.

    2010-01-01

    Armenia is contemplating an upgrade to its national power generation capacity to meet replacement and future energy needs. Unit 2 of ANPP is scheduled for shutdown after replacement power generation capacities are in place. A recent alternative energy study indicates viability of the nuclear option to replace this capacity. Some technology-specific proposals are being considered by the Ministry of Energy of Armenia. It is likely that the reactor technology decision will be made in the not too distant future. The existing reactor continues to be operated in the regulatory framework developed in the Soviet Union and adopted in Armenia. Given the interest in the new reactor, Armenia launched a project to review the existing system of regulation and to bring it into harmony with modern practice in preparation for the new reactor project development. The new regulatory framework will be needed as a basis for any potential tendering process. The US NRC and ANRA have agreed to perform a review and update nuclear legislation and the system of regulation in this area. The first step in this process was to develop an action plan for such program. The action plan describes the overall strategy of ANRA to modify existing or develop new processes and requirements, identifies the major Laws that need to be reviewed given practical legal considerations to construct and operate the reactor and Armenia's international obligations under various conventions. This work included review of existing models of regulation in different countries with 'small' nuclear program, including IAEA recommendations as well as existing legislation in Armenia in this area and development of a strategy for the regulatory model development. In addition, the plan to develop requirements for ANRA staffing and training needs to meet its regulatory obligations under the new reactor development process was developed

  18. A new strips tracker for the upgraded ATLAS ITk detector

    CERN Document Server

    David, Claire; The ATLAS collaboration

    2017-01-01

    The inner detector of the present ATLAS detector has been designed and developed to function in the environment of the present Large Hadron Collider (LHC). At the next-generation tracking detector proposed for the High Luminosity LHC (HL-LHC), the so-called ATLAS Phase-II Upgrade, the particle densities and radiation levels will be higher by as much as a factor of ten. The new detectors must be faster, they need to be more highly segmented, and covering more area. They also need to be more resistant to radiation, and they require much greater power delivery to the front-end systems. At the same time, they cannot introduce excess material which could undermine performance. For those reasons, the inner tracker of the ATLAS detector must be redesigned and rebuilt completely. The design of the ATLAS Upgrade inner tracker (ITk) has already been defined. It consists of several layers of silicon particle detectors. The innermost layers will be composed of silicon pixel sensors, and the outer layers will consist of s...

  19. The Phase II Upgrade of the ATLAS Calorimeter

    CERN Document Server

    Tartarelli, Giuseppe Francesco; The ATLAS collaboration

    2017-01-01

    This presentation will show the status of the upgrade projects of the ATLAS calorimeter system for the high luminosity phase of the LHC (HL-LHC). For the HL-LHC, the instantaneous luminosity is expected to increase up to L ≃ 7.5 × 1034 cm−2 s−1 and the average pile-up up to 200 interactions per bunch crossing. The Liquid Argon (LAr) calorimeter electronics will need to be replaced to cope with these challenging conditions: the expected radiation doses will indeed exceed the qualification range of the current readout system, and the upgraded trigger system will require much longer data storage in the electronics (up to 60 us), that the current system cannot sustain. The status of the R&D of the low-power ASICs (pre-amplifier, shaper, ADC, serializer and transmitters) and of the readout electronics design will be discussed. Moreover, a High Granularity Timing Detector (HGTD) is proposed to be added in front of the LAr calorimeters in the end-cap region (2.4 <|eta|< 4.2) for pile-up mitigation a...

  20. Ontario Power Generation's proposed L and ILW deep geologic repository: geo-scientific assessment

    International Nuclear Information System (INIS)

    Jensen, Mark; Raven, Ken; Leech, Robert

    2012-01-01

    Document available in extended abstract form only. The Nuclear Waste Management Organization (NWMO) on behalf of Ontario Power Generation (OPG) has conducted multi-disciplinary geo-scientific studies at the Bruce nuclear site to confirm the suitability of the site to host a proposed Deep Geologic Repository (DGR) for the long-term management of Low and Intermediate Level Radioactive Waste (L and ILW) from OPG owned or operated nuclear generating facilities. An Environmental Assessment for the proposed DGR is currently underway in accordance with the Canadian Environmental Assessment Act. Bruce nuclear site, situated 225 km northwest of Toronto on the eastern shore of Lake Huron, is underlain by an 850 m thick sedimentary sequence of Cambrian to Devonian age near-horizontally layered, weakly deformed shales, carbonates and evaporites of the Michigan Basin. Within this sedimentary pile, the proposed DGR would be excavated within the low permeability argillaceous limestone of the Cobourg Formation at a depth of 680 m, which is overlain by 200 m of Upper Ordovician shale formations (Figure 1). A key aspect of the DGR Safety Case is the predictable nature and long-term stability and integrity of the sedimentary sequence to contain and isolate L and ILW at time frames on the order of 1 Ma. Early in the project, geo-scientific studies that considered regional and site-specific public domain data sets indicated favourable geologic conditions for implementation of the DGR concept (Golder, 2003; Mazurek, 2004). Geo-scientific studies for the DGR were initiated in 2006 following decision by the Municipality of Kincardine to support the DGR concept. Geo-scientific activities were divided into two key areas; i) Site-specific geo-scientific studies of the Bruce nuclear site (i.e., Descriptive Geosphere Site Model); and ii) a Geo-synthesis to convey an understanding of past, present and future evolution of Geosphere enclosing the DGR relevant to communicating notions of

  1. Proposed principles on the use of nuclear power sources in space

    International Nuclear Information System (INIS)

    Bennett, G.L.

    1988-01-01

    Since the 1978 reentry of the Soviet satellite Cosmos 954, the United Nations has been discussing the use of nuclear power sources in outer space. Most of these deliberations have taken place in the U.N. Committee on the Peaceful Uses of Outer Space, its two subcommittees (Scientific and Technical Subcommittee and Legal Subcommittee) and their associated working groups. This paper focuses on the technical agreements reached by the Working Group on the Use of Nuclear Power Sources in Outer Space (WGNPS), the legal principles agreed to by the Legal Subcommittee, and relevant treaties on the use of outer space and the use of nuclear power. To date the conclusion reached by the WGNPS in its 1981 report represents a succinct statement of U.N. consensus and of the U.S. position: The Working Group reaffirmed its previous conclusion that nuclear power sources can be used safely in outer space, provided that all necessary safety precautions are met

  2. A high frequency, high power CARM proposal for the DEMO ECRH system

    International Nuclear Information System (INIS)

    Mirizzi, Francesco; Spassovsky, Ivan; Ceccuzzi, Silvio; Dattoli, Giuseppe; Di Palma, Emanuele; Doria, Andrea; Gallerano, Gianpiero; Lampasi, Alessandro; Maffia, Giuseppe; Ravera, GianLuca; Sabia, Elio; Tuccillo, Angelo Antonio; Zito, Pietro

    2015-01-01

    Highlights: • ECRH system for DEMO. • Cyclotron Auto-Resonance Maser (CARM) devices. • Relativistic electron beams. • Bragg reflectors. • High voltage pulse modulators. - Abstract: ECRH&CD systems are extensively used on tokamak plasmas due to their capability of highly tailored power deposition, allowing very localised heating and non-inductive current drive, useful for MHD and profiles control. The high electron temperatures expected in DEMO will require ECRH systems with operating frequency in the 200–300 GHz range, equipped with a reasonable number of high power (P ≥ 1 MW) CW RF sources, for allowing central RF power deposition. In this frame the ENEA Fusion Department (Frascati) is coordinating a task force aimed at the study and realisation of a suitable high power, high frequency reliable source.

  3. A high frequency, high power CARM proposal for the DEMO ECRH system

    Energy Technology Data Exchange (ETDEWEB)

    Mirizzi, Francesco, E-mail: francesco.mirizzi@enea.it [Consorzio CREATE, Via Claudio 21, I-80125 Napoli (Italy); Spassovsky, Ivan [Unità Tecnica Applicazioni delle Radiazioni – ENEA, C.R. Frascati, via E. Fermi 45, I-00044 Frascati (Italy); Ceccuzzi, Silvio [Unità Tecnica Fusione – ENEA C. R. Frascati, via E. Fermi 45, 00044 Frascati, Roma (Italy); Dattoli, Giuseppe; Di Palma, Emanuele; Doria, Andrea; Gallerano, Gianpiero [Unità Tecnica Applicazioni delle Radiazioni – ENEA, C.R. Frascati, via E. Fermi 45, I-00044 Frascati (Italy); Lampasi, Alessandro; Maffia, Giuseppe; Ravera, GianLuca [Unità Tecnica Fusione – ENEA C. R. Frascati, via E. Fermi 45, 00044 Frascati, Roma (Italy); Sabia, Elio [Unità Tecnica Applicazioni delle Radiazioni – ENEA, C.R. Frascati, via E. Fermi 45, I-00044 Frascati (Italy); Tuccillo, Angelo Antonio; Zito, Pietro [Unità Tecnica Fusione – ENEA C. R. Frascati, via E. Fermi 45, 00044 Frascati, Roma (Italy)

    2015-10-15

    Highlights: • ECRH system for DEMO. • Cyclotron Auto-Resonance Maser (CARM) devices. • Relativistic electron beams. • Bragg reflectors. • High voltage pulse modulators. - Abstract: ECRH&CD systems are extensively used on tokamak plasmas due to their capability of highly tailored power deposition, allowing very localised heating and non-inductive current drive, useful for MHD and profiles control. The high electron temperatures expected in DEMO will require ECRH systems with operating frequency in the 200–300 GHz range, equipped with a reasonable number of high power (P ≥ 1 MW) CW RF sources, for allowing central RF power deposition. In this frame the ENEA Fusion Department (Frascati) is coordinating a task force aimed at the study and realisation of a suitable high power, high frequency reliable source.

  4. Equipment and performance upgrade of compact nuclear simulator

    International Nuclear Information System (INIS)

    Park, Jae Chang; Kwon, Kee Choon; Cha, Hyung Ho; Park, Won Man; Song, Soon Ja; Seh, Kyung Won; Joo, Young Chang

    1998-12-01

    In this project, the techniques to upgrade obsolescent nuclear power plant simulation were developed: the simulation code operated in Macro-VAX II has been transplanted to the HP workstation: commercial equipment PLC was adopted for the interface system: the protection logic was developed in the prototype level: and the display system was strengthened. These techniques can be directly used to upgrade other obsolescent simulators

  5. Equipment and performance upgrade of compact nuclear simulator

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jae Chang; Kwon, Kee Choon; Cha, Hyung Ho; Park, Won Man; Song, Soon Ja; Seh, Kyung Won; Joo, Young Chang

    1998-12-01

    In this project, the techniques to upgrade obsolescent nuclear power plant simulation were developed: the simulation code operated in Macro-VAX II has been transplanted to the HP workstation: commercial equipment PLC was adopted for the interface system: the protection logic was developed in the prototype level: and the display system was strengthened. These techniques can be directly used to upgrade other obsolescent simulators.

  6. Upgrading of TREAT experimental capabilities

    International Nuclear Information System (INIS)

    Dickerman, C.E.; Rose, D.; Bhattacharyya, S.K.

    1982-01-01

    The TREAT facility at the Argonne National Laboratory site in the Idaho National Engineering Laboratory is being upgraded to provide capabilities for fast-reactor-safety transient experiments not possible at any other experimental facility. Principal TREAT Upgrade (TU) goal is provision for 37-pin size experiments on energetics of core-disruptive accidents (CDA) in fast breeder reactor cores with moderate sodium void coefficients. this goal requires a significant enhancement of the capabilities of the TREAT facility, specifically including reactor control, hardened neutron spectrum incident on the test sample, and enlarged building. The upgraded facility will retain the capability for small-size experiments of the types currently being performed in TREAT. Reactor building and crane upgrading have been completed. TU schedules call for the components of the upgraded reactor system to be finished in 1984, including upgraded TREAT fuel and control system, and expanded coverage by the hodoscope fuel-motion diagnostics system

  7. Final Report: ATLAS Phase-2 Tracker Upgrade Layout Task Force

    CERN Document Server

    Clark, A; The ATLAS collaboration; Hessey, N; Mättig, P; Styles, N; Wells, P; Burdin, S; Cornelissen, T; Todorov, T; Vankov, P; Watson, I; Wenig, S

    2012-01-01

    he mandate of the Upgrade Layout Task Force was to develop a benchmark layout proposal for the ATLAS Phase-2 Upgrade Letter of Intent (LOI), due in late 2012. The work described in this note has evolved from simulation and design studies made using an earlier "UTOPIA" upgrade tracker layout, and experience gained from the current ATLAS Inner Detector during the first years of data taking. The layout described in this document, called the LoI-layout, will be used as a benchmark layout for the LoI and will be used for simulation and engineering studies described in the LoI.

