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Sample records for bohunice v-1 reactor

  1. Safety upgrading of Bohunice V1 NPP

    International Nuclear Information System (INIS)

    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

  2. Experience of Bohunice V-1 NPP

    International Nuclear Information System (INIS)

    Slovakia remains significantly dependent on imports of primary energy sources, which represent as much as 80% of the demand. Of the total consumption of electricity in Slovakia, 40% was generated in nuclear power plant units in 1998. Slovakia operates 6 units with WWER 440 nuclear reactors. Slovakia is the signatory of all important international agreements and conventions in the field of nuclear energy, and its legislation is in an advanced stage of approximation to European Union law. This is a very important aspect, showing Slovakia's approach to nuclear safety. In 1993 Slovakia accepted the commitments of the UN Convention on Climate Changes, including a reduction of greenhouse gases to 1990 levels by the year 2000. Moreover, as an internal target Slovakia has set the reaching of the 'Toronto Objective', i.e. 20% reduction in COx, emissions through the year 2005 as compared to 1988. In our opinion, this is not possible without nuclear energy. Time has shown, that the political aspects are more powerful, especially if you underestimate their importance over the than the technical ones. In the case of Bohunice V-1 NPP the political aspects were on the following levels: 1. Slovak republic (Czechoslovakia), political changes, decisions of the government; 2. European Union - Agenda 2000, Accession criteria, nuclear safety criteria, EBRD; 3. Austria as a neighbouring country. Starting with year 1990, 23 expert missions took place at Bohunice V-1 NPP by now. The only criteria for further operation should have been Nuclear safety, which is supervised by NRA SR. It was fully in compliance with EU policy, each country is solely responsible for its energy sector and for nuclear energy use. Our satisfaction lasted not too long. Following negotiation with EU on the highest political level, driven by willingness to be invited for negotiation of accession on the Helsinki Summit, the Slovak government decided on September 14th, on Bohunice V-1 Units shutdown in 2006 and 2008

  3. Early closure of Bohunice V1 contested

    International Nuclear Information System (INIS)

    The early closure of the Bohunice V1 nuclear power plant following a time schedule that the Slovak government agreed with the EU three years ago is a political obligation of the government. The only objections to this plan so far have been related to the weakening of the generation base and economy of Slovenske elektrarne (SE), a.s. Neither the Nuclear Regulatory Authority of the Slovak Republic, nor the International Atomic Energy Agency, nor foreign experts preparing the closure of V1 in Jaslovske Bohunice have raised objections relating to increased security risks. Since he took up office last summer, the Minister of Economy Pavol Rusko has not hidden his personal interest in revising the agreement and extending the operation of the nuclear power plant. The fact that closing the power plant would have a negative impact on Slovakia's economy is not an argument good enough to persuade the original EU members. A proven security risk would be a better argument, especially as the operation of the V1 plant would not be extended literally - rather one of the reactors would work two years longer. Risk increased by 100%, a risk close to the level of acceptability in the EU - that is how in October he described the risks related to closure of V1 units according to the agreed time schedule, i.e. the first unit to be shut down by December 31, 2006 at the latest and the second unit by December 2008. The Minister based his opinion on a study prepared by the engineering and consulting company - Relko that assessed the risks V1 would represent after the first unit has been shut down. 'The only solution is to shut down both units at the same time', he concluded and in a comment addressed to the EU he added: 'If the EU has sincere intentions towards Slovakia, respects its security and does not wish it economic problems it will accept this'. (author)

  4. Experience from replacement and check of thermocouples during reconstruction of in-reactor temperature measurements at Bohunice V-1 units 1 and 2

    International Nuclear Information System (INIS)

    Replacement of thermocouples in the protection tube blocks was a key phase of the reconstruction of in-reactor temperature measurements at Bohunice V-1 with regard to the success, reliability and impact on safety of unit operation. The replacement consisted of reliable and safe withdrawal of 216 old thermocouples, their disposal and installation of new thermocouples into dry channels. In the material presented, this phase of reconstruction is described in details, with focus on the evaluation of replacement quality and check activities carried out at the new installed thermocouples. (Authors)

  5. Seismic re-evaluation criteria for Bohunice V1 reconstruction

    International Nuclear Information System (INIS)

    Bohunice V1 in Slovakia is a Russian designed two unit WWER 440, Model 230 Pressurized Water Reactor. The plant was not originally designed for earthquake. Subsequent and ongoing reassessments now confirm that the seismic hazard at the site is significant. EBO, the plant owner has contracted with a consortium lead by Siemens AG (REKON) to do major reconstruction of the plant to significantly enhance its safety systems by the addition of new systems and the upgrading of existing systems. As part of the reconstruction, a complete seismic assessment and upgrading is required for existing safety relevant structures, systems and components. It is not practical to conduct this reassessment and upgrading using criteria applied to new design of nuclear power plants. Alternate criteria may be used to achieve adequate safety goals. Utilities in the U.S. have faced several seismic issues with operating NPPs and to resolve these issues, alternate criteria have been developed which are much more cost effective than use of criteria for new design. These alternate criteria incorporate the knowledge obtained from investigation of the performance of equipment in major earthquakes and include provisions for structures and passive equipment to deform beyond the yield point, yet still provide their essential function. IAEA has incorporated features of these alternate criteria into draft Technical Guidelines for application to Bohunice V1 and V2. REKON has developed plant specific criteria and procedures for the Bohunice V1 reconstruction that incorporate major features of the U.S. developed alternate criteria, comply to local codes and which envelop the draft IAEA Technical Guidelines. Included in these criteria and procedures are comprehensive walkdown screening criteria for equipment, piping, HVAC and cable raceways, analytical criteria which include inelastic energy absorption factors defined on an element basis and testing criteria which include specific guidance on interpretation

  6. REKO - Bohunice V-1. Experience with instrumentation and control system

    International Nuclear Information System (INIS)

    In this paper and in presentation some results of upgrading of the NPP Bohunice V-1 are presented. For the first time, extensive upgrades are performed in all safety-related areas of both units with VVER 440/230 reactors. These upgrades focused on: - Expansion and upgrading of the process safety systems; - Replacement of the safety I and C system with a TELEPERM XS-based system; - Spatial separation of safety equipment; - Modernisation of the electrical auxiliary power systems; - Seismic upgrading and fire protection; - Improvement of the man-machine interface. This upgrade is considered exemplary around the world. The most extensive stage of gradual reconstruction of Unit 2 was completed according to the schedule in January 1999. For the first time, a reactor which incorporates state-of-the-art digital I and C in its reactor protection system is on-line. (author)

  7. Reconstruction of the V-1 nuclear power plant at Jaslovske Bohunice

    International Nuclear Information System (INIS)

    Based on the 1991 recommendation by the former Czechoslovak nuclear regulatory body - the Czechoslovak Atomic Energy Commission - the minor reconstruction of the V-1 nuclear power plant at Jaslovske Bohunice was aimed at safety improvement in the following fields: reactor pressure vessel and primary circuit integrity, hermetic compartments, instrumentation and control systems and accident protection systems, home consumption electrical systems, fire safety, seismic resistance, and reactor aftercooling in case of steam generator feedwater failure. The results of the reconstruction are presented. The reconstruction provided for all the recommendations. (J.B.). 2 tabs

  8. Bohunice V-1 and V-2 approach for achieving high availability, reliability and safety

    International Nuclear Information System (INIS)

    Long term operating experience of Bohunice units maintenance activities are overviewed in the paper. Based on common experience of WWER NPP operators, separate maintenance department was established at Bohunice NPP in very early stage of plant operation. Maintenance management, maintenance planning, outage management, diagnostics and monitoring, inspection technologies and backfitting activities are described particularly to demonstrate the capability of Bohunice maintenance department for most complex repairs and maintenance works of nuclear power plant components and equipment, including reactor and turbine itself. (author)

  9. Method of realization and exploitation of monitoring system for accuracy and reliability characteristics of standard temperature measurements in WWER-440 reactors at NPP Bohunice V1

    International Nuclear Information System (INIS)

    The sequences in development of computer equipment s and the sequences in development of measurement tools and procedures are listed in submitted presentation - from start-up the power plant in operation until present days. Present status of integration of a monitoring system for accuracy and reliability characteristics of standard temperature measurements in WWER-440 reactors in NPP V1 is presented here. The ways of data acquisition, storing of results and their evaluation are described in this presentation. In conclusion some practical possibilities of using a a monitoring system for accuracy and reliability are listed. (Authors)

  10. Safety analysis report, deterministic and probabilistic evaluation after Bohunice V1 NPP gradual upgrading

    International Nuclear Information System (INIS)

    This presentation describes approach used for nuclear safety assessment at the V -1 Bohunice after the Gradual Upgrading. The deterministic and probabilistic results are presented in detail form. (author)

  11. LBB technology application to the primary piping system of the NPP V1 Jaslovske Bohunice

    International Nuclear Information System (INIS)

    Due to several deficiences of the WER Model 230 type reactor a leak before break demonstration of this reactor is of primary importance. The complex project for NPP V1 Jaslovske Bohunice includes a static and dynamic stress analysis of the primary piping, a fatique damage analysis, leak rate assessments and an analysis of the stability of the heavy components supports. The material database includes data on fracture mechanics, on assessment of corrosion properties, and on the influence of 100 000 hr service exposure on base metal and welds including disimilar welds. The program was supported by large scale experiments on RPV safe-end, pressurizer safe-end, elbow welds with through-wall cracks and leak rate measurements. The results and applications are discussed. (orig.)

  12. Experience in modernization of safety I and C in VVER 440 nuclear power plants Bohunice V1 and Paks

    International Nuclear Information System (INIS)

    For nuclear power plants which have been in operation for more than 15 years, backfitting or even complete replacement of the instrumentation and control (I and C) equipment becomes an increasingly attractive option, motivated not only by the objective to reduce the cost of I and C system maintenance and repair but also to prolong or at least to safeguard the plant life-time: optimized spare-part management through use of standard equipment; reduction of number and variety of different items of equipment by implementing functions stepwise in application software; adding new functionality in the application software which was not possible in the old technology due to lack of space; safeguarding of long-term After-Sales-Service. Some years ago Bohunice V1 NPP, Slovak Republic and Paks NPP, Hungary intended to replace parts of their Safety I and C, mainly the Reactor Trip System, the Reactor Limitation System and the Neutron Flux Excore Instrumentation and Monitoring Systems. After a Basic Engineering Phase in Bohunice V1 and a Feasibility Study in Paks both plants decided to use the Siemens' Digital Safety I and C System TELEPERM XS to modernize their plants. Both Bohunice, Unit 2 and Paks, Unit 1 have been back on line for over six months with the new Digital Safety I and C. At the present time Bohunice, Unit 1 and within the next few months Paks, Unit 2 will be replaced. Trouble-free start-ups and no major problems under operation in the first two plants were based on: thorough understanding of the VVER 440 technology; comprehensive planning together with the plant operators and authorities; the possibility to adapt TELEPERM XS to every plant type; the execution of extensive pre-operational tests. Regarding these modernization measures Siemens, as well as the above Operators, have gained considerable experience in the field of I and C Modernization in VVER 440 NPPs. Important aspects of this experience are: how to transfer the VVER technology to TELEPERM XS; how to

  13. Safety first. Nuclear power plant in Jaslovske Bohunice

    International Nuclear Information System (INIS)

    In this leaflet the production of electricity in nuclear power plants, philosophy of nuclear safety with reactor WWER, influence of ionization radiation on the man, improvement on the reactor, reconstructed system on the Bohunice V-1 reactors, nuclear reactor WWER, nuclear fuel and fission reaction, are described. A briefly history of Bohunice V-1 NPP is presented

  14. Project Management Unit for decommissioning of NPP Bohunice VI (2003-2014); Project Management Unit para el desmantelamiento de CN Bohunice V1 (2003-2014)

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez Fernandez-conde, A.; Brochet, I.; Ferreira, A.