  8. Tracking detectors for the sLHC, the LHC upgrade

    CERN Document Server

    Sadrozinski, Hartmut F W

    2005-01-01

    The plans for an upgrade of the Large Hadron Collider (LHC) to the Super-LHC (sLHC) are reviewed with special consideration of the environment for the inner tracking system. A straw-man detector upgrade for ATLAS is presented, which is motivated by the varying radiation levels as a function of radius, and choices for detector geometries and technologies are proposed, based on the environmental constraints. A few promising technologies for detectors are discussed, both for sensors and for the associated front-end electronics. On-going research in silicon detectors and in ASIC technologies will be crucial for the success of the upgrade.

  9. LHCb: A new Readout Control system for the LHCb Upgrade

    CERN Multimedia

    Alessio, F

    2012-01-01

    The LHCb experiment has proposed an upgrade towards a full 40 MHz readout system in order to run between five and ten times its initial design luminosity. The entire readout architecture will be upgraded in order to cope with higher sub-detector occupancies, higher rate and higher network load. In this paper, we describe the architecture, functionalities and the first hardware implementation of a new Readout Control system for the LHCb upgrade. The system is based on FPGAs and bi-directional links for the control of the entire readout architecture. First results on the validation of the system are also given.

  10. Virtual power plant feasibility study and funding proposal / the virtual power plant objectives, concept, components, context, business plan / objectives, activities and timelines for the VPP feasibility study

    International Nuclear Information System (INIS)

    MacDonald, A.

    2004-01-01

    This paper presents a proposal for funding a virtual power plant feasibility study. The goals of the virtual power plant are to increase the efficiency of electricity use by creating a market-driven, subsidy-free, financially sustainable mechanism to finance economic Demand Side Management (DSM) by providing a fully liquid market for saved electricity, provide a new revenue opportunity for the Local Distributing Company (LDC) and increase the use of renewable and low environmental impact, high efficiency technologies within the service area

  11. Application of superconducting coils to VAR control in electric power systems: a proposal

    International Nuclear Information System (INIS)

    Boenig, H.J.; Hassenzahl, W.V.

    1979-11-01

    During the last eight years, static VAR-control systems with thyristor-controlled, room-temperature reactors have been used in electrical systems for voltage control and system stabilization. In this proposal, we describe a new static VAR-control system that uses an asymmetrically controlled Graetz bridge and a superconducting dc coil. Preliminary studies indicate that the proposed system will have lower overall losses and that its capital cost and electrical characteristics are comparable to those of a conventional system. Three- and four-year programs for developing the electronic circuitry and superconducting coils for VAR control, culminating in the installation and testing of an approx. 40-MVAR system, are proposed

  12. Comparison of Different MPPT Algorithms with a Proposed One Using a Power Estimator for Grid Connected PV Systems

    Directory of Open Access Journals (Sweden)

    Manel Hlaili

    2016-01-01

    Full Text Available Photovoltaic (PV energy is one of the most important energy sources since it is clean and inexhaustible. It is important to operate PV energy conversion systems in the maximum power point (MPP to maximize the output energy of PV arrays. An MPPT control is necessary to extract maximum power from the PV arrays. In recent years, a large number of techniques have been proposed for tracking the maximum power point. This paper presents a comparison of different MPPT methods and proposes one which used a power estimator and also analyses their suitability for systems which experience a wide range of operating conditions. The classic analysed methods, the incremental conductance (IncCond, perturbation and observation (P&O, ripple correlation (RC algorithms, are suitable and practical. Simulation results of a single phase NPC grid connected PV system operating with the aforementioned methods are presented to confirm effectiveness of the scheme and algorithms. Simulation results verify the correct operation of the different MPPT and the proposed algorithm.

  13. Upgrade Software and Computing

    CERN Document Server

    The LHCb Collaboration, CERN

    2018-01-01

    This document reports the Research and Development activities that are carried out in the software and computing domains in view of the upgrade of the LHCb experiment. The implementation of a full software trigger implies major changes in the core software framework, in the event data model, and in the reconstruction algorithms. The increase of the data volumes for both real and simulated datasets requires a corresponding scaling of the distributed computing infrastructure. An implementation plan in both domains is presented, together with a risk assessment analysis.

  14. Upgrading Enterprise Search

    Energy Technology Data Exchange (ETDEWEB)

    McDunn, R

    2005-04-28

    This presentation will describe the process we went through this past year to upgrade our enterprise search tool from a very old version of Inktomi to the latest version of Verity Ultraseek. We started with requirements gathering and then compared requirements against several available products to determine which product to choose. After purchasing the product, we worked through several defined phases of implementation and customization, with initial rollout late January 2004. Finally, we will show you where we are today and describe future search plans.

  15. Upgrade, rebuild or replace?

    International Nuclear Information System (INIS)

    Forbes, C.A.

    1990-01-01

    Ageing reactor simulators present some tough decisions for utility managers. Although most utilities have chosen the cheaper, upgrading solution as the best compromise between costs and outage length, some US utilities have found that for them, replacement represents the best option. Simulators may be less than ten years old, but they have limited instructor systems, older low fidelity models that cannot reproduce important training scenarios, and out of date, difficult to maintain computers that do not permit much expansion of the models anyway. Perhaps worse than this is the possibility that the simulator may no longer be a faithful reproduction of the referenced plant, or have poor (or non-existent) documentation. (author)

  16. Upgrading and modernization of the high flux reactor Petten

    International Nuclear Information System (INIS)

    Ahlf, J.

    1992-01-01

    The High Flux Reactor (HFR) at Petten, The Netherlands, owned by the European Communities and operated by the Netherlands Energy Research Foundation, is a water-cooled and moderated, multipurpose research reactor of the closed-tank in-pool type, operated at 45 MW. Performance upgrading comprised two power increases from 20 MW via 30 MW to 45 MW, providing more and higher rated irradiation positions in the tank. With the replacement of the original reactor vessel the experimental capabilities of the reactor were improved. Better pool side facilities and the introduction of a large cross-section, double, beam tube were implemented. Additional major installation upgrading activities consisted of the replacement of the primary and the pool heat exchangers, replacement of the beryllium reflector elements, extension of the overpower protection systems and upgrading of the nuclear instrumentation as well as the guaranteed power supply. Control room upgrading is in progress. A full new safety analysis, as well as the introduction of a comprehensive Quality Assurance system, are summarized under software upgrading. Continuous modernization and upgrading also takes place of equipment for fuel and structural materials irradiations for fission reactors and future fusion machines. In parallel, all supporting services, as well as the management structure for large irradiation programmes, have been developed. Presently the reactor is operating at about 275 full power days per year with an average utilization of the irradiation positions of 70 to 80%. (orig.)

  17. Repairing and Upgrading Your PC

    CERN Document Server

    Thompson, Robert

    2009-01-01

    Repairing and Upgrading Your PC delivers start-to-finish instructions, simple enough for even the most inexperienced PC owner, for troubleshooting, repairing, and upgrading your computer. Written by hardware experts Robert Bruce Thompson and Barbara Fritchman Thompson, this book covers it all: how to troubleshoot a troublesome PC, how to identify which components make sense for an upgrade, and how to tear it all down and put it back together. This book shows how to repair and upgrade all of your PC's essential components.

  18. The role of fusion power in energy scenarios. Proposed method and review of existing scenarios

    International Nuclear Information System (INIS)

    Lako, P; Ybema, J.R.; Seebregts, A.J.

    1998-04-01

    The European Commission wishes more insight in the potential role of fusion energy in the second half of the 21st century. Therefore, several scenario studies are carried out in the so-called macro-task Long Term Scenarios to investigate the potential role of fusion power in the energy system. The main contribution of ECN to the macro-task is to perform a long term energy scenario study for Western Europe with special focus on the role of fusion power. This interim report gives some methodological considerations for such an analysis. A discussion is given on the problems related to the long time horizon of the scenario study such as the forecast of technological innovations, the selection of appropriate discount rates and the links with climate change. Key parameters which are expected to have large effects on the role and cost-effectiveness are discussed in general terms. The key parameters to be varied include level and structure of energy demand, availability and prices of fossil energy, CO2 reduction policy, discount rates, cost and potential of renewable energy sources, availability of fission power and CO2 capture and disposal and the cost and the maximum rate of market growth of fusion power. The scenario calculations are to be performed later in the project with the help of an existing cost minimisation model of the Western European energy system. This MARKAL model is briefly introduced. The results of the model calculations are expected to make clear under which combinations of scenario parameters fusion power is needed and how large the expected financial benefits will be. The present interim report also gives an evaluation of existing energy scenarios with respect to the role of fusion power. 18 refs

  19. The LHC Luminosity Upgrade and Related ATLAS Detector Plans

    CERN Document Server

    Hartjes, F; The ATLAS collaboration

    2009-01-01

    3rd draft of the proposed talk about Atlas Upgrade for MPGD2009 (Instrumentation conference on gaseous pixel detectors) on Friday June 12, 2009. I concentrated my presentation on the upgrade plans and schedule of the LHC and on detector technologies for the new Inner Tracker, putting less emphasis on other subdetectors. Compared to the 2nd draft I modified and clarified a few items about trigger, muon detection and calorimetry and did a number of cosmetic adaptions.

  20. Human-machine interface upgrade

    International Nuclear Information System (INIS)

    Kropik, M.; Matejka, K.; Sklenka, L.; Chab, V.

    2002-01-01

    The article describes a new human-machine interface that was installed at the VR-1 training reactor. The human-machine interface upgrade was completed in the summer 2001. The interface was designed with respect to functional, ergonomic and aesthetic requirements. The interface is based on a personal computer equipped with two displays. One display enables alphanumeric communication between the reactor operator and the nuclear reactor I and C. The second display is a graphical one. It presents the status of the reactor, principal parameters (as power, period), control rods positions, course of the reactor power. Furthermore, it is possible to set parameters, to show the active core configuration, to perform reactivity calculations, etc. The software for the new human-machine interface was produced with the InTouch developing tool of the Wonder-Ware Company. It is possible to switch the language of the interface between Czech and English because of many foreign students and visitors to the reactor. Microcomputer based communication units with proper software were developed to connect the new human-machine interface with the present reactor I and C. The new human-machine interface at the VR-1 training reactor improves the comfort and safety of the reactor utilisation, facilitates experiments and training, and provides better support for foreign visitors. (orig.)

  1. ATLAS Detector Upgrade Prospects

    CERN Document Server

    Dobre, Monica; The ATLAS collaboration

    2016-01-01

    After the successful operation at the center-of-mass energies of 7 and 8 TeV in 2010 - 2012, the LHC is ramped up and successfully took data at the center-of-mass energies of 13 TeV in 2015. Meanwhile, plans are actively advancing for a series of upgrades of the accelerator, culminating roughly ten years from now in the high-luminosity LHC (HL-LHC) project, delivering of the order of five times the LHC nominal instantaneous luminosity along with luminosity leveling. The ultimate goal is to extend the dataset from about few hundred fb−1 expected for LHC running to 3000 fb−1 by around 2035 for ATLAS and CMS. The challenge of coping with the HL-LHC instantaneous and integrated luminosity, along with the associated radiation levels, requires further major changes to the ATLAS detector. The designs are developing rapidly for a new all-silicon tracker, significant upgrades of the calorimeter and muon systems, as well as improved triggers and data acquisition. ATLAS is also examining potential benefits of extens...

  2. ATLAS detector upgrade prospects

    CERN Document Server

    AUTHOR|(INSPIRE)INSPIRE-00184940; The ATLAS collaboration

    2017-01-01

    After the successful operation at the centre-of-mass energies of 7 and 8 TeV in 2010-2012, the LHC is ramped up and successfully took data at the centre-of-mass energies of 13 TeV in 2015. Meanwhile, plans are actively advancing for a series of upgrades of the accelerator, culminating roughly ten years from now in the high-luminosity LHC (HL-LHC) project, delivering of the order of five times the LHC nominal instantaneous luminosity along with luminosity levelling. The ultimate goal is to extend the dataset from about few hundred fb$^{-1}$ expected for LHC running to 3000 fb $^{-1}$ by around 2035 for ATLAS and CMS. The challenge of coping with the HL-LHC instantaneous and integrated luminosity, along with the associated radiation levels, requires further major changes to the ATLAS detector. The designs are developing rapidly for a new all-silicon tracker, significant upgrades of the calorimeter and muon systems, as well as improved triggers and data acquisition. ATLAS is also examining potential benefits of ...

  3. ATLAS Detector Upgrade Prospects

    International Nuclear Information System (INIS)

    Dobre, M

    2017-01-01

    After the successful operation at the centre-of-mass energies of 7 and 8 TeV in 2010-2012, the LHC was ramped up and successfully took data at the centre-of-mass energies of 13 TeV in 2015 and 2016. Meanwhile, plans are actively advancing for a series of upgrades of the accelerator, culminating roughly ten years from now in the high-luminosity LHC (HL-LHC) project, which will deliver of the order of five times the LHC nominal instantaneous luminosity along with luminosity levelling. The ultimate goal is to extend the dataset from about few hundred fb −1 expected for LHC running by the end of 2018 to 3000 fb −1 by around 2035 for ATLAS and CMS. The challenge of coping with the HL-LHC instantaneous and integrated luminosity, along with the associated radiation levels, requires further major changes to the ATLAS detector. The designs are developing rapidly for a new all-silicon tracker, significant upgrades of the calorimeter and muon systems, as well as improved triggers and data acquisition. ATLAS is also examining potential benefits of extensions to larger pseudorapidity, particularly in tracking and muon systems. This report summarizes various improvements to the ATLAS detector required to cope with the anticipated evolution of the LHC luminosity during this decade and the next. A brief overview is also given on physics prospects with a pp centre-of-mass energy of 14 TeV. (paper)

  4. Case study: Proposed application of project management techniques for construction of nuclear power plant in Malaysia

    International Nuclear Information System (INIS)

    Syahirah Abdul Rahman; Phongsakorn Prak Tom; Wan Abd Hadi Wan Abu Bakar; Shaharum Ramli

    2010-01-01

    This study discusses the techniques of project management for the construction of nuclear power plants that can be used in Malaysia. Nuclear power reactors are expected to apply is the categories of Gen III + reactor where it is safer and more modern than the first generation of reactors built in the 1970s. The objective of this study is that the construction of this reactor to be completed by the stipulated time and not exceed the cost estimates. In addition, project management is also able to meet all the specifications and achieve the quality standard. In this study, the techniques used in project management to ensure the success of construction projects of nuclear power plants are a Gantt Chart, CPM/ PERT and Microsoft Project. From the study, found that these techniques can assist in facilitating the management of the project for the construction of nuclear power plants to ensure that the estimated time and cost can be managed more effectively as well as quality of care. (author)

  5. 78 FR 5773 - Notification of Proposed Production Activity, Generac Power Systems, Inc., Subzone 41J...

    Science.gov (United States)

    2013-01-28

    ... Activity, Generac Power Systems, Inc., Subzone 41J, (Generators, Pressure Washers, Engines and Other... Whitewater, Edgerton and Jefferson, Wisconsin. The facilities are used for the production of generators... the foreign status components used in export production (15% of annual shipments). On its domestic...

  6. 76 FR 58837 - Notice of Intent to Accept Proposals, Select Lessee, and Contract for Hydroelectric Power...

    Science.gov (United States)

    2011-09-22

    ... Grande Project; and the anticipated return on investment. If there are additional transmission or... with Reclamation and interested entities to discuss Western's potential marketing of hydropower. FOR.... Information related to Western's purchasing and/or marketing of the power may be obtained by contacting Ms...

  7. Project managing your simulator DCS upgrade

    International Nuclear Information System (INIS)

    Carr, S.

    2006-01-01

    The intention of this paper is to provide helpful information and tips for the purchaser with regard to the project management of a DCS upgrade for an existing nuclear power station operator-training simulator. This paper was written shortly after STS Powergen completed two nuclear power station simulator DCS projects in the USA. Areas covered by this paper are: - Contractual documents and arrangements; - Licence and Escrow agreements; - Liquidated damages; - Project management; - Project schedules and resources; - Monitoring progress; - Defect reporting; - DCS automation code; - Access to proprietary information; - Tips for project meetings; - Testing; - Cultural issues; - Training

  8. Safety upgrading program in NPP Mochovce

    International Nuclear Information System (INIS)

    Baumeister, P.

    1999-01-01

    EMO interest is to operate only nuclear power plants with high standards of nuclear safety. This aim EMO declare on preparation completion and commissioning of Mochovce Nuclear Power Plant. Wide co-operation of our company with International Atomic Energy Agency and west European Inst.ions and companies has been started with aim to fulfil the nuclear safety requirements for Mochovce NPP. Set of 87 safety measures was implemented at Mochovce Unit 1 and is under construction at Unit 2. Mochovce NPP approach to safety upgrading implementation is showed on chosen measures. This presentation is focused on the issues category III.(author)

  9. Draft environmental statement related to the proposed manufacture of floating nuclear power plants (Docket No. STN 50-437)

    International Nuclear Information System (INIS)

    1976-10-01

    The proposed action is the issuance of a manufacturing license to Offshore Power Systems for the startup and operation of a proposed manufacturing facility located at Blount Island, Jacksonville, Florida (Docket No. STN 50-436). No nuclear fuel will be handled or stored at the manufacturing site. The plants will be fueled after they have been towed to and moored within breadwaters at specific offshore locations designated by the purchaser and after an operating license has been issued by the Nuclear Regulatory Commision. Each nuclear generating plant, mounted on a floating platform, has a net capacity of 1150 MWe. This energy is provided by a pressurized water reactor steam supply system consisting of a Westinghouse four-loop 3425 MWt unit with an ice-condenser containment system. When one or more of these units is located within a single breakwater, the installation is designated an offshore power station. 3 figs., 1 tab

  10. NPP Krsko Severe Accident Management Guidelines Upgrade

    International Nuclear Information System (INIS)

    Mihalina, Mario; Spalj, Srdjan; Glaser, Bruno; Jalovec, Robi; Jankovic, Gordan

    2014-01-01

    Nuclear Power Plant Krsko (NEK) has decided to take steps for upgrade of safety measures to prevent severe accidents, and to improve the means to successfully mitigate their consequences. The content of the program for the NEK Safety Upgrade is consistent with the nuclear industry response to Fukushima accident, which revealed many new insights into severe accidents. Therefore, new strategies and usage of new systems and components should be integrated into current NEK Severe Accident Management Guidelines (SAMG's). SAMG's are developed to arrest the progression of a core damage accident and to limit the extent of resulting releases of fission products. NEK new SAMG's revision major changes are made due to: replacement of Electrical Recombiners by Passive Autocatalytic Recombiners (PARs) and the installation of Passive Containment Filtered Vent System (PCFV); to handle a fuel damage situation in Spent Fuel Pool (SFP) and to assess risk of core damage situation during shutdown operation. (authors)

  11. LS1: electrical engineering upgrades and consolidation

    International Nuclear Information System (INIS)

    Duval, F.

    2012-01-01

    3 different types of activities are planned by the Engineering Department Electrical Engineering (EN-EL) Group for the first long shut down (LS1). First, the consolidation of EN-EL's ageing infrastructure elements. It is part of a 15- year programme aiming at increasing the reliability and availability of the power distribution network. Secondly, the maintenance of the accelerators infrastructure. In addition to the usual periodic operations and those delayed until LS1, the group will address more demanding activities like the replacement campaigns for irradiated cables and non-radiation resistant fibres as well as the removal of unused cables in particularly overcrowded areas. Thirdly, a vast amount of user copper and optical fibre cabling requests: EN-EL estimates that only 50% of LS1 requests are currently known. The main activities will be EN-EL's contributions to the R2E project, BE-BI upgrade projects, and the RF upgrade project in SPS BA3

  12. Cryomodule development for the CEBAF upgrade

    International Nuclear Information System (INIS)

    J. R. Delayen; L. R. Doolittle; E. Feldl; J. Hogan; J. Mammosser; V. Nguyen; H. L. Phillips; J. Preble; W. J. Scheider; D. X. Wang; M. Wiseman

    1999-01-01

    Long term plans for CEBAF at Jefferson Lab call for achieving 12 GeV in the middle of the next decade and 24 GeV after 2010. In support of these plans, an Upgrade Cryomodule capable of providing more than three times the voltage of the original CEBAF cryomodule specification within the same length is under development. Development activities have been focused on critical areas thought to have maximum impact on the overall design. These have included the cavity structure, rf power coupling, cavity suspension, alignment, cavity tuning, and beamline interface. It has been found that all design and development areas are tightly coupled and can not be developed independently. Substantial progress has been made toward an integrated design for the Jefferson Lab Upgraded Cryomodule

  13. Upgradation of automatic liquid scintillation counting system

    International Nuclear Information System (INIS)

    Bhattacharya, Sadhana; Behere, Anita; Sonalkar, S.Y.; Vaidya, P.P.

    2001-01-01

    This paper describes the upgradation of Microprocessor based Automatic Liquid Scintillation Counting systems (MLSC). This system was developed in 1980's and subsequently many systems were manufactured and supplied to Environment Survey labs at various Nuclear Power Plants. Recently this system has been upgraded to a more sophisticated one by using PC add-on hardware and developing Windows based software. The software implements more intuitive graphical user interface and also enhances the features making it comparable with commercially available systems. It implements data processing using full spectrum analysis as against channel ratio method adopted earlier, improving the accuracy of the results. Also it facilitates qualitative as well as quantitative analysis of the β-spectrum. It is possible to analyze a sample containing an unknown β-source. (author)

  14. ATA upgrade to 150 MeV

    International Nuclear Information System (INIS)

    Birx, D.L.; Hawkins, S.A.; Poor, S.E.; Reginato, L.L.; Smith, M.W.

    1985-01-01

    The increased interests in upgrading the ATA accelerator has warranted a preliminary look at applying the magnetic drivers to achieve both higher energy and higher average power. The goal of this upgrade is to satisfy the FEL requirements and to keep the capability of producing a higher current beam for CPB experiments at reduced energy. ATA Note 247 showed that a possible solution to obtain higher energy was simply to add additional cells, run them at higher voltage and accept a 30 ns pulse width with about 5% energy variation. Considering the recent history of the cells and the doubling of the voltage stress that would be required at the insulator, it seemed prudent to review the overall system reliability and try a different approach

  15. Exergy analysis for a proposed binary geothermal power plant in Nisyros Island, Greece

    DEFF Research Database (Denmark)

    Koroneos, Christopher; Polyzakis, A.; Xydis, George

    2017-01-01

    and a measure of the quality of the different forms of energy in relation to given environmental conditions. In this paper, data from an experimental geothermal drill in the Greek Island of Nisyros, located in the south of the Aegean Sea, have been used in order to estimate the maximum available work...... resulted supporting technical feasibility of the proposed geothermal plant....

  16. 76 FR 20822 - Proposed Information Collection (Living Will and Durable Power of Attorney for Health Care...

    Science.gov (United States)

    2011-04-13

    ... instructions about health care decisions in the event he or she is no longer has decision-making capability... whether the information will have practical utility; (2) the accuracy of VHA's estimate of the burden of the proposed collection of information; (3) ways to enhance the quality, utility, and clarity of the...

  17. Implementation and test of proposals to integrate human factors in reporting and causal analysis in nuclear power plants

    International Nuclear Information System (INIS)

    Wilpert; Maimer, H.; Miller, R.; Fahlbruch, B.; Leiber, I.; Szameitat, S.; Baggen, R.; Gans, A.; Becker, G.

    1998-01-01

    The research project 'Implementation and Test of Proposals to integrate Human Factors in Reporting and Causal Analysis in Nuclear Power Plants' ('Implementation and Test', SR 2039/8) is based on two antecedent projects: 'Reporting System' (SR 2039/1) and 'Causal Analysis' (SR 2039/2). The project 'Implementation and Test' conducted various tests and introductory programs in cooperation with different target groups concerning the event analysis methodology 'SOL - Safety through Organizational Learning': Regulators, consultant organizations, union/works councillors and utilities. Thus, SOL was concurrently optimized and [apted for the practice in the German nuclear power industry. SOL was also validated in a German nuclear power plant using a concrete event. Results of the 'Implementation and Test' project demonstrate that SOL is fit to conduct event analyses practicably and economically with appropriate comprehensiveness and depth. SOL facilitates the identification of relevant contributing factors of events. This report concludes with various concrete proposals for the further development of the Program of the Federal Ministry of Environment, Nature Protection and Reactor Safety (BMU) and the Federal Agency of R[iation Protection (BfS) concerning 'The Contribution of Humans to Safety of Nuclear Power Plants'. (orig.) [de

  18. Public regulation of site selection for nuclear power plants. Present procedures and reform proposals: an annotated bibliography

    International Nuclear Information System (INIS)

    Klema, E.D.; West, R.L.