    2015-07-01

    From October 2003 until december 2014 the Consortium consisting of Iberdrola Engineering and Construction (leader). Empresarios Agrupados Internacional, and Indra Sistemas has carried out the project Project Management Unit ((PMU) for the decommissioning of Bohunice V1 NPP (units 1 and 2), type VVER-440/V-230 in Slovakia. during the first phase (2003-2007) EdF was also part of the Consortium. The project is funded by the Bohunice International Decommissioning Support Fund (BIDSF) administered by the RBRD. The main objective of the project is to provide the necessary engineering and resources of project management for planning, execution, management, coordination and monitoring of all tasks in support of the decommissioning. (Author)

  15. Post-reconstruction full power and shut down level 2 PSA study for Unit 1 of Bohunice V1 NPP

    International Nuclear Information System (INIS)

    The level 2 PSA model of the J. Bohunice V1 NPP was developed in the RISK SPECTRUM Professional code with the following objectives: to identify the ways in which radioactive releases from the plant can occur following the core damage; to calculate the magnitudes and frequency of the release; to provide insights into the plant behaviour during a severe accident; to provide a framework for understanding containment failure modes; the impact of the phenomena that could occur during and following core damage and have the potential to challenge the integrity of the confinement; to support the severe accident management and development of SAMGs. The magnitudes of release categories are calculated using: the MAAP4/VVER for reactor operation and shutdown mode with closed reactor vessel and the MELCOR code for shutdown mode with open reactor vessel. In this paper an overview of the Level 2 PSA methodology; description of the confinement; the interface between the level 1 and 2 PSA and accident progression analyses are presented. An evaluation of the confinement failure modes and construction of the confinement event trees as well as definition of release categories, source term analysis and sensitivity analyses are also discussed. The presented results indicate that: 1)for the full power operation - there is an 25% probability that the confinement will successfully maintain its integrity and prevent an uncontrolled fission product release; the most likely mode of release from the confinement is a confinement bypass after SGTM with conditional probability of 30%; the conditional probability for the confinement isolation failure probability without spray is 5%, for early confinement failure at the vessel failure is 4%, for other categories 1% or less; 2) for the shutdown operating modes - the shutdown risk is high for the open reactor vessel and open confinement; important severe accident sequences exists for release categories: RC5.1, RC5.2 and RC6.2

  16. Seismic re-evaluation and upgrading of Bohunice V1 NPP

    International Nuclear Information System (INIS)

    Bohunice V1 in Slovakia is a two unit WWER 440/230 whose units went into commercial operation in 1979 and 1981 respectively. The plant was not initially designed for seismic loading. Later geotechnical studies concluded that the site seismic hazard should be defined as an earthquake of MSK 8 intensity. This relates to approximately 0.25 g peak ground acceleration in the free field at the site. Some early reconstruction to strengthen the plant against earthquakes was done in the early 1990s but did not include all safety significant structures and equipment. In 1996, EBO, the plant operator, entered into a contract with consortium REKON, a Siemens and VUJE joint venture, for a major reconstruction program to update all safety systems required for a safe shutdown, to improve integrity of confinement and assure spent fuel cooling. This reconstruction project includes verification of seismic adequacy of all safety related structures and equipment in the REKON scope which is not being replaced by new construction. Siemens and EQE International are jointly conducting the seismic verification and required upgrading for the existing structures and equipment. Criteria for the verification and upgrading were developed for the project utilizing Technical Guidelines provided by IAEA, Reference 1, and linking them with international and local codes and standards and specific methodologies developed for similar projects in the US and Western Europe. The criteria are briefly discussed herein and are summarized in a companion paper, Reference 4. Because of the major improvements being implemented in safety systems, much of the essential safety related equipment is being directly replaced or completely new systems are being constructed that supersede existing ones. Consequently, a significant amount of the equipment that would normally require seismic adequacy verification is deleted from the verification scope (see Table 4). The reconstruction project will continue through 1999

  17. Findings from measurement of vertical displacement of V-1 nuclear power plant buildings in Jaslovske Bohunice

    International Nuclear Information System (INIS)

    Vertical displacements were measured of the foundations and of selected bearing structures of the V-1 nuclear power plant buildings during the plant's construction and operation. Measured were displacements of the engine room foundations, the reactor building, the boron management building, the turbogenerator building, the cooling towers, the ventilation stack, and the foundations of buildings showing adverse properties. Some results are presented. (E.J.). 4 figs., 2 refs

  18. Resin intrusion into the primary circuit of NPP Jaslovske Bohunice V-1

    International Nuclear Information System (INIS)

    During the refueling at the first unit of Bohunice NPP in 2005 a lot of sediment was found on the upper storage rack. This sediment was identification as a filter resin. Resin was found in most of the fuel assemblies, pipes and tanks of the primary circuit and his auxiliary systems. Resin producer and WANO network was contacted in order to get information about similar events. Management of Bohunice NPP made a decision that primary circuit, fuel assemblies and auxiliary systems have to be cleaned. Subsequent cleaning extended outage by 31 days. This paper summarizes causes, existing consequences and corrective actions. Accent was put on the hydraulic characteristics of the primary circuit measurement, power distribution core monitoring and the primary circuit water quality verification (Authors)

  19. Selective Leaching of aerosol particles collected by cascade impactor in the ventilation stack of NPP V1 in Jaslovske Bohunice

    International Nuclear Information System (INIS)

    The study was apart of investigation of the size distribution of aerosol in air effluents from NPP V1 Jaslovske Bohunice. The evaluation the possible relationship between aerodynamic diameter of aerosol particles and chemical forms of radionuclides attached to the discharged aerosol was tried. Selective leaching was used for speciation of radionuclides present in the aerosol particles and for the estimation of their behaviour in the environment and absorption in gastro-intestinal tract. Activity concentrations of the radionuclides in the air, collected on collection substrates taken from individual impact stages and on back-up filter, were determined by sensitive gamma-spectrometric analysis using high purity Ge detectors. For the individual groups seven leaching steps were used. Following 12 radionuclides: silver-110m, cobalt-58, cobalt-60, cesium-134, cesium-137, manganese-54, ruthenium-103, antimony-124, antimony-125, tin-113, zinc-65, zirconium-95. Result shows that the leached fraction of the of the activity concentration does not depend on the size of the aerosol particles. (J.K.) 3 tabs., 3 figs

  20. Results of reconstruction of in-core outlet coolant temperature measurements at V-230 reactors, Unit 1 and 2 NPP Bohunice

    International Nuclear Information System (INIS)

    During the reconstruction of NPP V 1 Bohunice units with V-230 reactors, all in-core temperature measuring systems were upgraded. All measuring channels including thermocouples up to data acquisition system were replaced. The report provides the objectives, process and results of the reconstruction. Accuracy and reliability of the in-core measurements were enhanced, and their resistance to accident environment was achieved. Moreover metrological assurance and automatic self-check of accuracy with the temperature etalon of reactor measurements were achieved. The obtained quality of the in-core temperature measurements exceeds that of similar systems in V-213 reactors. (Authors)

  1. Bituminization plant Jaslovske Bohunice

    International Nuclear Information System (INIS)

    In this leaflet the principle of the bituminization plant for radioactive concentrate (the intermediate liquid radioactive waste generated during the NPP A1, V-1, V-2 operations) solidification used in the Bohunice Radwaste Treatment Centre (BSC RAO) is presented

  2. Thirtieth anniversary of reactor accident in A-1 Nuclear Power Plant Jaslovske Bohunice

    International Nuclear Information System (INIS)

    The facts about reactor accidents in A-1 Nuclear Power Plant Jaslovske Bohunice, Slovakia are presented. There was the reactor KS150 (HWGCR) cooled with carbon dioxide and moderated with heavy water. A-1 NPP was commissioned on December 25, 1972. The first reactor accident happened on January 5, 1976 during fuel loading. This accident has not been evaluated according to the INES scale up to the present time. The second serious accident in A-1 NPP occurred on February 22, 1977 also during fuel loading. This INES level 4 of reactor accident resulted in damaged fuel integrity with extensive corrosion damage of fuel cladding and release of radioactivity into the plant area. The A-1 NPP was consecutively shut down and is being decommissioned in the present time. Both reactor accidents are described briefly. Some radioecological and radiobiological consequences of accidents and contamination of area of A-1 NPP as well as of Manivier Canal and Dudvah River as result of flooding during the decommissioning are presented (authors)

  3. The LBB methodology application results performed on the safety related piping of NPP V-1 in Jaslovske Bohunice

    Energy Technology Data Exchange (ETDEWEB)

    Kupca, L.; Beno, P. [Nuclear Power Plants Research Institute, Trnava (Slovakia)

    1997-04-01

    A broad overview of the leak before break (LBB) application to the Slovakian V-1 nuclear power plant is presented in the paper. LBB was applied to the primary cooling circuit and surge lines of both WWER 440 type units, and also used to assess the integrity of safety related piping in the feed water and main steam systems. Experiments and calculations performed included analyses of stresses, material mechanical properties, corrosion, fatigue damage, stability of heavy component supports, water hammer, and leak rates. A list of analysis results and recommendations are included in the paper.

  4. Bohunice Nuclear Power Plant Safety Upgrading Program

    International Nuclear Information System (INIS)

    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)

  5. Safety enhancement in NPP Bohunice

    International Nuclear Information System (INIS)

    The upgrading and safety enhancement of both the Bohunice V-1 and V-2 reactors is described in detail. The total estimated cost of the gradual reconstruction of these two units during 1996 to 1999 is 180 mil. US dollars. For the 1995 to 1997 period, the actions common for both units include a quality assurance programme, a personnel training programme, installation of a multifunction simulator, implementation of symptom-oriented operation procedures, installation of diagnostic systems, of a site security system, and of a teledosimetric system. At present, the main maintenance tasks are: to carry out major repair of units, to remedy service interruptions, to enhance equipment service availability, to enhance the technical level of corrective actions at equipment. Investment into maintenance level upgrade has grown from 7.5 mil. Slovak crowns in 1994 to estimated 32 mil. in 2000. The partners of international cooperation are mentioned. (M.D.)