    1977-01-01

    Part I of this bibliography contains literature which describes the process of power-plant siting as conducted by the utilities, siting procedures at the point of initiative, analytical tools employed or proposed for site assessment by enterprises in the industry, and the wide range of considerations which the utilities take into account in making site assessments. Part II contains studies and reports on the structure and process of public regulation of power plant siting: the licensing of nuclear facilities by the NRC under terms of the special Government powers in the field of nuclear energy that have evolved since World War II; the steady expansion of regulatory objectives bearing on site approval for nuclear power plants; local government, State, and other Federal agency regulation of siting; survey siting procedures in other countries; the role of regulatory delay in the long lead-time required for construction and operation of nuclear plants. Part III incudes citations on regulatory structure and practice that are unresponsive to the public interest; regulatory decision making's insufficient accessible to public scrutiny and participation; and regulatory procedures that encourage and protect inefficient practices of the regulated industries. Some legal decisions and case studies are included. Part IV, Reform Proposals, includes citations on regulatory reform and reform of siting regulations. Abstracts are provided with 157 of the citations with many more papers cited by title, author, and accession data

  19. Slum Upgrading and Health Equity.

    Science.gov (United States)

    Corburn, Jason; Sverdlik, Alice

    2017-03-24

    Informal settlement upgrading is widely recognized for enhancing shelter and promoting economic development, yet its potential to improve health equity is usually overlooked. Almost one in seven people on the planet are expected to reside in urban informal settlements, or slums, by 2030. Slum upgrading is the process of delivering place-based environmental and social improvements to the urban poor, including land tenure, housing, infrastructure, employment, health services and political and social inclusion. The processes and products of slum upgrading can address multiple environmental determinants of health. This paper reviewed urban slum upgrading evaluations from cities across Asia, Africa and Latin America and found that few captured the multiple health benefits of upgrading. With the Sustainable Development Goals (SDGs) focused on improving well-being for billions of city-dwellers, slum upgrading should be viewed as a key strategy to promote health, equitable development and reduce climate change vulnerabilities. We conclude with suggestions for how slum upgrading might more explicitly capture its health benefits, such as through the use of health impact assessment (HIA) and adopting an urban health in all policies (HiAP) framework. Urban slum upgrading must be more explicitly designed, implemented and evaluated to capture its multiple global environmental health benefits.

  20. Upgrade trigger: Biannual performance update

    CERN Document Server

    Aaij, Roel; Couturier, Ben; Esen, Sevda; De Cian, Michel; De Vries, Jacco Andreas; Dziurda, Agnieszka; Fitzpatrick, Conor; Fontana, Marianna; Grillo, Lucia; Hasse, Christoph; Jones, Christopher Rob; Le Gac, Renaud; Matev, Rosen; Neufeld, Niko; Nikodem, Thomas; Polci, Francesco; Del Buono, Luigi; Quagliani, Renato; Schwemmer, Rainer; Seyfert, Paul; Stahl, Sascha; Szumlak, Tomasz; Vesterinen, Mika Anton; Wanczyk, Joanna; Williams, Mark Richard James; Yin, Hang; Zacharjasz, Emilia Anna

    2017-01-01

    This document presents the performance of the LHCb Upgrade trigger reconstruction sequence, incorporating changes to the underlying reconstruction algorithms and detector description since the Trigger and Online Upgrade TDR. An updated extrapolation is presented using the most recent example of an Event Filter Farm node.

  1. Independent review of the SaskPower rate proposal of August 2004 : final report

    International Nuclear Information System (INIS)

    Ewing, J.D.; Buhr, L.A.

    2004-01-01

    This paper presents an independent review of SaskPower's request for an increase in rates effective September 1, 2004 and September 1, 2005. With the exception of manufacturing customers, whose rate increase will be phased in over four years, these rate changes will result in a 9 per cent system average increase in 2004 and a 1.8 per cent system average increase in 2005. The report presents an introduction and description of the terms of reference for this review; a financial outlook and comparisons; system operational analysis; an analysis of expenditures; revenue requirement; cost of service issues; and rate design. The report also presents a summary and recommendations on cost of service and rate design issues. The report concluded that the scope of this review does not lend itself to a definitive conclusion on the appropriateness of the cost of service model and its application by SaskPower. Several areas needing further attention include: net fuel and purchased power allocations to different classes; allocation of rate base and in particular distribution rate base to various classes; target ratios for revenue to revenue requirements and the subsequent return on rate base percentages for each class; and demand/energy/customer components of revenue requirements compared to billing revenues. refs., 31 tabs., 1 fig., 6 appendices

  2. A study on the sensitivity of self-powered neutron detectors (SPNDs) and a new proposal

    International Nuclear Information System (INIS)

    Lee, Wan No; Cho, Gyu Seong

    1997-01-01

    Self-Powered Neutron Detectors (SPNDs) are currently used to estimate the power generation distribution and fuel burn-up in several nuclear power reactors in Korea. In this paper, Monte Carlo simulation is accomplished to calculate the escape probability of beta particle as a function of their birth position for the typical geometry of rhodium-based SPNDs. Also, a simple numerical method calculates the initial generation rate of beta particles and the change of generation rate due to rhodium burn-up. Using the simulation and the numerical method, the burn-up profile of rhodium density and the neutron sensitivity are calculated as a function of burn-up time in the reactor. The sensitivity of the SPNDs decreases non-linearly due to the high absorption cross-section and the non-uniform burn-up of rhodium in the emitter rod. In addition, for improvement of some properties of rhodium-based SPNDs which are currently used, this paper presents a new material. The method used here can be applied to the analysis of other types of SPNDs and will be useful in the optimum design of new SPNDs for long term usage

  3. Upgrading the ATLAS control system

    International Nuclear Information System (INIS)

    Munson, F.H.; Ferraretto, M.

    1993-01-01

    Heavy-ion accelerators are tools used in the research of nuclear and atomic physics. The ATLAS facility at the Argonne National Laboratory is one such tool. The ATLAS control system serves as the primary operator interface to the accelerator. A project to upgrade the control system is presently in progress. Since this is an upgrade project and not a new installation, it was imperative that the development work proceed without interference to normal operations. An additional criteria for the development work was that the writing of additional ''in-house'' software should be kept to a minimum. This paper briefly describes the control system being upgraded, and explains some of the reasons for the decision to upgrade the control system. Design considerations and goals for the new system are described, and the present status of the upgrade is discussed

  4. LHC luminosity upgrade detector challenges

    CERN Multimedia

    CERN. Geneva; de Roeck, Albert; Bortoletto, Daniela; Wigmans, Richard; Riegler, Werner; Smith, Wesley H

    2006-01-01

    LHC luminosity upgrade: detector challenges The upgrade of the LHC machine towards higher luminosity (1035 cm -2s-1) has been studied over the last few years. These studies have investigated scenarios to achieve the increase in peak luminosity by an order of magnitude, as well as the physics potential of such an upgrade and the impact of a machine upgrade on the LHC DETECTORS. This series of lectures will cover the following topics: • Physics motivation and machine scenarios for an order of magnitude increase in the LHC peak luminosity (lecture 1) • Detector challenges including overview of ideas for R&D programs by the LHC experiments: tracking and calorimetry, other new detector developments (lectures 2-4) • Electronics, trigger and data acquisition challenges (lecture 5) Note: the much more ambitious LHC energy upgrade will not be covered

  5. Computer codes used during upgrading activities at MINT TRIGA reactor

    International Nuclear Information System (INIS)

    Mohammad Suhaimi Kassim; Adnan Bokhari; Mohd Idris Taib

    1999-01-01

    MINT TRIGA Reactor is a 1-MW swimming pool nuclear research reactor commissioned in 1982. In 1993, a project was initiated to upgrade the thermal power to 2 MW. The IAEA assistance was sought to assist the various activities relevant to an upgrading exercise. For neutronics calculations, the IAEA has provided expert assistance to introduce the WIMS code, TRIGAP, and EXTERMINATOR2. For thermal-hydraulics calculations, PARET and RELAP5 were introduced. Shielding codes include ANISN and MERCURE. However, in the middle of 1997, MINT has decided to change the scope of the project to safety upgrading of the MINT Reactor. This paper describes some of the activities carried out during the upgrading process. (author)

  6. BioPower and economic theology. Critical review of the Giorgio Agamben’s proposals

    Directory of Open Access Journals (Sweden)

    Adán Salinas Araya

    2015-02-01

    Full Text Available The article make a critical review of the Giorgio Agamben’s proposals, showing the tensions between Homo sacer I and The Kingdom and the Glory. In this review is taken in particular consideration how a possible economic theology would constitute a projection of the Foucault’s biopolitical analysis; or rather, continuity of schmittians political theology. For this, the main arguments of the Agamben’s proposal and some of the Schmitt debates with Benjamin and Peterson are reconstructed. In the first case, regarding messianism, and the second, regarding the impossibility of political theology. The economic theology of Agamben and the political theology of Schmitt would share a same status, both necessarily express the conviction that theology is able to justify a speech and a political order.

  7. The Fermilab ACNET upgrade

    International Nuclear Information System (INIS)

    Briegel, C.; Johnson, G.; Winterowd, L.

    1990-01-01

    The Fermilab Accelerator Controls Network (ACNET) upgrade consists of a new physical medium (IEEE 802.5 token ring), additions to the calling sequence and added processor support. ACNET is the accelerator control backbone network for all data communication. A proprietary network was replaced by an IEEE standard enabling an open network with excellent characteristics for the control system. The calling sequence was enhanced for the added capabilities of the token-ring interface such as 'gather-read' and 'scatter-write'. In addition to prior support of DEC PDP11s under RS11M and VAXs under VMS, the ACNET calling sequence was implemented in the language C for the IBM PC with MS-DOS and Motorola 680x0 with MTOS using VME bus. Additional support is in progress for Intel 80x86 with MTOS using Multibus II. (orig.)

  8. Power plant cable condition monitoring and testing at Georgia Power

    International Nuclear Information System (INIS)

    Champion, T.C.

    1988-01-01

    Georgia Power's Research Center has been heavily involved in the evaluation of electrical insulating materials and cables since its inception more than 17 years ago. For the past ten years that expertise has been applied to cables used in generation plants. This paper discusses the results of two test programs. The first is a quality control inspection on 169 samples of new power generation cables. The second is a material degradation evaluation on four short cable samples removed from a coal fired plant during an equipment upgrade. The new material evaluation was performed to identify the cause of a high failure rate upon initial hi-pot testing of newly installed cables. The material degradation evaluation was performed to evaluate the need for replacement of existing cables during an equipment upgrade. Results of the evaluations have led to development of a detailed proposal for a program to evaluate cable degradation and remaining life for cables used in power generation facilities

  9. The ALICE Central Trigger Processor (CTP) upgrade

    International Nuclear Information System (INIS)

    Krivda, M.; Alexandre, D.; Barnby, L.S.; Evans, D.; Jones, P.G.; Jusko, A.; Lietava, R.; Baillie, O. Villalobos; Pospíšil, J.

    2016-01-01

    The ALICE Central Trigger Processor (CTP) at the CERN LHC has been upgraded for LHC Run 2, to improve the Transition Radiation Detector (TRD) data-taking efficiency and to improve the physics performance of ALICE. There is a new additional CTP interaction record sent using a new second Detector Data Link (DDL), a 2 GB DDR3 memory and an extension of functionality for classes. The CTP switch has been incorporated directly onto the new LM0 board. A design proposal for an ALICE CTP upgrade for LHC Run 3 is also presented. Part of the development is a low latency high bandwidth interface whose purpose is to minimize an overall trigger latency

  10. A proposed power assisted system of manual wheelchair based on universal design for eldery

    Science.gov (United States)

    Susmartini, Susy; Pryadhitama, Ilham; Herdiman, Lobes; Wahyufitriani, Cindy

    2017-11-01

    Difficulties in walking is high percentage case in the limitations mobility of the elderly. An assisted technology commonly used to help the elderly who have walking difficulty is a manual wheelchair. However, the elderly frequently experiences difficulties in operating manual wheelchair due to gradually degradation of their physical condition. Preliminary study results showed that the average grip strength of the hands of seven elderly subjects was 13.8 ± 6.96 kg and the value is relatively weak. In addition, the mean maximum speed of 7 elderly subjects when doing to round the wheelchair is 0.6 ± 0.2m / s. This value is only 56.4% compared with an average speed of 20-23-year age group (8 males), which is 1.1 ± 0.1 m / s. This shows that the elderly who have walking difficulty have low grip strength and speed in operating a wheelchair. On the other hand, manual wheelchairs suffer an inadequate technology solution to solve the problem. Therefore, an assistive technology is proposed to create mobility aid to accommodate the elderly needs. One approach used is Universal Design. This paper proposes a system of intervention in the manual wheelchair through the 7 principles of Universal Design approach. The preliminary principle has not been able to accommodate the needs of the elderly will become a reference in the proposed design of this study.

  11. Study and Proposal of the Nuclear Power Plant Technology for the Ninh Thuan 2 Project

    International Nuclear Information System (INIS)

    Tran Chi Thanh; Le Van Hong; Hoang Sy Than; Nguyen Van De; Mai Dinh Trung; Nguyen Nhi Dien; Nguyen Minh Tuan; Pham Van Lam; Phan Ngoc Tuyen; Do Chi Dung; Hoang Minh Giang; Le Dai Dien

    2015-01-01

    The Ninh Thuan 1&2 Nuclear Power Plant Projects were approved on November 25th, 2009. At present, the task of NPP technology selection of these projects is an important and complex task. This report will show the acceptable method to create a set of criterion for selecting technology for Ninh Thuan 2 NPP project. The result of evaluation of three NPP technologies, such as ATMEA1, AP1000 and MPWR+ introduced in the Feasibility Study Reports of this project, will be discussed. In conclusion, the AP1000 technology is the first candidate for the Ninh Thuan 2 NPP Project. (author)

  12. Structural seismic upgrading of NPPs in Czech and Slovak republics

    Energy Technology Data Exchange (ETDEWEB)

    David, M [DAVID Consulting, Engineering and Design Office, Prague (Czech Republic)

    1997-03-01

    Several Nuclear Power Plants of the VVER type has been constructed during the past years in former Czechoslovak Republic. Some of them has been already put in operation and some of them are under construction. Nuclear Power Plants V1(2 units of VVER 440/230), V2(2 units of VVER 440/213) in Slovak and NPP Dukovany (4 units of VVER 440/213) in Czech republic are in operation. NPP Mochovce (4 units of VVER 440/213) in Slovak and NPP Temelin (4 units reduced now to 2 units VVER 1000) have been already almost completed, but still under construction. All above cited NPPs have not been either explicitly designed against earthquake or the design against earthquake or its input data must be upgraded to be compatible with present requirements. The upgrading of seismic input as well the seismic upgrading of all structures and technological equipments for so many NPPs has involved a lot of comprehensive work in Czech as well as in Slovak republics. The upgrading cannot be completed in a short time and as a rule the seismic upgrading has been usually performed in several steps, beginning with the most important arrangements against seismic hazard. The basic principles and requirements for seismic upgrading has been defined in accordance with the international and particularly with the IAEA recommendations. About the requirements for seismic upgrading of NPPs in Czech and Slovak republics will be reported in other contribution. This contribution is dealing with the problems of seismic upgrading of NNPs civil engineering structures. The aim of this contribution is to point out some specific problems connected firstly with very complicated concept of Versa structures and secondly with the difficult task to increase the structural capacity to the required seismic level. (J.P.N.)

  13. Structural seismic upgrading of NPPs in Czech and Slovak republics

    International Nuclear Information System (INIS)

    David, M.

    1997-01-01

    Several Nuclear Power Plants of the VVER type has been constructed during the past years in former Czechoslovak Republic. Some of them has been already put in operation and some of them are under construction. Nuclear Power Plants V1(2 units of VVER 440/230), V2(2 units of VVER 440/213) in Slovak and NPP Dukovany (4 units of VVER 440/213) in Czech republic are in operation. NPP Mochovce (4 units of VVER 440/213) in Slovak and NPP Temelin (4 units reduced now to 2 units VVER 1000) have been already almost completed, but still under construction. All above cited NPPs have not been either explicitly designed against earthquake or the design against earthquake or its input data must be upgraded to be compatible with present requirements. The upgrading of seismic input as well the seismic upgrading of all structures and technological equipments for so many NPPs has involved a lot of comprehensive work in Czech as well as in Slovak republics. The upgrading cannot be completed in a short time and as a rule the seismic upgrading has been usually performed in several steps, beginning with the most important arrangements against seismic hazard. The basic principles and requirements for seismic upgrading has been defined in accordance with the international and particularly with the IAEA recommendations. About the requirements for seismic upgrading of NPPs in Czech and Slovak republics will be reported in other contribution. This contribution is dealing with the problems of seismic upgrading of NNPs civil engineering structures. The aim of this contribution is to point out some specific problems connected firstly with very complicated concept of Versa structures and secondly with the difficult task to increase the structural capacity to the required seismic level. (J.P.N.)

  14. SLC-2000: A luminosity upgrade for the SLC

    International Nuclear Information System (INIS)

    Breidenbach, M.; Decker, F.-J.; Helm, R.; Napoly, O.; Phinney, N.; Raimondi, P.; Raubenheimer, T.O.; Siemann, R.; Zimmermann, F.; Hertzbach, S.

    1996-01-01

    We discuss a possible upgrade to the Stanford Linear Collider (SLC), whose objective is to increase the SLC luminosity by at least a factor 7, to an average Z production rate of more than 35,000 per week. The centerpiece of the upgrade is the installation of a new superconducting final doublet with a field gradient of 240 T/m, which will be placed at a distance of only 70 cm from the interaction point. In addition, several bending magnets in each final focus will be lengthened and two octupole correctors are added. A complementary upgrade of damping rings and bunch compressors will allow optimum use of the modified final focus and can deliver, or exceed, the targeted luminosity. The proposed upgrade will place the SLC physics program in a very competitive position, and will also enable it to pursue its pioneering role as the first and only linear collider. (author)

  15. Hybrid biogas upgrading in a two-stage thermophilic reactor

    DEFF Research Database (Denmark)

    Corbellini, Viola; Kougias, Panagiotis; Treu, Laura

    2018-01-01

    The aim of this study is to propose a hybrid biogas upgrading configuration composed of two-stage thermophilic reactors. Hydrogen is directly injected in the first stage reactor. The output gas from the first reactor (in-situ biogas upgrade) is subsequently transferred to a second upflow reactor...... (ex-situ upgrade), in which enriched hydrogenotrophic culture is responsible for the hydrogenation of carbon dioxide to methane. The overall objective of the work was to perform an initial methane enrichment in the in-situ reactor, avoiding deterioration of the process due to elevated pH levels......, and subsequently, to complete the biogas upgrading process in the ex-situ chamber. The methane content in the first stage reactor reached on average 87% and the corresponding value in the second stage was 91%, with a maximum of 95%. A remarkable accumulation of volatile fatty acids was observed in the first...

  16. Optimization bitumen-based upgrading and refining schemes

    Energy Technology Data Exchange (ETDEWEB)

    Munteanu, M.; Chen, J. [National Centre for Upgrading Technology, Devon, AB (Canada); Natural Resources Canada, Devon, AB (Canada). CanmetENERGY

    2009-07-01

    This poster highlighted the results of a study in which the entire refining scheme for Canadian bitumen as feedstocks was modelled and simulated under different process configurations, operating conditions and product structures. The aim of the study was to optimize the economic benefits, product quality and energy use under a range of operational scenarios. Optimal refining schemes were proposed along with process conditions for existing refinery configurations and objectives. The goal was to provide guidelines and information for upgrading and refining process design and retrofitting. Critical steps were identified with regards to the upgrading process. It was concluded that the information obtained from this study would lead to significant improvement in process performance and operations, and in reducing the capital cost for building new upgraders and refineries. The simulation results provided valuable information for increasing the marketability of bitumen, reducing greenhouse gas emissions and other environmental impacts associated with bitumen upgrading and refining. tabs., figs.

  17. Mathematical investigation of the possibility of a power increase of the subcritical assembly in Dubna (SAD) up to 100 kW

    International Nuclear Information System (INIS)

    Petrochenkov, S.A.; Shvetsov, V.N.; Polanski, A.

    2007-01-01

    We present the results of Monte-Carlo modeling of the experimental accelerator-driven electronuclear system composed of the subcritical assembly and DLNP JINR Phasotron. The expected thermal power of the subcritical assembly in Dubna (SAD) is about 30 kW. The possibility of assembly power increase without changes in design and basic elements is considered. The proposed assembly upgrade gives power increase up to 100 kW. It is of importance that proposed upgrade operations can be performed both before and after the run with nominal power and partial fulfillment of a basic experimental program

  18. Upgrading of PWR plant simulators

    International Nuclear Information System (INIS)

    Wada, Tomonori; Sasaki, Kazunori; Nakaishi, Hirokazu.

    1989-01-01

    For the education and training of operators in electric power plants, simulators have been employed, and it is well known that their effect is great. There are operation training simulators which simulate the dynamic characteristics of plants and all the machinery and equipment that operators handle, and train the procedure of restoration at the time of abnormality in plants, education simulators which can analyze the dynamic characteristics of plants efficiently in a short time, and offer information by visualizing phenomena with three-dimensional display and others so as to be easily understandable, and forecast simulators which do the analysis forecasting plant behavior at the time of abnormality in plants, and investigate the necessity of the guide for operation procedure and the countermeasures at the time of emergency. In this explanation, the upgrading of operation training simulators which have been put already in training is discussed. The constitution of simulator system and the instructor function, the outline of PWR plant simulation models comprising thermal flow model, pump model, leak model and so on, the techniques of increasing simulator speed, and the example of analysis using the NUPAC code are reported. (K.I.)

  19. IPNS upgrade: A feasibility study

    International Nuclear Information System (INIS)

    1995-04-01

    Many of Argonne National Laboratory's (ANL's) scientific staff members were very active in R ampersand D work related to accelerator-based spoliation sources in the 1970s and early 1980s. In 1984, the Seitz/Eastman Panel of the National Academy of Sciences reviewed U.S. materials science research facilities. One of the recommendations of this panel was that the United States build a reactor-based steady-state source, the Advanced Neutron Source (ANS), at Oak Ridge National Laboratory. Subsequently, R ampersand D activities related to the design of an accelerator-based source assumed a lower priority. The resumption of pulsed-source studies in this country started simultaneously with design activities in Europe aimed at the European Spallation Source (ESS). The European Community funded a workshop in September 1991 to define the parameters of the ESS. Participants in this workshop included both accelerator builders and neutron source users. A consortium of European countries has proposed to build a 5-MW pulsed source, and a feasibility study is currently under way. Soon after the birth of the ESS, a small group at ANL set about bringing themselves up to date on pulsed-source information since 1984 and studied the feasibility of upgrading ANL's Intense Pulsed Neutron Source (IPNS) to 1 MW by means of a rapidly cycling synchrotron that could be housed, along with its support facilities, in existing buildings. In early 1993, the Kohn panel recommended that (1) design and construction of the ANS should be completed according to the proposed project schedule and (2) development of competitive proposals for cost-effective design and construction of a 1-MW pulsed spallation source should be authorized immediately

  20. IPNS upgrade: A feasibility study

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    Many of Argonne National Laboratory`s (ANL`s) scientific staff members were very active in R&D work related to accelerator-based spoliation sources in the 1970s and early 1980s. In 1984, the Seitz/Eastman Panel of the National Academy of Sciences reviewed U.S. materials science research facilities. One of the recommendations of this panel was that the United States build a reactor-based steady-state source, the Advanced Neutron Source (ANS), at Oak Ridge National Laboratory. Subsequently, R&D activities related to the design of an accelerator-based source assumed a lower priority. The resumption of pulsed-source studies in this country started simultaneously with design activities in Europe aimed at the European Spallation Source (ESS). The European Community funded a workshop in September 1991 to define the parameters of the ESS. Participants in this workshop included both accelerator builders and neutron source users. A consortium of European countries has proposed to build a 5-MW pulsed source, and a feasibility study is currently under way. Soon after the birth of the ESS, a small group at ANL set about bringing themselves up to date on pulsed-source information since 1984 and studied the feasibility of upgrading ANL`s Intense Pulsed Neutron Source (IPNS) to 1 MW by means of a rapidly cycling synchrotron that could be housed, along with its support facilities, in existing buildings. In early 1993, the Kohn panel recommended that (1) design and construction of the ANS should be completed according to the proposed project schedule and (2) development of competitive proposals for cost-effective design and construction of a 1-MW pulsed spallation source should be authorized immediately.

  1. A proposed aging management program for alkali silica reactions in a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Saouma, Victor E., E-mail: saouma@colorado.edu; Hariri-Ardebili, Mohammad A.

    2014-10-01

    Drawing from publicly available information, this paper addresses the alkali silica reaction management of Seabrook nuclear power plant. The essence of the reaction is first examined, followed by a summary of findings, current and planned work. Then, the authors draw on their experience in ASR to first comment on the current work, and then complete the paper with what they would recommend. An important observation is that ASR constitutes a major challenge to the nuclear industry, and a thorough understanding of the State of the Art is essential before a holistic approach is undertaken. It is neither a simple nor an inexpensive challenge, yet a most critical one that industry and regulators must confront. This paper is only a breach into such an effort.

  2. A proposed aging management program for alkali silica reactions in a nuclear power plant

    International Nuclear Information System (INIS)

    Saouma, Victor E.; Hariri-Ardebili, Mohammad A.