  6. The fast breeder reactor. v. 1

    International Nuclear Information System (INIS)

    The Energy Committee's report was prepared after hearing evidence (the minutes of which are published in Volume II) from the Central Electricity Generating Board, the United Kingdom Atomic Energy Authority and the Department of Energy. Memoranda received from other interested bodies or individuals were also considered and members of the Committee visited fast breeder projects in France, West Germany and Japan. As well as the development of the fast reactors, the economics and timescale were reviewed. The particular case of the fast breeder reactor and proposed fuel reprocessing plant at Dounreay was considered. The main conclusion is that major expenditure on fast reactor programmes can only be justified if there is a potential economic case, i.e. if the fuel cycle costs are lower than for PWRs. This would only be the case if uranium costs increased greatly. It is not considered worthwhile to participate in the European Fast Reactor although this should be reviewed in 1993 and 1997. The Committee agree with the Government's decision to cease funding the PFR in 1994 and endorses the need to regenerate the local economy which will be affected by this decision. (UK)

  7. Risk monitor for unit 3 of the Jaslovske Bohunice V2 nuclear power plant at the full power and for the shut-down reactor

    International Nuclear Information System (INIS)

    The EOOS (Equipment Out Of Service) Monitor is part of the Risk and Reliability Workstation software package developed by EPRI. The software package was provided to the Jaslovske Bohunice NPP and the Slovak Nuclear Regulatory Authority within a contract with the US Department of Energy (DOE). A risk monitor for unit 3 of the Jaslovske Bohunice V2 NPP was developed by integration of a PSA model into the EOOS monitor. The paper describes the monitor and its application to risk monitoring during full power operation and reactor shutdown. (author)

  8. The primary circuit materials properties results analysis performed on archive material used in NPP V-1 and Kola NPP Units 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Kupca, L.; Beno, P. [Nuclear Power Plants Research Institute Inc., Trnava (Slovakia)

    1997-04-01

    A very brief summary is provided of a primary circuit piping material properties analysis. The analysis was performed for the Bohunice V-1 reactor and the Kola-1 and -2 reactors. Assessment was performed on Bohunice V-1 archive materials and primary piping material cut from the Kola units after 100,000 hours of operation. Main research program tasks included analysis of mechanical properties, corrosion stability, and microstructural properties. Analysis results are not provided.

  9. Radwaste Treatment Centre Jaslovske Bohunice

    International Nuclear Information System (INIS)

    In this leaflet the Bohunice Radwaste Treatment Centre (BSC RAO) is presented. BSC RAO is designed to process and treat liquid and solid radwaste, arising from the NPP A-1 decommissioning, from NPPs V-1, V-2, and Mochovce operations, as well as institutional radwaste of diverse institutional (hospitals, research institutes) in the Slovak Republic. Transport, sorting, incineration, compacting, concentration and cementation of radwaste as well as monitoring of emission are described

  10. Lifetime evaluation of Bohunice NPP components

    International Nuclear Information System (INIS)

    The paper discuss some aspects of the main primary components lifetime evaluation program in Bohunice NPP which is performed by Nuclear Power Plant Research Institute (NPPRI) Trnava in cooperation with Bohunice and other organizations involved. Facts presented here are based on the NPPRI research report which is regularly issued after each reactor fuel campaign under conditions of project resulted from the contract between NPPRI and Bohunice NPP. For the calculations, there has been used some computer codes adapted (or made) by NPPRI and the results are just the conclusive and very brief, presented here in Tables (Figures). (authors)

  11. Experience with applying the automated control system to maintenance at the Bohunice nuclear power plant

    International Nuclear Information System (INIS)

    The automated system of maintenance control at the V-1 nuclear power plant at Jaslovske Bohunice uses experience gained with the maintenance of the A-1 nuclear power plant. With regard to the range of work operations, maintenance includes inspection, routine repair, overhaul of equipment and replacement. Also observed is the classification of equipment according to whether it may be repaired without reactor shutdown or whether the reactor will have to be shut down. At present the maintenance of the Jaslovske Bohunice nuclear power plant is being processed by an automated control system into five year variable plans of repairs, annual and monthly plans of repairs, plans of shut-downs and a schedule of unit shutdowns. The repair plan includes over 6000 items. (Z.M.)

  12. 30th and 29th anniversary of reactor accidents in A-1 nuclear power plant Jaslovske Bohunice - radioecological and radiobiological consequences

    International Nuclear Information System (INIS)

    In this paper authors present facts about construction, operation and reactor accidents in A-1 Nuclear Power Plant Jaslovske Bohunice, Slovakia. There was the reactor KS 150 (HWGCR) cooled with carbon dioxide and moderated with heavy water. A-1 NPP was commissioned on December 25, 1972. The first reactor accident happened on January 5, 1976 during fuel loading. Two persons of personal died by suffocation with carbon dioxide. This accident has been not evaluated according to the INES scale up to present time. The second serious accident in A-1 NPP occurred in February 22, 1977 also during fuel loading. This INES level 4 of reactor accident resulted in damaged fuel integrity with extensive corrosion damage of fuel cladding and release of radioactivity into the plant area. The A-1 NPP was consecutively shut down and is being decommissioned in the present time. Both reactor accidents are described in this paper. Some radioecological and radiobiological consequences of accidents and contamination of area of A-1 NPP as well as of Manivier canal and Dudvah River as result of flooding during the decommissioning are presented. (authors)

  13. In-core-sipping in Jaslovske Bohunice

    International Nuclear Information System (INIS)

    The Siemens in-core sipping system has proved to work satisfactorily in the Jaslovske Bohunice Nuclear Power Station. In 1990, Siemens (KWU) installed a new version of the system advanced in the light of past operating experience, in which the rectangular eightfold bell had been replaced by rotationally symmetrical sevenfold bell. The number of failed fuel elements detected in the four generating units of the Jaslovske Bohunice Nuclear Power Station is relatively small, documenting reliable operation of the fuel elements in the WWER-440 reactor. (orig./HP)

  14. Fusion reactor design and technology 1986. V. 1

    International Nuclear Information System (INIS)

    The first volume of the Proceedings of the Fourth Technical Committee Meeting and Workshop on Fusion Reactor Design and Technology organized by the IAEA (Yalta, 26 May - 6 June 1986) includes 36 papers devoted to the following topics: fusion programmes (3 papers), tokamaks (15 papers), non-tokamak reactors and open systems (9 papers), inertial confinement concepts (5 papers), fission-fusion hybrids (4 papers). Each of these papers has a separate abstract. Refs, figs and tabs

  15. Fast breeder reactors: experience and trends. V. 1

    International Nuclear Information System (INIS)

    The IAEA Symposium on ''Fast Breeder Reactors: Experience and Future Trends'' was held, at the invitation of the Government of France, in Lyons, France, on 22-26 July 1985. It was hosted by the French Commissariat a l'energie atomique and Electricite de France. The purpose of the Symposium was to review the experience gained so far in the field of LMFBRs, taking into account the constructional, operational, technological, economic and fuel cycle aspects, and to consider the developmental trends as well as the international co-operation in fast breeder reactor design and utilization. The Symposium presentations were divided into sessions devoted to the following topics: Experience of LMFBR construction and operation and resultant development strategies (6 papers); LMFBR plant startup and commissioning tests and general behaviour (8 papers); Core performance experience for high burnup and core design trends (8 papers); Experience and trends in the LMFBR fuel cycle (4 papers); Core design and behaviour (3 papers); Fuels and materials (7 papers). A separate abstract was prepared for each of these papers

  16. Fuel reliability of Bohunice NPP

    International Nuclear Information System (INIS)

    Paper summarizes experience from last 15 years of operation at NPP Jaslovske Bohunice. During this period, leaking fuel assemblies have had been identified by in-core sipping method and verified by vendor specified canister sipping method. Methodology of operational and outage fuel integrity monitoring is described. Full survey of identified leaking assemblies is given. Fuel failure rates are calculated separately for V-1 (V-230 type) and V-2 (V-213 type) units. Systematic difference - significantly lower fuel failure rate at V-213 units exists for all period investigated. Analysis of potential fuel failure reasons and all related measures (planned and already implemented) are presented. Design, operation and fabrication features have been analyzed with the aim to identify dominant factors contributing to fuel failure. No unambiguous reasons have been found so far. It is believed that there is a superposition of several factors and differences causing higher failure rate at V-230 type units. (author)

  17. Long-term corrosion study at nuclear power plant Bohunice (Slovakia)

    Science.gov (United States)

    Slugen, V.; Lipka, J.; Dekan, J.; Tóth, I.; Smieško, I.

    2010-03-01

    Steam generators of four VVER-440 units at nuclear power plants V-1 and V-2 in Jaslovske Bohunice (Slovakia) were gradually changed by new original "Bohunice" design in period 1994-1998. Corrosion processes before and after these design and material changes in Bohunice secondary circuit were studied using Mössbauer spectroscopy during last 25 years. Innovations in the feed water pipeline design as well as material composition improvements were evaluated positively. Mössbauer spectroscopy studies of phase composition of corrosion products were performed on real specimens scrapped from water pipelines or in form of filter deposits. The corrosion of new feed water pipelines system (from austenitic steel) in combination to innovated operation regimes goes dominantly to magnetite. The hematite presence is mostly on the internal surface of steam generator body and its concentration increases towards the top of the body. In the results interpretation it is necessary to consider also erosion as well as scope and type of maintenance activities. The long-term study of phase composition of corrosion products at VVER reactors is one of precondition for the safe operation over the projected NPP lifetime.

  18. Seismic evaluation and strengthening of Bohunice nuclear power plant structures

    International Nuclear Information System (INIS)

    A seismic assessment and strengthening investigation is being performed for selected structures at the Bohunice V1 Nuclear Power Plant in Slovakia. Structures covered in this paper include the reactor building complex and the emergency generator station. The emergency generator station is emphasized in the paper as work is nearly complete while work on the reactor building complex is ongoing at this time. Seismic evaluation and strengthening work is being performed by a cooperative effort of Siemens and EQE along with local contractors. Seismic input is the interim Review Level Earthquake (horizontal peak ground acceleration of 0.3 g). The Bohunice V1 reactor building complex is a WWER 4401230 nuclear power plant that was originally built in the mid-1970s but had extensive seismic upgrades in 1991. Siemens has performed three dimensional dynamic analyses of the reactor building complex to develop seismic demand in structural elements. EQE is assessing seismic capacities of structural elements and developing strengthening schemes, where needed. Based on recent seismic response analyses for the interim Review Level Earthquake which account for soil-structure interaction in a rigorous manner, the 1991 seismic upgrade has been found to be inadequate in both member/connection strength and in providing complete load paths to the foundation. Additional strengthening is being developed. The emergency generator station was built in the 1970s and is a two-story unreinforced brick masonry (URM) shear wall building above grade with a one story reinforced concrete shear wall basement below grade. Seismic analyses and testing of the URM walls has been performed to assess the need for building strengthening. Required structural strengthening for in-plane forces consists of revised and additional vertical steel framing and connections, stiffening of horizontal roof bracing, and steel connections between the roof and supporting walls and pointing of two interior transverse URM

  19. Coolant technology of water cooled reactors. V. 1: Chemistry of primary coolant in water cooled reactors

    International Nuclear Information System (INIS)

    This report is a summary of the work performed within the framework of the Coordinated Research Programme on Investigations on Water Chemistry Control and Coolant Interaction with Fuel and Primary Circuit Materials in Water Cooled Power Reactors organized by the IAEA and carried out from 1987 to 1991. It is the continuation of a programme entitled Reactor Water Chemistry Relevant to Coolant-Cladding Interaction (IAEA-TECDOC-429), which ran from 1981 to 1986. Subsequent meetings resulted in the title of the programme being changed to Coolant Technology of Water Cooled Reactors. The results of this Coordinated Research Programme are published in four volumes with an overview in the Technical Reports Series. The titles of the volumes are: Volume 1: Chemistry of Primary Coolant in Water Cooled Reactors; Volume 2: Corrosion in the Primary Coolant Systems of Water Cooled Reactors; Volume 3: Activity Transport Mechanisms in Water Cooled Reactors; Volume 4: Decontamination of Water Cooled Reactors. These publications should be of interest to experts in water chemistry at nuclear power plants, experts in engineering, fuel designers, research and development institutes active in the field and to consultants to these organizations. Refs, figs and tabs

  20. Bohunice - information within July 2004

    International Nuclear Information System (INIS)

    In this leaflet results of exploitation of four units of the Bohunice V-1 and V-2 NPPs are presented. The electricity and heat production in July 2004 are reviewed. Within a July 2004 the electricity was produced: 285 GWh (block 1), 292 GWh (block 2), 0 GWh (block 3), 20 GWh (block 4), totally 597 GWh, and 6352 GWh within a January - July 2004. The heat production in July 2004 was 9 417 GJ, and within a January - July 2004 it was produced 941 403 GJ of heat. After enlargement of European Union (EU) by ten new member states on May 1, 2004 the number of nuclear units has been risen by 19 units. 136 nuclear units were in operation in 'old' European Union. The most of nuclear units have been brought by Czech Republic and Slovak Republic (6 operational units, each state); Hungary has brought four units, Lithuania two and Slovenia one nuclear unit. Remaining five countries - Poland, Estonia, Cyprus, Latvia and Malta do not use nuclear energy for electricity production. Nuclear energetics is used in fourteen countries in enlarged European Union. France operates the largest number of nuclear units (59), which generated 77.67 per cent electricity of total French produced electricity in last year. However, France has lasted its dominant position in European Union since May, because two Lithuanian nuclear units generated 79.88 per cent of electricity in last year. In 2003 nuclear units reached 33.1 per cent of electricity generation within European Union. After enlargement of EU in 2004 this share should be raised to 34 per cent

  1. Final results of the gradual reconstruction of Bohunice VI in Slovakia and evaluation of the reconstruction by international missions

    International Nuclear Information System (INIS)

    The gradual reconstruction of the Bohunice V1 nuclear power plant (Slovakia) represents the most extensive reconstruction of a nuclear power plant in operation as implemented worldwide up to now. Extensive reconstruction works in both civil construction and process parts, in instrumentation and control part, and in electric part enhanced both nuclear safety and operational reliability of Bohunice V1 in a significant way.(author)

  2. Metamorphosis of NPP A1, V1, V2

    International Nuclear Information System (INIS)

    In this book the history of construction, commissioning and exploitation of NPP A1, NPP V1 and NPP V2 in Jaslovske Bohunice is presented on documentary photos. Vicinity around of these NPPs is presented, too

  3. Internal communication at Bohunice NPPs

    International Nuclear Information System (INIS)

    Communication is the base of everyday existence of a modern person and every company. It is not easy to work in this area in a changing 'eastern' country. Many tools, which are used are in the mind of people connected with 'propaganda'. I would like to share our experience with you. The goal of an internal communication is to spread and provide continuous current of objective information between the management of Bohunice NPPs and its personnel and between the personnel itself. Communication with the Bohunice NPPs employees helps to get acquainted with their opinions and ideas concerning the subsidiary and nuclear power industry

  4. Safety improvement programme of WWER 440/230 units in Jaslovske Bohunice

    International Nuclear Information System (INIS)

    A brief overview is given of the power sources in Slovakia which include 6 operational reactor units (4 at Jaslovske Bohunice and 2 at Mochovce) and 2 units under construction (at Mochovce). The efforts undertaken in the past 10 years and aimed at upgrading the nuclear safety of the two older (V-230 Soviet type) units at Bohunice are highlighted. The relevant regulatory decisions are dealt with and the measures already carried out are listed. Also characterized are several IAEA international safety assessment missions and safety-aimed meetings which took place in 1998 and 1999 and are of concern to the older Bohunice units. (A.K.)

  5. Verification of RBMK-1500 reactor main circulation circuit model with Cathare V1.3L

    International Nuclear Information System (INIS)

    Among other computer codes, French code CATHARE is also applied for RBMK reactor calculations. In this paper results of such application for Ignalina NPP reactor (RBMK-1500 type) main circulation circuit are presented. Three transients calculations were performed: all main circulation pumps (MCP) trip, trip of one main circulation pump and trip of one main circulation pump without a closure of check valve on the pump line. Calculation results were compared to data from the Ignalina NPP, where all these transients were recorded in the years 1986, 1996 and 1998. The presented studies prove the capability of the CATHARE code to treat thermal-hydraulic transients with a reactor scram in the RBMK, in case of single or multiple pump trips. However, the presented model needs further improvements in order to simulate loss of coolant accidents. For this reason, emergency core cooling system should be included in the model. Additional model improvement is also needed in order to gain more independent pressure behavior in both loops. Also, flow rates through the reactor channels should be modeled by dividing channels into several groups, referring to channel power (in RBMK power produced in a channel, located in different parts of the core is not the same). The point-neutron kinetic model of the CATHARE code is not suitable to predict transients when the reactor is operating at a nominal power level. Such transients would require the use of 3D-neutron kinetics model to describe properly the strong space-time effect on the power distribution in the reactor core

  6. Decommissioning Project of Bohunice A1 NPP

    International Nuclear Information System (INIS)

    The first (pilot) nuclear power plant A1 in the Slovak Republic, situated on Jaslovske Bohunice site (60 km from Bratislava) with the capacity of 143 MWel, was commissioned in 1972 and was running with interruptions till 1977. A KS 150 reactor (HWGCR) with natural uranium as fuel, D2O as moderator and gaseous CO2 as coolant was installed in the A1 plant. Outlet steam from primary reactor coolant system with the temperature of 410 C was led to 6 modules of steam generators and from there to turbine generators. Refueling was carried out on-line at plant full power. The first serious incident associated with refueling occurred in 1976 when a locking mechanism at a fuel assembly failed. The core was not damaged during that incident and following a reconstruction of the damaged technology channel, the plant continued in operation. However, serious problems were occurring with the integrity of steam generators (CO2 gas on primary side, water and steam on secondary side) when the plant had to be shut down frequently due to failures and subsequent repairs. The second serious accident occurred in 1977 when a fuel assembly was overheated with a subsequent release of D2O into gas cooling circuit due to a human failure in the course of replacement of a fuel assembly. Subsequent rapid increase in humidity of the primary system resulted in damages of fuel elements in the core and the primary system was contaminated by fission products. In-reactor structures had been damaged, too. Activity had penetrated also into certain parts of the secondary system via leaking steam generators. Radiation situation in the course of both events on the plant site and around it had been below the level of limits specified. Based on a technical and economical justification of the demanding character of equipment repairs for the restoration of plant operation, and also due to a decision made not to continue with further construction of gas cooled reactors in Czechoslovakia, a decision was made in

  7. Bohunice NPPs - Part of the Slovak's economy (sustainable) development

    International Nuclear Information System (INIS)

    Of the total consumption of electricity in Slovakia, 42% was generated in nuclear power plant units in 1999. Slovakia operates 6 units with a WWER 440 nuclear reactors, 4 of them are at Bohunice site and 2 at Mochovce. The Nuclear Regulatory Authority of SR is not the only regulatory body controlling nuclear activity. Both - the system of nuclear activities regulation in Slovakia as well as the approach to Nuclear Safety enhancement of the operator were positively judged by IAEA and WENRA. In 1993 -Slovakia has accepted the commitments of the UN Convention on Climate Changes, including a reduction of greenhouse gases to 1990 levels by the year 2000. Moreover, as an internal target Slovakia has set the reaching of the ,'Toronto Objective', i.e. 20% reduction in COx emissions through the year 2005 as compared to 1988. Taking into account the actual situation as well as natural conditions for some renewable sources utilisation, the target won't be reached without nuclear energy. The nuclear energy is free of emissions, does not burn oxygen, and with the share of production in Slovakia will remain significant contributor. To the environment protection it contributes also by replacing fossil heat plants with heat delivery for the region. In case of radiological wastes the environment protection is ensured by very strict system of control, evidence, treatment and repository. To conclude, Bohunice NPPs were, are and will remain very important part of the Slovak's economy, creating conditions for its (sustainable) development

  8. Modernization of Nuclear Power Plant V2 Bohunice in Slovak Republic

    International Nuclear Information System (INIS)

    After successful completion of extensive Gradual Reconstruction (1996-2000) of Nuclear Power Plant V1 (2 x VVER440/V230), there started modernisation project of Nuclear Power Plant V2 (2 x VVER440/V213) in the site Jaslovske Bohunice with planned completion in the year 2008. The main goal and priority of NPP V2 modernisation programme is to increase safety and reliability of the operation, but also to create conditions for extension of the operating life and economy improvement of NPP V2 operation. NPP V2 units in Jaslovske Bohunice were commissioned in the year 1984 and 1985. In the year 1997, management of Slovenske Elektrarne approved goals of modernisation programme and safety increasing of NPP V2. At modernisation programme defining, there were taken into consideration results of safety assessment and recommendations for improvement of NPP with VVER 440/V213 processed within the projects IAEA, WANO, VUJE and the other organisations which have had experiences with the operation of NPP with VVER reactors (basic documents: Safety report NPP V2 after 10 years of operation, VUJE, 1993, Safety issue and their ranking for nuclear power plants WWER 440/V213 type, IAEA, 1996, Safety improvements of NPP V2 and design of their solution, VUJE, 1997). Detail range, content and schedule of programme implementation were elaborated by VUJE in the year 2001. VUJE worked out solution designs into the level of project requirements (Conceptual Design) in the document: 'Safety concept for modernisation and safety increasing of NPP V2' Modernisation works are implemented mainly in I and C and electro part, works in nuclear systems and the civil part are implemented in smaller range. Implementation works in modernisation project are realized mainly during planned units outages for refuelling. VUJE as the general designer provides elaboration of design documentation, safety documentation; support of general contractor and it is responsible for overall coordination and functionality