    2014-01-01

    Drawing from publicly available information, this paper addresses the alkali silica reaction management of Seabrook nuclear power plant. The essence of the reaction is first examined, followed by a summary of findings, current and planned work. Then, the authors draw on their experience in ASR to first comment on the current work, and then complete the paper with what they would recommend. An important observation is that ASR constitutes a major challenge to the nuclear industry, and a thorough understanding of the State of the Art is essential before a holistic approach is undertaken. It is neither a simple nor an inexpensive challenge, yet a most critical one that industry and regulators must confront. This paper is only a breach into such an effort

  3. Risk-vs.-benefit communication for the example of nuclear power a proposed concept

    International Nuclear Information System (INIS)

    Notz, M.; Schupfner, M.; Susanek, A.; Waldthausen, D. von; Wilderer, M.

    2002-01-01

    The need to communicate risks and benefits in the field of nuclear power is widely underestimated. In the light of new requirements and stricter framework conditions, this will continue to play an important role. In this connection, the international expansion of the activities of power utilities increasingly requires characteristics specific to certain countries to be taken into account. At the same time, the internationalization of perception causes interdependences of the activities of companies in various countries, which should also be made part of a communication strategy. Risk-vs.-benefit communication, by its very nature and as a result of its history, is fraught with many difficulties. However, most of the problems result from the failure to pay attention to fundamental rules of communication, such as addressee-orientedness, bilaterality, and purposefulness. The main objective of risk-vs.-benefit communication as argued in this paper is to create trust, credibility, and acceptance through an active design of communication. For this purpose, companies need a communication concept integrated into their systems of objectives, incorporating aspects of long-term strategy, and taking into account any weak points identified. The main features of the concept developed in this contribution are the systematic approach, the inclusion of interdependences, and the explicit analysis of the different levels of communication. This is to contribute to successful risk-vs.-benefit communication and, in this way, improve the position of the brand and the perceived integrity of the company. In particular, it allows aspects of long-term strategy to be included in the definition of communication measures as well as a deliberate support of internationalization. (orig.) [de

  4. Upgrade of the CMS Global Muon Trigger

    CERN Document Server

    Jeitler, Manfred; Rabady, Dinyar; Sakulin, Hannes; Stahl, Achim

    2015-01-01

    The increase in center-of-mass energy and luminosity for Run-II of the Large Hadron Collider poses new challenges for the trigger systems of the experiments. To keep triggering with a similar performance as in Run-I, the CMS muon trigger is currently being upgraded. The new algorithms will provide higher resolution, especially for the muon transverse momentum and will make use of isolation criteria that combine calorimeter with muon information already in the level-1 trigger. The demands of the new algorithms can only be met by upgrading the level-1 trigger system to new powerful FPGAs with high bandwidth I/O. The processing boards will be based on the new μTCA standard. We report on the planned algorithms for the upgraded Global Muon Trigger (μGMT) which sorts and removes duplicates from boundaries of the muon trigger sub-systems. Furthermore, it determines how isolated the muon candidates are based on calorimetric energy deposits. The μGMT will be implemented using a processing board that features a larg...

  5. H-1 Upgrades (4BW/4BN) (H-1 Upgrades)

    Science.gov (United States)

    2015-12-01

    automatic blade fold of the new composite rotor blades, new performance matched transmissions, a new four-bladed tail rotor and drive system, upgraded...Upgrades December 2015 SAR March 18, 2016 10:59:17 UNCLASSIFIED 4 Col Steven Girard PMA-276 USMC Light/Attack Helicopter Program Executive Officer...attack helicopter is to provide rotary wing close air support, anti-armor, armed escort, armed/visual reconnaissance and fire support coordination

  6. Proposal for the award of a contract, without competitive tendering, for the maintenance of uninterruptable power supply systems

    CERN Document Server

    2003-01-01

    This document concerns the award of a contract, without competitive tendering, for the maintenance of uninterruptable power supply systems. The Finance Committee is invited to agree to the negotiation of a contract, without competitive tendering, for the maintenance of uninterruptable power supply systems with MGE (FR) for a total amount of 575 000 euros (911 000 Swiss francs), covering an initial period of five years, subject to revision for inflation after 1 January 2007. The contract will include options for two one-year extensions beyond the initial five-year period. The amount in Swiss francs has been calculated using the present rate of exchange. The firm has indicated the following distribution by country of the contract value covered by this adjudication proposal: FR - 100%.

  7. Core exit thermocouple upgrade at Zion station

    International Nuclear Information System (INIS)

    Ulinski, T.M.; Ferg, D.A.

    1989-01-01

    Following the Three Mile Island accident, the ability of the core exit thermocouple (CET) system to monitor reactor core conditions and core cooling status became a requirement of the U.S. Nuclear Regulatory Commission (NRC). Since the thermocouple system at Zion station was not originally required for postaccident monitoring, Commonwealth Edison Company (CECo) committed to upgrading the CET system and to installing a subcooling margin monitoring (SMM) system. The significance of this commitment was that CECo proposed to accomplish the upgrade effort using internal resources and by developing the required in-house expertise instead of procuring integrated packages from several nuclear steam supply system vendors. The result was that CECo was able to demonstrate a number of new capabilities and unique design features with a significant cost savings. These included a qualified connector with an integral thermocouple cold-reference junction temperature compensation; the design, assembly, testing, and installation of a seismically qualified class 1E microprocessor; a commercial-grade dedication/upgrade process for safety-related hardware; a human factors review capability, and a verification and validation program for safety-related software. A discussion of these new capabilities and details of the design features is presented in this paper

  8. MODEL REQUEST FOR PROPOSALS TO PROVIDE ENERGY AND OTHER ATTRIBUTES FROM AN OFFSHORE WIND POWER PROJECT

    Energy Technology Data Exchange (ETDEWEB)

    Jeremy Firestone; Dawn Kurtz Crompton

    2011-10-22

    This document provides a model RFP for new generation. The 'base' RFP is for a single-source offshore wind RFP. Required modifications are noted should a state or utility seek multi-source bids (e.g., all renewables or all sources). The model is premised on proposals meeting threshold requirements (e.g., a MW range of generating capacity and a range in terms of years), RFP issuer preferences (e.g., likelihood of commercial operation by a date certain, price certainty, and reduction in congestion), and evaluation criteria, along with a series of plans (e.g., site, environmental effects, construction, community outreach, interconnection, etc.). The Model RFP places the most weight on project risk (45%), followed by project economics (35%), and environmental and social considerations (20%). However, if a multi-source RFP is put forward, the sponsor would need to either add per-MWh technology-specific, life-cycle climate (CO2), environmental and health impact costs to bid prices under the 'Project Economics' category or it should increase the weight given to the 'Environmental and Social Considerations' category.

  9. Proposed framework for the Western Area Power Administration Environmental Risk Management Program

    Energy Technology Data Exchange (ETDEWEB)

    Glantz, C.S.; DiMassa, F.V.; Pelto, P.J.; Brothers, A.J. [Pacific Northwest Lab., Richland, WA (United States); Roybal, A.L. [Western Area Power Administration, Golden, CO (United States)

    1994-12-01

    The Western Area Power Administration (Western) views environmental protection and compliance as a top priority as it manages the construction, operation, and maintenance of its vast network of transmission lines, substations, and other facilities. A recent Department of Energy audit of Western`s environmental management activities recommends that Western adopt a formal environmental risk program. To accomplish this goal, Western, in conjunction with Pacific Northwest Laboratory, is in the process of developing a centrally coordinated environmental risk program. This report presents the results of this design effort, and indicates the direction in which Western`s environmental risk program is heading. Western`s environmental risk program will consist of three main components: risk communication, risk assessment, and risk management/decision making. Risk communication is defined as an exchange of information on the potential for threats to human health, public safety, or the environment. This information exchange provides a mechanism for public involvement, and also for the participation in the risk assessment and management process by diverse groups or offices within Western. The objective of risk assessment is to evaluate and rank the relative magnitude of risks associated with specific environmental issues that are facing Western. The evaluation and ranking is based on the best available scientific information and judgment and serves as input to the risk management process. Risk management takes risk information and combines it with relevant non-risk factors (e.g., legal mandates, public opinion, costs) to generate risk management options. A risk management tool, such as decision analysis, can be used to help make risk management choices.

  10. The Atlas upgrade project

    International Nuclear Information System (INIS)

    Bollinger, L.M.

    1988-01-01

    ATLAS is a heavy-ion accelerator system consisting of a 9-MV tandem electrostatic injector coupled to a superconducting linac. A project now well advanced will upgrade the capabilities of ATLAS immensely by replacing the tandem and its negative-ion source with a positive-ion injector that consists of an electron-cyclotron resonance (ECR) ion source and a 12-MV superconducting injector linac of novel design. This project will increase the beam intensity 100 fold and will extend the projectile-mass range up to uranium. Phase 1 of the work, which is nearing completion in late 1988, will provide an injector comprising the ECR source and its 350-kV voltage platform, beam analysis and bunching systems, beam lines, and a prototype 3-MV linac. The ECR source and its voltage platform are operational, development of the new class of low-frequency interdigital superconducting resonators required for the injector linac has been completed, and assembly of the whole system is in progress. Test runs and then routine use of the Phase 1 injector systems are planned for early 1989, and the final 12-MV injector linac will be commissioned in 1990. 12 refs., 6 figs

  11. Altair performance and upgrades

    Science.gov (United States)

    Lai, Olivier; Véran, Jean-Pierre; Herriot, Glen; White, John; Ball, Jesse; Trujillo, Chad

    2014-07-01

    Altair is the facility single conjugate AO system for Gemini North. Although it has been in operation for more than 10 years (and upgraded to LGS in 2007), Altair's performance is degraded by three main issues: vibrations of the telescope and instrument support structure, spatial aliasing on centroid offsets from the M2 support structure print-through on the optical surface and static non-common path aberrations. Monte-Carlo simulations can reproduce the behavior of Altair when including these three effects and they are roughly of the same order of magnitude. Solutions or mitigations are being investigated to overcome these nefarious effects and restore Altair's performance to its nominal level. A simplex algorithm as well as a phase diversity approach are being investigated to measure and correct for static aberrations. A high accuracy phase map of the M2 print-through has been obtained and is being used to calibrate and/or filter centroids affected by aliasing. A new real time computer is under consideration, to be able to handle more advanced controllers, especially notch filters to combat vibrations. In this paper we will report on the various simulations and on-sky results of this rejuvenation of one of Gemini's workhorse instruments.

  12. Alberta propylene upgrading prospects

    International Nuclear Information System (INIS)

    2000-03-01

    A very significant byproduct recovery and purification scheme is at present being prepared by TransCanada Midstream (TCMS). Alberta Economic Development commissioned an independent study to identify propylene supply options while proceeding with the evaluation of various propylene derivatives with regard to their fit with the Alberta context. Identification of chemical companies with derivative interests was also accomplished. By 2005, it is estimated that 280 kilo-tonnes of propylene will be available on an annual basis from byproduct sources. Those sources are oil sands upgraders, ethylene plants and refineries. The ranges of impurities and supply costs vary between the different sources. An option being considered involves pipeline and rail receipt with a major central treating and distillation facility for the production of polymer grade (PG) propylene with propane and other smaller byproducts. Special consideration was given to three chemicals in this study, namely: polypropylene (PP), acrylonitrile (ACN), and acrylic acid (AA). Above average growth rates were identified for these chemicals: demand is growing at 6 to 7 per cent a year for both PP and ACN, while demand for AA grows at 8 per cent annually. Two other possibilities were identified, propylene oxide (PO) and phenol. The study led to the conclusion that low capital and operating costs and shipping costs to the Pacific Rim represent advantages to the development of propylene derivatives in the future in Alberta. 4 refs., 87 tabs., 7 figs

  13. Progress and plan of KSTAR plasma control system upgrade

    Energy Technology Data Exchange (ETDEWEB)

    Hahn, Sang-hee, E-mail: hahn76@nfri.re.kr [National Fusion Research Institute, Daejeon (Korea, Republic of); Kim, Y.J. [National Fusion Research Institute, Daejeon (Korea, Republic of); Penaflor, B.G. [General Atomics, San Diego, CA (United States); Bak, J.G.; Han, H.; Hong, J.S.; Jeon, Y.M.; Jeong, J.H.; Joung, M.; Juhn, J.W.; Kim, J.S.; Kim, H.S.; Lee, W.R.; Woo, M.H. [National Fusion Research Institute, Daejeon (Korea, Republic of); Eidietis, N.W.; Ferron, J.R.; Humphreys, D.A.; Hyatt, A.; Johnson, R.D.; Piglowski, D.A. [General Atomics, San Diego, CA (United States); and others

    2016-11-15

    Highlights: • Recent achievements of the KSTAR plasma control system are described. • Requirements and results of the testbed system for the future upgrade of the KSTAR plasma control system are presented. • An overview of the upgrade layout based is given. - Abstract: The plasma control system (PCS) has been one of essential systems in annual KSTAR plasma campaigns: starting from a single-process version in 2008, extensive upgrades are done through the previous 7 years in order to achieve major goals of KSTAR performance enhancement. Major implementations are explained in this paper. In consequences of successive upgrades, the present KSTAR PCS is able to achieve ∼48 s of 500 kA plasma pulses with full real-time shaping controls and real-time NB power controls. It has become a huge system capable of dealing with 8 separate categories of algorithms, 26 actuators directly controllable during the shot, and real-time data communication units consisting of +180 analog channels and +600 digital input/outputs through the reflective memory (RFM) network. The next upgrade of the KSTAR PCS is planned in 2015 before the campaign. An overview of the upgrade layout will be given for this paper. The real-time system box is planned to use the CERN MRG-Realtime OS, an ITER-compatible standard operating system. New hardware is developed for faster real-time streaming system for future installations of actuators/diagnostics.