  9. The human factor and the part it plays in failures of the normal operation of water-cooled, water-moderated WWER-440 reactors at the Bohunice nuclear power plant

    International Nuclear Information System (INIS)

    The paper presents the findings of a study of the role of the human factor based on the results of the first four years of operation of the Bohunice B-1 nuclear power plant. It describes the method by which plant personnel are trained and the system of maintaining the level of staff skills. It is expected that there will be an improvement in the quality of personnel training and that an analysis of the role of the human factor will be made in the course of subsequent operation. (author)

  10. Project Management Unit for decommissioning of NPP Bohunice VI (2003-2014)

    International Nuclear Information System (INIS)

    From October 2003 until december 2014 the Consortium consisting of Iberdrola Engineering and Construction (leader). Empresarios Agrupados Internacional, and Indra Sistemas has carried out the project Project Management Unit ((PMU) for the decommissioning of Bohunice V1 NPP (units 1 and 2), type VVER-440/V-230 in Slovakia. during the first phase (2003-2007) EdF was also part of the Consortium. The project is funded by the Bohunice International Decommissioning Support Fund (BIDSF) administered by the RBRD. The main objective of the project is to provide the necessary engineering and resources of project management for planning, execution, management, coordination and monitoring of all tasks in support of the decommissioning. (Author)

  11. Testing of measuring systems TELEPERM-XS and SUGAN at Bohunice NPP during physical start-up tests commissioning in year 2000

    International Nuclear Information System (INIS)

    The paper presents testing methodology of neutron flux measurements systems used standard chains incorporated to the reactor control system and non-standard measuring system, used during start-up tests after refuelling of the reactors. Comparison of both measuring systems is given. Methodology is illustrated on results of measurements performed at Bohunice NPP during reactor start-up tests.(author)

  12. Personnel education and training at Bohunice NPP

    International Nuclear Information System (INIS)

    Procedure for education and training of all the personnel employed at Bohunice Nuclear power plant is presented in detail describing the training system structure, kinds of training, staff members qualification development, short term and long term tasks needed to assure attaining the training objectives. The proposed Staff Members Lifetime education implementation project contains basic starting points, measures to be implemented by 1998. It was prepared on the basis of a primary analysis which confirmed the existing need for implementing the lifetime education system

  13. Radiological characterisation of V1 NPP technological systems and buildings - Activation

    International Nuclear Information System (INIS)

    V1 NPP at Jaslovske Bohunice site has been finally shutdown after 28 years of successful operation in 2006 (Unit 1) and 2008 (Unit 2). At present, both units are finally shutdown and since July 2011 under decommissioning license. The preparation of V1 NPP decommissioning has been supported and partly financed by the Bohunice International Decommissioning Support Fund (BIDSF), under the administration of the European Bank for Reconstruction and Development. From 06/2008 to 12/2011 AMEC Nuclear Slovakia, together with partners STM Power and EWN GmbH, carried out BIDSF B6.4 project - Decommissioning database development (DDB). The main purpose of the B6.4 project was to develop a physical and radiological inventory database to support V1 NPP decommissioning process planning and performance. One of the specific deliverable tasks within the B6.4 project was deliverable D12 - Characterization of activated equipment and civil structures based on measurement, sampling and analyses performed on the samples. The scope of deliverable services within D12 task consisted of: 1. Categorization of activated components ; 2. Development of single working programs for their radiological monitoring and sampling ; 3. Preparation of sampling device and revision of all handling equipment; 4. Dose rate monitoring and sampling of: - Civil structures from reactors shaft on both units ; - Components placed in HLW storage, (so called 'Mogilnik') - connection rods, absorbers ; of control rod assemblies and neutron flux measurement channels ; - Reactor pressure vessel and shielding assemblies at both units of V1 NPP, reactor; internals from Unit 2 of V1 NPP; 5. Analysis of samples ; 6. Determination of radiological inventory ; 7. Import of radiological data for activated components into DDB. During sampling, mainly remotely controlled sampling device and radiation resistant camera with LED lightening for visual checking of all performed activities was used. In total, 125 samples have been taken

  14. ESTE EMO and ESTE EBO - emergency response system for NPP Mochovce and NPP Bohunice V-2

    International Nuclear Information System (INIS)

    Programs ESTE EMO and ESTE EBO are emergency response systems that help the crisis staff of the NPP in assessing the source term (predicted possible release of radionuclides to the atmosphere ), in assessing the urgent protective measures and sectors under threat, in assessing real release (symptoms of release really detected and observed), in calculating radiological impacts of real release, averted or avertable doses, potential doses and doses during transport or evacuation on specified routes. Both systems serve as instruments in case of severe accident (DBA or BDBA) at NPP Mochovce or NPP Bohunice, accidents with threat of release of radioactivity to the atmosphere. Systems are implemented at emergency centre of Mochovce NPP and Bohunice NPP and connected online to the sources of technological and radiological data from the reactor, primary circuit, confinement, secondary circuit, ventilation stack, from the area of NPP (TDS 1) and from the emergency planning zone (TDS 11). Systems are connected online to the sources of meteorological data, too. (authors)

  15. Decommissioning database of V1 NPP

    International Nuclear Information System (INIS)

    Since 2001, the preparation of V1 NPP practical decommissioning has been supported and partly financed by the Bohunice International Decommissioning Support Fund (BIDSF), under the administration of the European Bank for Reconstruction and Development. AMEC Nuclear Slovakia, together with partners STM Power and EWN GmbH, have been carrying out BIDSF B6.4 project - Decommissioning database development (June 2008 until July 2010). The main purpose of the B6.4 project is to develop a comprehensive physical and radiological inventory database to support RAW management development of the decommissioning studies and decommissioning project of Bohunice V1 NPP. AMEC Nuclear Slovakia was responsible mainly for DDB design, planning documents and physical and radiological characterization including sampling and analyses of the plant controlled area. After finalization of all activities DDB includes over 75.000 records related to individual equipment and civil structures described by almost 3.000.000 parameters. On the basis of successful completion of the original contract the amendment was signed between JAVYS and Consultant's Consortium related to experimental characterization of NPP activated components. The works within this amendment have been still running. (authors)

  16. Gas-cooled reactor programs. Fuel-management positioning and accounting module: FUELMANG Version V1.11, September 1981

    International Nuclear Information System (INIS)

    This report documents the code module FUELMANG for fuel management of a reactor. This code may be used to position fuel during the calculation of a reactor history, maintain a mass balance history of the fuel movement, and calculate the unit fuel cycle component of the electrical generation cost. In addition to handling fixed feed fuel without recycle, provision has been made for fuel recycle with various options applied to the recycled fuel. A continuous fueling option is also available with the code. A major edit produced by the code is a detailed summary of the mass balance history of the reactor and a fuel cost analysis of that mass balance history. This code is incorporated in the system containing the VENTURE diffusion theory neutronics code for routine use. Fuel movement according to prescribed instructions is performed without the access of additional user input data during the calculation of a reactor operating history. Local application has been primarily for analysis of the performance of gas-cooled thermal reactor core concepts

  17. Gas-cooled reactor programs. Fuel-management positioning and accounting module: FUELMANG Version V1. 11, September 1981

    Energy Technology Data Exchange (ETDEWEB)

    Medlin, T.W.; Hill, K.L.; Johnson, G.L.; Jones, J.E.; Vondy, D.R.

    1982-01-01

    This report documents the code module FUELMANG for fuel management of a reactor. This code may be used to position fuel during the calculation of a reactor history, maintain a mass balance history of the fuel movement, and calculate the unit fuel cycle component of the electrical generation cost. In addition to handling fixed feed fuel without recycle, provision has been made for fuel recycle with various options applied to the recycled fuel. A continuous fueling option is also available with the code. A major edit produced by the code is a detailed summary of the mass balance history of the reactor and a fuel cost analysis of that mass balance history. This code is incorporated in the system containing the VENTURE diffusion theory neutronics code for routine use. Fuel movement according to prescribed instructions is performed without the access of additional user input data during the calculation of a reactor operating history. Local application has been primarily for analysis of the performance of gas-cooled thermal reactor core concepts.

  18. Radiation monitoring and free release of materials from V1 NPP decommissioning

    International Nuclear Information System (INIS)

    Dismantling and decommissioning of nuclear facilities is an important part of the VF, a.s. business activities. VF a.s. is taking part in following important tasks during dismantling and decommissioning activities: - Fragmentation a decontamination; - Radiation monitoring and radiation protection; - Release of materials to the environment. On the 20th July, 2011 V1 NPP was officially shutdown and V1 entered the decommissioning phase. Bohunice International Decommissioning Support Fund (BIDSF) for shutdown of both units of V1 NPP in Jaslovske Bohunice was established. VF is responsible for major tasks being part of the following V1 NPP BIDSF Projects Project group C - Projects related to radioactive waste management. The BIDSF project is described.(author)

  19. Information letter 2. Information about operation of plants SE-NPP Bohunice and SE-VYZ during February 2005

    International Nuclear Information System (INIS)

    In this leaflet results of exploitation of four units of the Bohunice V-1 and V-2 NPPs are presented. The electricity and heat production in February 2005 are reviewed. Within a February 2005 the electricity was produced: 217 GWh (block 1), 281 GWh (block 2), 277 GWh (block 3), 282 GWh (block 4), totally 1057 GWh, and 2271 GWh within a January - February 2005. The heat production in February 2005 was 266 506 GJ, and within a January - February 2005 it was produced 531 849 GJ of heat. On February 17 Slovak minister of economy Pavol Rusko and general director of ENEL Paolo Scaroni signed the agreement on acquisition of 66 per cent of Slovenske elektrarne (SE) by Italian ENEL for 840 million Eur. SE has capacity of around 7 GW (83 per cent of total Slovakian capacity). In 2004 SE generated 26 TWh of electricity. Processing and storage of radioactive wastes in Decommissioning of Nuclear Installations and Spent Fuel and Rad-waste Management (SE-VYZ) is presented. Since beginning of this year 58 fibre-concrete containers have been filled up in Bohunice processing centre of radioactive wastes. Twenty-three pieces of fibre-concrete containers were processed into fibre-concrete containers in Bohunice processing centre of radioactive wastes (BSC RAO) in February 2005. Twenty fibre-concrete containers were stored into Republic storage of radioactive wastes (RU RAO). Total number in RU RAO reached 830 pieces of fibre-concrete containers, which represent 11.53 per cent of storage capacity (7200 containers). Bohunice processing centre of radioactive wastes was put into active operation just before five years

  20. The most extensive reconstruction of nuclear power plant with VVER 440/V230 reactor

    International Nuclear Information System (INIS)

    The nuclear power plant V-1 Bohunice consists of two VVER-440 units with V-230 reactors. Unit 1 was commissioned in 1978 and Unit 2 in 1980. Large experience and knowledge from the operation of previous units with V-230 reactors were incorporated into the V-1 design, which resulted in a higher level of safety and operational reliability of these units. The Siemens company which won an international bidding process developed these basic goals for the Gradual Upgrading into the so called Basic Engineering (BE). For the implementation of the Gradual Upgrading in line with the BE, Rekon consortium was established consisting of Siemens and VUJE. The implementation of the Gradual Upgrading is scheduled for the time period of 1996 - 2000. Siemens was responsible for the upgrading strategy - based on the approved results of the basic engineering phase and the PSAR, the engineering and realization of all I and C improvements, and also for the seismic upgrade. VUJE's responsibility covered the detailed engineering and implementation of mechanical, electrical and civil part of upgrading measures as well as overall organisation and evaluation of verification tests. The consortium awarded contracts for final planning and design, installation services and commissioning to other Slovakian subcontractors in order to ensure the largest possible local content. The gradual reconstruction of the V-1 Bohunice with V230 reactors represents a comprehensive reconstruction of safety-related systems and equipment. Following its completion, the units will be operated with a safety level accepted internationally. (author)

  1. Response of native flora to inducible genotoxic damage from increased radioactivity around NPP Jaslovske Bohunice, Slovakia

    International Nuclear Information System (INIS)

    It is not generally known that the first serious failure of nuclear power plant (NPP) technology with loss of human lives occurred in NPP Jaslovske Bohunice (Czechoslovakia) in January 1976. A year later the second accident finally broken reactor A1 with large radioactive contamination. This material was later (in 1980) washed into the nearby drainage by the heavy rain. In cleaning procedure, the contaminated soil particles contaminated the slopes of the drainage. These spots have the shape of 'blurs' about 15 cm wide with a scale of contamination from 0,067; 0,15; 2,38; 9,5; 45.5 up to 322 kBq/kg 137Cs. The research was done in cooperation with the Institute of Tumorbiology, University of Vienna, within the grant Action Austria - Slovak Republic. Details of radioactivity at the area were obtained thanks to the Research Institute of the Nuclear Energy in Trnava, Slovakia. In our ten years long-term study of contaminated soil around nuclear power plant (NPP) Jaslovske Bohunice 24 species of local flora were used to show impact of these accidents. The 19 km long banks of the Jaslovske Bohunice NPP waste water recipient has been identified as contaminated by 137Cs. In total, more than 67,000 m2 of river banks have been found as being contaminated at levels exceeding 1 Bq 137Cs/g of soil. Used phytotoxic and cytogenetic -in situ' tests were extended by analyses of pollen grains. Although the dose of some samples of radioactive soil was relatively high (322 kBq kg-1) no any significant impact on the biological level of tested wild plant species was observed. Possible explanation (such as adaptation and resistance) is discussed. (author)

  2. Gradual reconstruction of the V-1 NPP

    International Nuclear Information System (INIS)

    The background and objectives of the gradual reconstruction of the Bohunice V-1 nuclear power plant are described in detail, including the pre-design and design preparation activities, tender procedures, aims, safety analyses, and technological coverage of the project. The following systems are included in the reconstruction project: (1) safety valves and pressurizer relief line system; (2) steam generator super emergency feedwater system; (3) system of steam dump valves to the atmosphere; (4) external power supply system for plant home consumption; (5) emergency core cooling system and spray system; (6) fire prevention systems; (7) electrical systems; (8) instrumentation and control systems; (9) system of accident location in the hermetic zone; (10) hermetic zone leaktightness and integrity, filtered venting system; (11) hermetic zone strength; (12) vital technological water system; (13) ventilation and air conditioning systems; and (14) seismic strengthening of the facilities. Each of the items is described in detail. (P.A.)

  3. Risk-informed decision making during Bohunice NPP safety upgrading

    International Nuclear Information System (INIS)

    The paper summarizes some facts of risk-informed regulation developments within UJD regulatory environment. Based on national as well as international operating experience and indications resulted from PSA, Nuclear Regulatory Authority of the Slovak Republic (UJD) since its constituting in 1993 has devoted an effort to use PSA technology to support the regulatory policy in Slovakia. The PSA is considered a complement, not a substitute, to the deterministic approach. Suchlike integrated approach is used in decision making processes and the final decision on scope and priorities is based on it. The paper outlines risk insights used in the decision making process concerning Bohunice NPP safety upgrading and focuses on the role of PSA results in Gradual Reconstruction of Bohunice VI NPP. Besides, two other examples of the PSA results application to the decision making process are provided: the assessment of proposal of modifications to the main power supply diagram (incorporation of generator switches) and the assessment of licensee request for motor generator AOT (Allowable Outage Time) extension. As an example of improving support of Bohunice V-2 risk-informed operations, concept of AOT calculations and Bohunice V-2 Risk Monitor Project are briefly described. (author)

  4. Safety culture at the Bohunice nuclear power plant

    International Nuclear Information System (INIS)

    The approach of the Bohunice nuclear power plant to the safety culture issue is highlighted. Activities performed so far at the plant to improve the plant safety culture with a view to enhancing the awareness of each employee and thus to minimize the effect of the human factor on the evolution of incidents and accidents at the plant are described. (author)

  5. Regulatory involvement in IandC systems upgrading on WWER 440 type reactors in the Slovak Republic

    International Nuclear Information System (INIS)

    An overview is given of the recommendations and regulations concerning IandC systems of nuclear power plants with WWER-440 reactors in the Slovak Republic, and of the relevant involvement of regulatory bodies. The issues included in regulatory decrees and pertaining to the safety aspects of IandC systems are mentioned point by point, with emphasis put on the upgrading of the systems. The power plants covered include the Bohunice V-1 and V-2 plants and the Mochovce-1 and Mochovce-2 units. (A.K.)

  6. Nuclear data for reactors. Proceedings of a conference on nuclear data - microscopic cross-sections and other data basic for reactors. V. 1

    International Nuclear Information System (INIS)

    Proceedings of a conference organized by the IAEA and held in Paris, 17-21 October 1966, at the invitation of the French Government and the French Atomic Energy Commission. The meeting was attended by 213 participants from 24 countries and 4 international organizations. The main theme of the Conference was the discussion of neutron cross-sections and other neutron data with regard to their use for nuclear reactor calculations, emphasizing the roles of the compiler and the evaluator in this connection. Contents: (Vol.1) Keynote address; Nuclear data requirements (4 papers); Cross-section and resonance parameters of non-fissile nuclides in the resonance energy region (13 papers); Statistical properties of resonance parameters (8 papers); (n,p), (n,α), (n,2n)-reactions, etc. and inverse reactions (5 papers); Cross-sections and constants used as standards (7 papers); Neutron cross-sections above the resonance energy region (13 papers); Neutron radiative capture (16 papers); (Vol.II) Cross-sections and parameters of fissile nuclides (23 papers); Comparison of fission cross-sections in the resonance energy region (3 papers); Neutron data evaluation (12 papers); International co-operation in the field of nuclear data (1 paper); Panel discussion. Of the 106 papers contained in these Proceedings, 83 are published in full with abstracts and 23 are presented by title and abstract only. Each paper is in its original language (69 English, 19 French and 18 Russian), the abstracts being in English and the original language if this is not English. Discussions are in English. (author)

  7. Seismic and geological conditions at the Bohunice NPP site

    International Nuclear Information System (INIS)

    The paper brings basic information on geological and seismic characteristics of the site of NPP Jaslovske Bohunice, Slovakia. Western Carpathians and Trnava, bay geological properties are briefly introduced. The most important macroseismic data and data obtained from field measurements are analysed. Main features of the expected strong seismic motion are discussed. The attention is devoted to local soil characteristics just under the site of NPP. (author)

  8. Termination of exploitation of V 1 NPP - BIDSF projects

    International Nuclear Information System (INIS)

    In this paper the interview with engineer Peter Hlbocky, director of division of the Project of decommissioning of V 1 Nuclear Power Plant in Jaslovske Bohunice is presented. Project Manager Unit (PMU) was formed on the basis of directive of the General Director of the Slovenske elektrarne, a.s. The Director of the Division of decommissioning of the V 1 NPP and at the same time the Main manager of the PMU is engineer Peter Hlbocky. On this project participate 19 employees of the Slovenske elektrarne, a. s. (SE), 6 abroad employees of the consortium IBERINCO, 15 employees of the VUEZ and 25 abroad employees on the detached place of work in the Spain and France

  9. MELCOR Comparative Analyses of Severe Accident of Medium LOCA for the NPP V2 Bohunice

    International Nuclear Information System (INIS)

    This paper presents the results of safety analysis of a medium LOCA (break size 100 mm in cold leg) for the V2 Bohunice nuclear power plant (VVER-440/V-213), and compares the results calculated by various computer codes (MELCOR, MAAP, RELAP/SCADAP). The analysis is performed within the SWISSLOVAK project by the safety analysis group at the Nuclear Regulatory Authority of the Slovak Republic. The medium LOCA accident is combined with station blackout scenario which leads to the core uncovery and meltdown of the reactor core. The core meltdown is followed by the core relocation to the lower plenum, heat up of the reactor pressure vessel lower head, failure of the lower head, and debris ejection into the reactor cavity. The time of key events calculated by various computer codes is similar. The start of core melt is predicted within 0.8 to 1.08 hours and the reactor pressure vessel lower head failure is predicted within 4.1 to 6.3 hours since the initiation of the accident. A substantial release of noble gases to the environment through the permanent containment leakage is calculated. The compartmentalization of the containment and the presence of the bubble condenser affect the release of the fission products. (author)

  10. Modernization and safety improvement project of the NPP V-2 Jaslovske Bohunice

    International Nuclear Information System (INIS)

    The contribution deals with form, present state and results of Nuclear Power Plants Research Institute (the Slovak acronym is VUJE - Vyskumny Ustav Jadrovych Elektrarni) participation in the NPP V-2 Jaslovske Bohunice Modernization and Safety Improvement Project. Short description of VUJE history, activity and results is also done as well as NPPs Jaslovske Bohunice characterization. (authors)

  11. Nomogram of economic efficiency of extending the life of the V-1 nuclear power plant

    International Nuclear Information System (INIS)