  14. A proposed adaptive step size perturbation and observation maximum power point tracking algorithm based on photovoltaic system modeling

    Science.gov (United States)

    Huang, Yu

    Solar energy becomes one of the major alternative renewable energy options for its huge abundance and accessibility. Due to the intermittent nature, the high demand of Maximum Power Point Tracking (MPPT) techniques exists when a Photovoltaic (PV) system is used to extract energy from the sunlight. This thesis proposed an advanced Perturbation and Observation (P&O) algorithm aiming for relatively practical circumstances. Firstly, a practical PV system model is studied with determining the series and shunt resistances which are neglected in some research. Moreover, in this proposed algorithm, the duty ratio of a boost DC-DC converter is the object of the perturbation deploying input impedance conversion to achieve working voltage adjustment. Based on the control strategy, the adaptive duty ratio step size P&O algorithm is proposed with major modifications made for sharp insolation change as well as low insolation scenarios. Matlab/Simulink simulation for PV model, boost converter control strategy and various MPPT process is conducted step by step. The proposed adaptive P&O algorithm is validated by the simulation results and detail analysis of sharp insolation changes, low insolation condition and continuous insolation variation.

  15. Mongolia - Vocational Education - Equipment Upgrades

    Data.gov (United States)

    Millennium Challenge Corporation — Evaluation design The impact evaluation sought to identify the causal impact of exposure to equipment upgrades on subsequent outcomes. Insofar as we were not able to...

  16. Mining Upgrades to Reduce Pollution

    Science.gov (United States)

    Settlement with Southern Coal Corporation and 26 affiliates requires the companies to comprehensively upgrade their coal mining and processing operations to prevent polluted wastewater from threatening rivers and streams and communities across Appalachia.

  17. Fermilab linac upgrade. Module conditioning results

    International Nuclear Information System (INIS)

    Kroc, T.; Moretti, A.; Popovic, M.

    1992-01-01

    The 805 MHz side-coupled cavity modules for the Fermilab 400 MeV linac upgrade have been conditioned to accept full power. The sparking rate in the cavities and in the side cells has been reduced to acceptable levels. It required approximately 40 x 10 6 pulses for each module to achieve an adequately low sparking rate. This contribution outlines the commissioning procedure, presents the sparking rate improvements and the radiation level improvements through the commissioning process and discusses the near-on-line commissioning plans for this accelerator. (Author) ref., 4 figs

  18. Fermilab Linac Upgrade: Module conditioning results

    International Nuclear Information System (INIS)

    Kroc, T.; Moretti, A.; Popovic, M.

    1992-12-01

    The 805 MHz Side-coupled cavity modules for the Fermilab 400 MeV linac upgrade have been conditioned to accept full power. The sparking rate in the cavities and in the side-cells has been reduced to acceptable levels. It required approximately 40 x 10 6 pulses for each module to achieve an adequately low sparking rate. This contribution outlines the commissioning procedure, presents the sparking rate improvements and the radiation level improvements through the commissioning process and disc the near-online commissioning plans for this accelerator

  19. Silicon Tracking Upgrade at CDF

    International Nuclear Information System (INIS)

    Kruse, M.C.

    1998-04-01

    The Collider Detector at Fermilab (CDF) is scheduled to begin recording data from Run II of the Fermilab Tevatron in early 2000. The silicon tracking upgrade constitutes both the upgrade to the CDF silicon vertex detector (SVX II) and the new Intermediate Silicon Layers (ISL) located at radii just beyond the SVX II. Here we review the design and prototyping of all aspects of these detectors including mechanical design, data acquisition, and a trigger based on silicon tracking

  20. WNP-2 core model upgrade

    International Nuclear Information System (INIS)

    Golightly, C.E.; Ravindranath, T.K.; Belblidia, L.A.; O'Farrell, D.; Andersen, P.S.

    2006-01-01

    The paper describes the core model upgrade of the WNP-2 training simulator and the reasons for the upgrade. The core model as well as the interface with the rest of the simulator are briefly described . The paper also describes the procedure that will be used by WNP-2 to update the simulator core data after future core reloads. Results from the fully integrated simulator are presented. (author)

  1. Analysis of integrated plant upgrading/life extension programs

    International Nuclear Information System (INIS)

    McCutchan, D.A.; Massie, H.W. Jr.; McFetridge, R.H.

    1988-01-01

    A present-worth generating cost model has been developed and used to evaluate the economic value of integrated plant upgrading life extension project in nuclear power plants. This paper shows that integrated plant upgrading programs can be developed in which a mix of near-term availability, power rating, and heat rate improvements can be obtained in combination with life extension. All significant benefits and costs are evaluated from the viewpoint of the utility, as measured in discounted revenue requirement differentials between alternative plans which are equivalent in system generating capacity. The near-term upgrading benefits are shown to enhance the benefit picture substantially. In some cases the net benefit is positive, even if the actual life extension proves to be less than expected

  2. Setting priorities for safeguards upgrades

    International Nuclear Information System (INIS)

    Al-Ayat, R.A.; Judd, B.R.; Patenaude, C.J.; Sicherman, A.

    1987-01-01

    This paper describes an analytic approach and a computer program for setting priorities among safeguards upgrades. The approach provides safeguards decision makers with a systematic method for allocating their limited upgrade resources. The priorities are set based on the upgrades cost and their contribution to safeguards effectiveness. Safeguards effectiveness is measured by the probability of defeat for a spectrum of potential insider and outsider adversaries. The computer program, MI$ER, can be used alone or as a companion to ET and SAVI, programs designed to evaluate safeguards effectiveness against insider and outsider threats, respectively. Setting the priority required judgments about the relative importance (threat likelihoods and consequences) of insider and outsider threats. Although these judgments are inherently subjective, MI$ER can analyze the sensitivity of the upgrade priorities to these weights and determine whether or not they are critical to the priority ranking. MI$ER produces tabular and graphical results for comparing benefits and identifying the most cost-effective upgrades for a given expenditure. This framework provides decision makers with an explicit and consistent analysis to support their upgrades decisions and to allocate the safeguards resources in a cost-effective manner

  3. Evaluating Proposed Investments in Power System Reliability and Resilience: Preliminary Results from Interviews with Public Utility Commission Staff

    Energy Technology Data Exchange (ETDEWEB)

    LaCommare, Kristina [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Larsen, Peter [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Eto, Joseph [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2017-01-01

    Policymakers and regulatory agencies are expressing renewed interest in the reliability and resilience of the U.S. electric power system in large part due to growing recognition of the challenges posed by climate change, extreme weather events, and other emerging threats. Unfortunately, there has been little or no consolidated information in the public domain describing how public utility/service commission (PUC) staff evaluate the economics of proposed investments in the resilience of the power system. Having more consolidated information would give policymakers a better understanding of how different state regulatory entities across the U.S. make economic decisions pertaining to reliability/resiliency. To help address this, Lawrence Berkeley National Laboratory (LBNL) was tasked by the U.S. Department of Energy Office of Energy Policy and Systems Analysis (EPSA) to conduct an initial set of interviews with PUC staff to learn more about how proposed utility investments in reliability/resilience are being evaluated from an economics perspective. LBNL conducted structured interviews in late May-early June 2016 with staff from the following PUCs: Washington D.C. (DCPSC), Florida (FPSC), and California (CPUC).

  4. Status of the University of Missouri-Columbia Research Reactor upgrade

    Energy Technology Data Exchange (ETDEWEB)

    McKibben, J C; Edwards, Jr, C B; Meyer, Jr, W A [MU Research Reactor, Columbia, MO (United States); Kim, S S [Idaho Nuclear Engineering Laboratory, Idaho Falls, ID (United States)

    1990-05-01

    The University of Missouri-Columbia (MU) Research Reactor Facility staff is in the process of upgrading the operational and research capabilities of the reactor and associated facilities. The upgrades include an extended life aluminide fuel element, a power increase, improved instrumentation and control equipment, a cold neutron source, a building addition, and improved research instrumentation and equipment. These upgrades will greatly enhance the capabilities of the facility and the research programs. This paper discusses the parts of the upgrade and current status of implementation. (author)

  5. Status of the University of Missouri-Columbia Research Reactor upgrade

    International Nuclear Information System (INIS)

    McKibben, J.C.; Edwards, C.B. Jr.; Meyer, W.A. Jr.; Kim, S.S.

    1990-01-01

    The University of Missouri-Columbia (MU) Research Reactor Facility staff is in the process of upgrading the operational and research capabilities of the reactor and associated facilities. The upgrades include an extended life aluminide fuel element, a power increase, improved instrumentation and control equipment, a cold neutron source, a building addition, and improved research instrumentation and equipment. These upgrades will greatly enhance the capabilities of the facility and the research programs. This paper discusses the parts of the upgrade and current status of implementation. (author)

  6. An examination of the proposals for the off-site electrical power sources at the Sizewell B PWR

    Energy Technology Data Exchange (ETDEWEB)

    Woodhouse, P. A. [HM Nuclear Installations Inspectorate, London (United Kingdom)

    1986-02-15

    Over the past few years there has been an increase in the attention being given to the adequacy and reliability of alternative sources of power provided to supply safety equipment should off-site electrical sources fail. This paper discusses the rationale of HM Nuclear Installations Inspectorates assessment of the electrical systems proposed for the UK's first Pressurized water Reactor, Sizewell 3. The requirements for on-site sources are given, and a discussion is provided of the NII's Assessment Principles including common mode failure, single failure criterion and reliability targets. Where the assessment has resulted in notifications to the original design the reasons are given. The UK's large interconnected Grid System makes complete losses of off-site power comparatively rare. The potential exists however and this paper shows how the current approach ensures that not only are adequate on-site sources available but also that their siting, maintenance and testing are such that loss of off-site power will not cause an unacceptable risk to the public. (author)

  7. Upgrading inflatable door seals

    International Nuclear Information System (INIS)

    Sykes, T.M.; Metcalfe, R.; Welch, L.A.; Josefowich, J.M.

    1997-01-01

    Inflatable door seals are used for airlocks in CANDU stations. They have been a significant source of unreliability and maintenance cost. A program is underway to improve their performance and reliability, backed by environmental qualification testing. Only commercial products and suppliers existed in 1993. For historical reasons, these 'existing products' did not use the most durable material then available. In hindsight, neither had they been adapted nor optimized to combat conditions often experienced in the plants-sagging doors, damaged sealing surfaces, and many thousands of openings and closings per year. Initial attempts to involve the two existing suppliers in efforts to upgrade these seals were unsuccessful. Another suitable supplier had therefore to be found, and a 'new,' COG-owned seal developed; this was completed in 1997. This paper summarizes its testing, along with that of the two existing products. Resistance to aging has been improved significantly. Testing has shown that an accident can be safely withstood after 10 years of service or 40,000 openings-closings, whichever comes first. AECL's Fluid Sealing Technology Unit (FSTU) has invested in the special moulds, test fixtures and other necessary tooling and documentation required to begin commercial manufacture of this new quality product. Accordingly, as with FSTU's other nuclear products such as pump seals, the long-term supply of door seals to CANDU plants is now protected from many external uncertainties-e.g., commercial products being discontinued, materials being changed, companies going out of business. Manufacturing to AECL's detailed specifications is being subcontracted to the new supplier. FSTU is performing the quality surveillance, inspection, testing, and customer service activities concomitant with direct responsibility for supply to the plants. (author)

  8. Instrumentation and control upgrade evaluation methodology. Volume 1: Manual. Final report

    International Nuclear Information System (INIS)

    Bliss, M.; Brown, E.; Florio, F.; Stofko, M.