    The evaluation was processed of the economic efficiency of extending the life of the V-1 nuclear power plant in Jaslovske Bohunice. The power plant is expected to be shut down for reconstruction in 1995, i.e., in its 16th year in operation. The evalulation considered reconstruction within a 2 to 5 years' period, the costs at 6 to 12 thousand million crowns and decommissioning between the years 2005 to 2015. The results are processed in a nomogram of specific annual updated costs for supplied electric power. (Z.M.). 2 figs., 1 tab., 2 refs

  12. Chemistry monitoring and diagnostic system at NPP Jaslovske Bohunice

    International Nuclear Information System (INIS)

    This paper provides a description of water chemistry monitoring and diagnostic system installed at Slovak NPP Jaslovske Bohunice. System has complex architecture and covers laboratory data, chemistry and radiochemistry on-line monitoring data, process data acquisition and processing and diagnostics. Pre-filtered data from process computer and chemistry on-line monitors are recorded together with laboratory data in the ORACLE-based information system CHEMIS with many presentation and processing features. Brief information is given about the basic features of a newly developed diagnostic system for early detection and identification of anomalies incoming in the water chemistry regime of the primary and secondary circuit of VVER-440 type unit. This system, called SACHER (System of Analysis of Chemical Regime) has been installed within the major modernization project at the NPP Bohunice in the Slovak Republic. System SACHER has been developed fully in MATLAB environment. Diagnostic system works exclusively with available on-line data as an operation personnel support application allowing effective response to adverse chemistry events/trends. The availability of prompt information about the chemical conditions of the primary and secondary circuit is very important in order to prevent the undue corrosion and deposit build-up processes within the plant systems. The typical chemical information systems that exist and work at the NPPs give the user values of the measured quantities together with their time trends and other derived values. It is then the experienced user's role to recognize the situation the monitored process is in and make the subsequent decisions and take the measures. The SACHER system, based on the computational intelligence techniques, inserts the elements of intelligence into the overall chemical information system. It has the modular structure with the following most important modules: - normality module- its aim is to recognize that the process

  13. Analysis of Steam Generators Corrosion Products from Slovak NPP Bohunice

    Directory of Open Access Journals (Sweden)

    Jarmila Degmová

    2012-01-01

    Full Text Available One of the main goals of the nuclear industry is to increase the nuclear safety and reliability of nuclear power plants (NPPs. As the steam generator (SG is the most corrosion sensitive component of NPPs, it is important to analyze the corrosion process and optimize its construction materials to avoid damages like corrosion cracking. For this purpose two different kinds of SGs and its feed water distributing systems from the NPP Jaslovske Bohunice were studied by nondestructive Mössbauer spectroscopy. The samples were scraped from the surface and analyzed in transmission geometry. Magnetite and hematite were found to be the main components in the corrosion layers of both SGs. Dependant of the material the SG consisted of, and the location in the system where the samples were taken, the ratios between magnetite and hematite and the paramagnetic components were different. The obtained results can be used to improve corrosion safety of the VVER-440 secondary circuit as well as to optimize its water chemistry regime.

  14. BIDSF Project B6.4.Decommissioning database of V1 NPP

    International Nuclear Information System (INIS)

    Since 2001, the preparation of V1 NPP practical decommissioning has been supported and partly financed by the Bohunice International Decommissioning Support Fund (BIDSF), under the administration of the European Bank for Reconstruction and Development. AMEC Nuclear Slovakia, together with partners STM Power and EWN GmbH, have been carrying out BIDSF B6.4 project - Decommissioning database development (June 2008 until July 2010). The main purpose of the B6.4 project is to develop a comprehensive physical and radiological inventory database to support RAW management development of the decommissioning studies and decommissioning project of Bohunice V1 NPP. AMEC Nuclear Slovakia was responsible mainly for DDB design, planning documents and physical and radiological characterization including sampling and analyses of the plant controlled area. After finalization of all activities DDB includes over 75.000 records related to individual equipment and civil structures described by almost 3.000.000 parameters. On the basis of successful completion of the original contract the amendment was signed between JAVYS and Consultant's Consortium related to experimental characterization of NPP activated components. The works within this amendment have been still running. (authors)

  15. Monitoring of water level inside reactor pressure vessel

    International Nuclear Information System (INIS)

    Up to the TMI accident the water level inside the pressurizer was used to monitor the water inventory inside the primary cooling system of pressurized water reactors. The TMI accident showed that this was not a reliable measurement for the reactor coolant inventory inside the reactor pressure vessel. For this reason there was a demand for a measurement of the water level inside the RVP, independent from the existing one inside the pressurizer and with a diverse measuring method. For WWER reactors a new level measurement system was developed to monitor the water level inside the reactor pressure vessel by means of the KNITU, resp. KITU level probe which meet all the mentioned engineered safeguards and geometric and constructive requirements. First backfitting s of the new level measurement system in the WWER s 440 in Bohunice V1 (Slovakia), unit 1 (1998) and unit 2 (2000), Novovoronezh (Russia), unit 4 (1999) and Kola (Russia), unit 1 and unit 2 (1999) show very good operational results. (Authors)

  16. Eco information 5. Influence of operation of the plants Jadrova vyradovacia spolocnost, a.s., on the environment, locality of Bohunice, within May 2013

    International Nuclear Information System (INIS)

    In this leaflet the results of monitoring of chemical gaseous and liquid effluents into the Vah River and Dudvah River as well as of radiation monitoring of Bohunice V1 NPP, Interim Spent Fuel Storage (MSVP), Bohunice Radioactive Waste Processing Centre (VK808 - BSC), The Main Production Unit (VK 46A - HVB) and Bitumenation Lines (VK 46B - BL) are presented. The radioactive effluents into atmosphere within January - May 2013 (for NPP V1, MSVP, BSC, HVB and BL, respectively) were: 0.138 MBq (0.000% of AL) for V1, 0.194 MBq (0.065 of AL) for MSVP, 0.192 MBq (0.136% of AL) for BSC, 0.470 MBq (0.071% of AL) for HVB and 0.168 MBq (0.119% of AL) for BL of aero-soles. The radioactive effluents into atmosphere and hydrosphere within a May 2013 for NPP V1, MSVP, and VK 808 BSC, respectively, were: 0.024 MBq (V1), 0.055 MBq (VK MSVP), 0.070 MBq (VK 808 BSC), 0.074 MBq (VK 46A) and 0.011 MBq (VK 46B) of aero-soles into atmosphere; 1.249 MBq (V1 and MSVP) and 6.744 MBq (TSU RAO and NPP A1) of corrosive and fission products, and 5.723 GBq (V1 and MSVP) and 5.744 GBq (TSU RAO and NPP A1) of tritium into the Vah River and 0.000 GBq (V1 and MSVP) and 0.000 MBq (TSU RAO and NPP A1) of corrosive and fission products and 0.000 GBq of tritium (V1) and 0.000 GBq of tritium (TSU RAO and NPP A1) into the Dudvah River). For the period January - May 2013 these radioactive effluents into recipient of Vah River represent for corrosive and fission products 5.653 MBq (0.043% of AL for V1 and MSVP) and 34.953 MBq (0.291% of AL for TSU RAO and MSVP); and for tritium it is 8.397 GBq (0.420% of AL) for V1 and MSVP, and 31.661 GBq (0.317% of AL) for TSU RAO and NPP A1 (into the Vah River) and for corrosive and fission products 0.000 MBq (V1 and MSVP) and 0.000 MBq (TSU RAO and NPP A1) (0.000% of AL) and 0.000 GBq (0.000% of AL) for V1 and MSVP and 0.000 GBq (0.000% of AL) (TSU RAO and NPP A1) of tritium (into the Dudvah River). Chemical effluents are reported, too.

  17. The common project for completion of Bubbler Condenser Qualification (Bohunice, Mochovce, Dukovany and Paks NPPs)

    International Nuclear Information System (INIS)

    Described is the common project for completion of bubbler condenser qualification for nuclear power plants in Bohunice, Mochovice, Dukovany and Paks. Functionality of the bubbler condenser was elaborated during the simulation of the main steam line brake, medium break and small break LOCA. On this basis the appropriate operation of bubbler condenser containment under accident conditions can be positively confirmed

  18. Intercomparison of liquid metal fast reactor seismic analysis codes. V.1: Validation of seismic analysis codes using reactor core experiments. Proceedings of a research co-ordination meeting held in Vienna, 16-17 November 1993

    International Nuclear Information System (INIS)

    The Research Co-ordination Meeting held in Vienna, 16-17 November 1993, was attended by participants from France, India, Italy, Japan and the Russian Federation. The meeting was held to discuss and compare the results obtained by various organizations for the analysis of Italian tests on PEC mock-up. The background paper by A. Martelli, et al., Italy, entitled Fluid-Structure Interaction Experiments of PEC Core Mock-ups and Numerical Analysis Performed by ENEA presented details on the Italian PEC (Prova Elementi di Combustibile, i.e. Fuel Element Test Facility) test data for the benchmark. Several papers were presented on the analytical investigations of the PEC reactor core experiments. The paper by M. Morishita, Japan, entitled Seismic Response Analysis of PEC Reactor Core Mock-up, gives a brief review of the Japanese data on the Monju mock-up core experiment which had been distributed to the participating countries through the IAEA. Refs, figs and tabs

  19. Programmes design for Bohunice NPP personnel other than control room operators

    International Nuclear Information System (INIS)

    This paper deals with project development of training programmes for non-licenced NPP personnel-masters, field operators, maintenance and technical supporting personnel. The programme development focuses on the part stage and on the job training at NPP. Bohunice NPP belongs to plants with higher specific number of personnel per installed power capacity. This factor also influenced the choice of programmes design. Undermentioned procedure is one of various approaches to SAT exploitation for training programmes design. (author)

  20. Radiological characterisation on V1 NPP technological systems and buildings - Contamination

    International Nuclear Information System (INIS)

    Since 2001, the preparation of V1 NPP practical decommissioning has been supported and partly financed by the Bohunice International Decommissioning Support Fund, under the administration of the European bank for Reconstruction and development. AMEC Nuclear Slovakia, together with partners STM Power and EWN GmbH, performed BIDSF B.4 project - Decommissioning database development. The main purpose of the B6.4 project was to develop a comprehensive physical and radiological inventory database to support RAW management development of the decommissioning studies and decommissioning project of Bohunice V1 NPP. AMEC Nuclear Slovakia was responsible mainly for DDB design, planning documents and physical and radiological characterization including sampling and analyses of the plant controlled area. The objective of V1 NPP radiological characterization was summarisation of sampling and analyses results, description of methodology used for radiological characterization and determination of the V1 NPP radiological inventory. Results of the characterization survey included the identification and distribution of contamination in buildings, structures, and other site facilities or other impacted media. The characterization survey clearly identified those portions of the site that have been affected by site activities and are contaminated. The survey also identified the portions of the site that have not been affected by these activities and can be marked as 'not impacted'. Radiological data have been presented also on the basis of index RAI level, where 5 radiological classes have been defined. On the basis of sampling and analyses results following radiological parameters have been assigned to all impacted components and civil structures included in DDB: dose rate in contact, dose rate in distance 1 m, external surface contamination, internal surface contamination and volume/mass contamination. Each room in controlled area has been described by following radiological parameters

  1. Core monitoring and surveillance of VVER-440 type reactors in the Czech Republic and Slovak Republic

    International Nuclear Information System (INIS)

    The SCORPIO-VVER reactor core monitoring system is an advanced redundant software system without actuating members falling in the BT3 class which has been installed at the four Dukovany reactor units and at two units of the Slovak Jaslovske Bohunice V2 NPP. The system is described in detail and its history and experience gained at Dukovany are highlighted. (orig.)