    1996-07-01

    This methodology manual describes how to develop an Upgrade Evaluation Report (UER) for an I and C system that has been identified as an upgrade candidate in the I and C Life Cycle Management Plan (LCMP). A UER can be developed by a nuclear power plant to determine the cost-effectiveness and feasibility of upgrading an aging or obsolete Instrumentation and Control (I and C) System. A separate UER is developed for each upgrade candidate system. A UER will determine if a given system requires an upgrade or if it is more cost-effective to maintain the present system. If an upgrade is unnecessary, the system will be reclassified as a retained system and a system maintenance plan will be developed for it. This manual is accompanied by a workbook (EPRI TR-104963-V2) which contains various worksheets, outlines, and generic interview questions that aid in the UER development process

  9. Trigger tracking for the LHCb upgrade

    CERN Multimedia

    Dungs, K

    2014-01-01

    This poster presents a trigger system for the upgraded LHCb detector, scheduled to begin operation in 2020. The proposed trigger system is implemented entirely in software. We show that track reconstruction of a similar quality to that available in the offline algorithms can be performed on the full inelastic pp-collision rate. A track finding efficiency of 98.8% relative to offline can be achieved for good trigger tracks. The CPU time required for this reconstruction is less than 60% of the available budget.

  10. Power distribution studies for CMS forward tracker

    International Nuclear Information System (INIS)

    Todri, A.; Turqueti, M.; Rivera, R.; Kwan, S.

    2009-01-01

    The Electronic Systems Engineering Department of the Computing Division at the Fermi National Accelerator Laboratory is carrying out R and D investigations for the upgrade of the power distribution system of the Compact Muon Solenoid (CMS) Pixel Tracker at the Large Hadron Collider (LHC). Among the goals of this effort is that of analyzing the feasibility of alternative powering schemes for the forward tracker, including DC to DC voltage conversion techniques using commercially available and custom switching regulator circuits. Tests of these approaches are performed using the PSI46 pixel readout chip currently in use at the CMS Tracker. Performance measures of the detector electronics will include pixel noise and threshold dispersion results. Issues related to susceptibility to switching noise will be studied and presented. In this paper, we describe the current power distribution network of the CMS Tracker, study the implications of the proposed upgrade with DC-DC converters powering scheme and perform noise susceptibility analysis.

  11. Straflo upgrade for Laufenburg

    Energy Technology Data Exchange (ETDEWEB)

    Ruoss, R.; Gyenge, J.; Fischer, F.

    1988-03-01

    Built in the early years of this century to generate power from the headwaters of the river Rhine, the Laufenburg power station is undergoing modernization. Previous upratings have brought its net output from 40MW to 81MW. The present plant utilizes 10 Straflo turbines in place of Francis machines and the planned maximum output is 106MW. The turbines are described in some detail in this paper, together with associated modifications to the plant.

  12. The analysis and rationale behind the upgrading of existing standard definition thermal imagers to high definition

    Science.gov (United States)

    Goss, Tristan M.

    2016-05-01

    With 640x512 pixel format IR detector arrays having been on the market for the past decade, Standard Definition (SD) thermal imaging sensors have been developed and deployed across the world. Now with 1280x1024 pixel format IR detector arrays becoming readily available designers of thermal imager systems face new challenges as pixel sizes reduce and the demand and applications for High Definition (HD) thermal imaging sensors increases. In many instances the upgrading of existing under-sampled SD thermal imaging sensors into more optimally sampled or oversampled HD thermal imaging sensors provides a more cost effective and reduced time to market option than to design and develop a completely new sensor. This paper presents the analysis and rationale behind the selection of the best suited HD pixel format MWIR detector for the upgrade of an existing SD thermal imaging sensor to a higher performing HD thermal imaging sensor. Several commercially available and "soon to be" commercially available HD small pixel IR detector options are included as part of the analysis and are considered for this upgrade. The impact the proposed detectors have on the sensor's overall sensitivity, noise and resolution is analyzed, and the improved range performance is predicted. Furthermore with reduced dark currents due to the smaller pixel sizes, the candidate HD MWIR detectors are operated at higher temperatures when compared to their SD predecessors. Therefore, as an additional constraint and as a design goal, the feasibility of achieving upgraded performance without any increase in the size, weight and power consumption of the thermal imager is discussed herein.

  13. Feasibility analysis in the expansion proposal of the nuclear power plant Laguna Verde: application of real options, binomial model

    International Nuclear Information System (INIS)

    Hernandez I, S.; Ortiz C, E.; Chavez M, C.

    2011-11-01

    At the present time, is an unquestionable fact that the nuclear electrical energy is a topic of vital importance, no more because eliminates the dependence of the hydrocarbons and is friendly with the environment, but because is also a sure and reliable energy source, and represents a viable alternative before the claims in the growing demand of electricity in Mexico. Before this panorama, was intended several scenarios to elevate the capacity of electric generation of nuclear origin with a variable participation. One of the contemplated scenarios is represented by the expansion project of the nuclear power plant Laguna Verde through the addition of a third reactor that serves as detonator of an integral program that proposes the installation of more nuclear reactors in the country. Before this possible scenario, the Federal Commission of Electricity like responsible organism of supplying energy to the population should have tools that offer it the flexibility to be adapted to the possible changes that will be presented along the project and also gives a value to the risk to future. The methodology denominated Real Options, Binomial model was proposed as an evaluation tool that allows to quantify the value of the expansion proposal, demonstrating the feasibility of the project through a periodic visualization of their evolution, all with the objective of supplying a financial analysis that serves as base and justification before the evident apogee of the nuclear energy that will be presented in future years. (Author)

  14. The Advanced Light Source Upgrade

    International Nuclear Information System (INIS)

    Chemla, Daniel S.; Feinberg, Benjamin; Hussain, Zahid; Krebs, Gary F.; Padmore, Howard A.; Robin, David S.; Robinson, Arthur L.; Smith, Neville V.

    2003-01-01

    The ALS, a third-generation synchrotron light source at Berkeley Lab, has been operating for almost a decade and is generating forefront science by exploiting the high brightness of a third-generation source in three areas: (1) high resolving power for spectroscopy; (2) high spatial resolution for microscopy and spectromicroscopy; and (3) high coherence for experiments such as speckle. However, the ALS was one of the first third-generation machines to be designed, and accelerator and insertion-device technology have significantly changed since its conception. As a result, its performance will inevitably be outstripped by newer, more advanced sources. To remain competitive and then set a new standard, the performance of the ALS, in particular its brightness, must be enhanced. Substantial improvements in brightness and current have always been feasible in principle, but they incur the penalty of a much reduced lifetime, which is totally unacceptable to our users. Significant brightness improvements can be realized in the core soft x-ray region by going to top-off operation, where injection would be quasi-continuous and the lifetime objections disappear. In top-off mode with higher average current, a reduced vertical emittance and beta function, and small-gap permanent-magnet or superconducting insertion devices, one to two orders of magnitude improvement in brightness can be had in the soft x-ray range. These improvements also extend the high energy range of the undulator radiation beyond the current limit of 2000 eV. Descriptions of the upgrade and the important new science achievable are presented

  15. Technical and economic proposal for the extension of the Laguna Verde Nuclear Power plant with an additional nuclear reactor

    International Nuclear Information System (INIS)

    Leal C, C.D.; Francois L, J.L.

    2006-01-01

    The increment of the human activities in the industrial environments and of generation of electric power, through it burns it of fossil fuels, has brought as consequence an increase in the atmospheric concentrations of the calls greenhouse effect gases and, these in turn, serious repercussions about the environment and the quality of the alive beings life. The recent concern for the environment has provoked that industrialized countries and not industrialized carry out international agreements to mitigate the emission from these gases to the atmosphere. Our country, like part of the international community, not is exempt of this problem for what is necessary that programs begin guided toward the preservation of the environment. As for the electric power generation, it is indispensable to diversify the sources of primary energy; first, to knock down the dependence of the hydrocarbons and, second, to reduce the emission of polluting gases to the atmosphere. In this item, the nucleo electric energy not only has proven to be safe and competitive technical and economically, able to generate big quantities of electric power with a high plant factor and a considerable cost, but rather also, it is one of the energy sources that less pollutants it emits to the atmosphere. The main object of this work is to carry out a technical and economic proposal of the extension of the Laguna Verde Nuclear power plant (CNLV) with a new nuclear reactor of type A BWR (Advanced Boiling Water Reactor), evolutionary design of the BWR technology to which belong the two reactors installed at the moment in the plant, with the purpose of increasing the installed capacity of generation of the CNLV and of the Federal Commission of Electricity (CFE) with foundation in the sustainable development and guaranteeing the protection of the environment by means of the exploitation of a clean and sure technology that counts at the moment with around 12,000 year-reactor of operational experience in more of

  16. Major upgrades of the high frequency B-dot probe diagnostic suite on ASDEX Upgrade

    Directory of Open Access Journals (Sweden)

    Ochoukov Roman

    2017-01-01

    Full Text Available The high frequency B-dot (HFB probe diagnostic on the ASDEX Upgrade tokamak has undergone a considerable upgrade during the 2016 opening of the torus. The probe coverage is now greatly expanded toroidally, as well as radially with the addition of probes on the high field side and the removable manipulator head. A new 2-channel fast digitizer now allows to examine and record radio frequency (RF wave emissions emanating from the plasma in the ion cyclotron range of frequencies (ICRF. Possible studies that can be achieved now include: a study of core ICRF power absorption efficiency; a study of ion cyclotron emissions from the plasma generated by energetic ions; and study of ICRF wave/plasma turbulence interactions in the scrape-off layer region.

  17. Extension of electron cyclotron heating at ASDEX Upgrade with respect to high density operation

    Directory of Open Access Journals (Sweden)

    Schubert Martin

    2017-01-01

    Full Text Available The ASDEX Upgrade electron cyclotron resonance heating operates at 105 GHz and 140 GHz with flexible launching geometry and polarization. In 2016 four Gyrotrons with 10 sec pulse length and output power close to 1 MW per unit were available. The system is presently being extended to eight similar units in total. High heating power and high plasma density operation will be a part of the future ASDEX Upgrade experiment program. For the electron cyclotron resonance heating, an O-2 mode scheme is proposed, which is compatible with the expected high plasma densities. It may, however, suffer from incomplete single-pass absorption. The situation can be improved significantly by installing holographic mirrors on the inner column, which allow for a second pass of the unabsorbed fraction of the millimetre wave beam. Since the beam path in the plasma is subject to refraction, the beam position on the holographic mirror has to be controlled. Thermocouples built into the mirror surface are used for this purpose. As a protective measure, the tiles of the heat shield on the inner column were modified in order to increase the shielding against unabsorbed millimetre wave power.

  18. Decision proposal aiming at creating an inquiry commission relative to the vulnerability of the power transportation and distribution network in France

    International Nuclear Information System (INIS)

    2009-02-01

    On January 24, 2009, a violent storm hit the SW of France and led to the collapse of the power network. The low- and medium-voltage lines, in particular, were seriously damaged. This vulnerability of the power grid is particularly ominous and has motivated this proposal of creation of an inquiry commission for: estimating the costs generated by the January 24, 2009 storm, evaluating the resistance capacity of power generation, transport and distribution networks in front of natural disasters or extreme climate conditions, calculating the average cots of the burial of the high- and very-high voltage power lines, studying the impact on health and on environment of aerial and buried very-high voltage power lines, elaborating a scenario of decentralization and diversification of power generation means, identifying the measures to be implemented in priority to significantly reduce the power consumption, and proposing the scheme of an emergency plan for extreme climate riskiness. (J.S.)

  19. Bioelectrochemical removal of carbon dioxide (CO2): an innovative method for biogas upgrading.

    Science.gov (United States)

    Xu, Heng; Wang, Kaijun; Holmes, Dawn E

    2014-12-01

    Innovative methods for biogas upgrading based on biological/in-situ concepts have started to arouse considerable interest. Bioelectrochemical removal of CO2 for biogas upgrading was proposed here and demonstrated in both batch and continuous experiments. The in-situ biogas upgrading system seemed to perform better than the ex-situ one, but CO2 content was kept below 10% in both systems. The in-situ system's performance was further enhanced under continuous operation. Hydrogenotrophic methanogenesis and alkali production with CO2 absorption could be major contributors to biogas upgrading. Molecular studies showed that all the biocathodes associated with biogas upgrading were dominated by sequences most similar to the same hydrogenotrophic methanogen species, Methanobacterium petrolearium (97-99% sequence identity). Conclusively, bioelectrochemical removal of CO2 showed great potential for biogas upgrading. Copyright © 2014 Elsevier Ltd. All rights reserved.

  20. New window design options for CEBAF energy upgrade

    International Nuclear Information System (INIS)

    Phillips, L.; Mammosser, J.; Nguyen, V.

    1997-01-01

    As the Jefferson Laboratory upgrades the existing CEBAF electron accelerator to operate at higher energies, the fundamental power coupler windows will be required to operate with lower RF dissipation and increased immunity to radiation from cavity field emission. New designs and modifications to existing designs which can achieve these goals are described