  2. Thickness measurement of A-1 reactor caisson tube walls

    International Nuclear Information System (INIS)

    The equipment is described of measuring the thickness of caisson pipes built in the Bohunice A-1 reactor. The pulse-type ultrasonic thickness gauge is based on the reflection method using the double probe. The measurement accuracy is 0.1 mm. (J.B.)

  3. Measurement and evaluation with control computer of reactor core temperature field

    International Nuclear Information System (INIS)

    A modular system is suggested of monitoring the temperature field of the WWER reactor core. Standard measurements were completed with specified measurements and evaluation of coolant heating, with tests of functionality of measuring chains for coolant temperature at the fuel assembly outlet, changes in the offset of the thermocouple cold ends and with the evaluation of thermal and hydraulic characteristics of the core and of the primary circuit. Experience is presented with the application of this system based on the hardware and software of the RPP-16S control and computer system of the first and second units of the Bohunice V-1 nuclear power plant. Described are the structure of computer subsystems, the design of algorithms for data acquisition, testing of the credibility of temperatures measured with thermocouples, the processing of measured values and the algorithm for reactor heating computations. The system has been proven, and specified measurements made it possible to maintain a more stable and more accurate thermal output of the reactor. (M.D.)

  4. Information about influence of the Bohunice V-2 NPP on the environment, August 2008

    International Nuclear Information System (INIS)

    In this paper results of monitoring of chemical gaseous and liquid effluents into the rivers Vah River as well as of radiation monitoring of Bohunice V-2 NPP are presented. The radioactive effluents into atmosphere within August 2008 were: 2.72 MBq of aerosols, 0.052 MBq of of iodine-131, and 537 GBq of rare gases. For the period January - August 2008 these radioactive effluents into recipient of Vah River represented 6.66 MBq (0.318% of annually limit (AL)) of aero-soles; 0.318 MBq (0.00049% of AL) of iodine-131 and 3341 GBq (0.172% of AL) of rare gases. The radioactive effluents into Vah River recipient within August 2008 were: 968.78 GBq of tritium and 1.35 MBq of corrosive and fission products. For the period January - August 2008 these radioactive effluents into Vah River recipient represented 3,233.51 GBq (16.1675% of AL) of tritium, and 13.50 MBq (0.104% of AL) of corrosive and fission products. Average dose equivalents rate for the villages in surroundings of the Bohunice V-2 NPP for the period from July 31 to September, 2008 are published. Chemical effluents are also reported

  5. Environment monitoring and residents health condition monitoring of nuclear power plant Bohunice region

    International Nuclear Information System (INIS)

    The report contents final environment evaluation and selected characteristic of residents health physics of nuclear power plant Bohunice region. Evaluated data were elaborated during analytical period 1993-1997.Task solving which results are documented in this final report was going on between 1996- 1998. The report deals in individual stages with the following: Information obtaining and completing which characterize demographic situation of the area for the 1993-1997 period; Datum obtaining and completing which contain selected health physics characteristics of the area residents; Database structures for individual data archiving from monitoring and collection; Brief description of geographic information system for graphic presentation of evaluation results based on topographic base; Digital mapping structure description; Results and evaluation of radionuclide monitoring in environment performed by Environmental radiation measurements laboratory by the nuclear power plant Bohunice for the 1993-1997 period. Demographic situation evaluation and selected health physics characteristics of the area of nuclear power plant residents for the 1993-1997 period are summarized in the final part of the document. Monitoring results and their evaluation is processed in graph, table, text description and map output forms. Map outputs are processed in the geographic information system Arc View GIS 3.0a environment

  6. Bohunice NPP experience with SARs and Safety Analyses. TM on Comparative Analysis of Assumptions, Models and Results of AA included in SAR. IAEA RER/9/070

    International Nuclear Information System (INIS)

    guidelines, as well as all available guidelines issued by the IAEA and Regulatory authority gradually applied. The methodologies is 'fine tuned' in the Bohunice V-1 safety upgrading programme, including design analyses and licensing analyses. The reasons for in-house development of databases are unavailability of reliable data for the analysts, absence of some data in the plant documentation. The necessity for systematic identification of experiments or sources of data which can be collected only in specific regimes of the plant and duplication of efforts in the past

  7. 2007 year - annual impacts of effluents in routine releases to the atmosphere and to the hydrosphere from NPP Bohunice V-2 evaluated by the code ESTE AI

    International Nuclear Information System (INIS)

    Annual impacts of Bohunice V -2 operation caused by effluents in routine releases during the year 2007 were calculated and evaluated first time with the help of completely new program - ESTE AI. Program is approved by the 'Public Health Authority of the Slovak Republic' and since January 2008 is used as legal instrument by Slovenske elektrarne a.s., NPP Bohunice. In this poster presented are annual effluents to the atmosphere and to the hydrosphere from Bohunice V-2 NPP. Presented, analyzed and discussed are main results of 2007 impacts evaluation. (authors)

  8. Planning for environmental restoration of the contaminated banks near NPP Bohunice

    International Nuclear Information System (INIS)

    The 18 km long banks of the Bohunice NPP waste water recipient are contaminated by cesium-137 as a result of two accidents on the CO2 cooled NPP A1 unit in 1976 and 1977. Since 1992, all he contaminated waste waters dumping from NPP Bohunice has been carried out directly to the Vah River through a specially constructed 15 km long pipeline. The final extent of contamination in the Bohunice site is represented. The overall contaminated area in this site with cesium-137 activity above 1 Bq/g of soil is about 67000 m2 and thus, the corresponding volume of top 20 cm thick soil layer is about 13000 m3. For optimizing less costly remedial measures (warning signs...) an agreed scenario with a pre-estimated factor factor collective dose 2.10-7 man.Sv.y-1/(m2.Bq137Cs.g-1) was applied. Limitation of individual effective doses according to a site specific stay scenario was also considered for this purposes with a limiting value of 0.25 mSv/y. Cost analysis of available remedial techniques were carried out, too. Two techniques have been selected for the contaminated banks restoration project: 1) removing/disposal of 20 cm soil top layer from steep and unengineered banks, and 2) mechanical dilution/fixation of contamination by clean 15 cm soil cover for the contaminated flat areas. Two-fold reduction of anticipated potential radiation risk were accepted, maximally, for the lastly mentioned technique, however cost saving is considerable (about 10-time lower the cost comparing to removing/disposal technique one). The basic acceptance limits AL for 137Cs in soil and criteria size of continuously contaminated bank areas were derived as: AL200 = 6.0 Bq/g and 800 m2 (300 m) or AL50 8.0 Bq/g and 200 m2 (80 m) for removing/disposal of the soil on steep unengineered banks. For clean soil covering technique the resulting limits are in an interval AL50C = 8 up to 16 Bq/g. According to the criteria developed, it is necessary to subject to restoration about 11000 m2 of contaminated area on

  9. Principles and criteria for environmental restoration of the contaminated banks near NPP Bohunice

    International Nuclear Information System (INIS)

    The 18 km long banks of the Bohunice NPP waste water recipient are contaminated by 137Cs as a result of two accidents on the CO2 cooled NPP-A1 unit in 1976 and 1977. Contamination acceptance limits 6 or 8 Bq 137Cslg of soil, depending on contaminated area size, were derived on the basis of developed principles, and approved by the authorities. Removing and safe burial of 1,100 m3 of contaminated soil from steep area and 15 cm thick clean soil covering on about 1ha of flat area of the contaminated banks is planned in frame of the re-considered restoration project implementation in 1995/96. (author)

  10. WWER–440 Spent Fuel and Structural Materials Performance in Jaslovke Bohunice Wet Storage Facility

    International Nuclear Information System (INIS)

    The main goals of actual stage of this long-term project are: • Analyses of the seventh set of specimens No.116/2 from ATABOR steel after 7, 5 eventually 4 years of exposition in the Bohunice spent fuel interim wet storage environment using the following methods: o Documentation of sample surfaces after removal from storage pool; - Microstructure evaluation for the base and weld metal; - Analysis of corrosion media influence to the structure of ATABOR steel using the light microscopy; o Scanning electron microscopy and microanalysis of exposed samples; • The optimization of database structure on the base of experience from the second stage of SPAR-III contract; • On the basis of the analysis results to prepare the new optimized set of specimens prepared from the specific heat of ATABOR steel

  11. Bohunician technology and thermoluminescence dating of the type locality of Brno-Bohunice (Czech Republic).

    Science.gov (United States)

    Richter, D; Tostevin, G; Skrdla, P

    2008-11-01

    Results of thermoluminescence (TL) dating of 11 heated flint artifacts from the 2002 excavation at Brno-Bohunice, Czech Republic, are presented. The samples are from the eponym locality for the Bohunician, an industrial type considered technologically transitional between Middle and Upper Paleolithic core reduction strategies. The Bohunician is the first early Upper Paleolithic technocomplex in the Middle Danube of Central Europe and, therefore, is implicated in several issues related to the origins of modern humans in Europe. The Bohunician provides an example of how one technological strategy combines crested blade initiation of a core with the surficial (almost Levalloisian) reduction of blanks as blades and points. As the Middle Danube lacks antecedents of the behavioral steps within this technology, several hypotheses of inter-regional cultural transmission, with and without hominin gene flow, could explain the appearance of the Bohunician. The elucidation of the temporal context of Bohunician assemblages is, therefore, a critical step in understanding the behavioral, and potentially biological, succession in this region. Radiocarbon age estimates from charcoal associated with Bohunician sites suggest a wide age range between 33 and 41 ka 14C BP, which is also observed for individual sites. TL dating of heated flint artifacts provides ages on the calendric time scale of an archeological event, the firing. The weighted mean of 48.2+/-1.9 ka BPTL for 11 heated flint samples from Brno-Bohunice provides the first non-radiocarbon data on archeological material from the Bohunician. The TL dating, in conjunction with the archeological and sedimentological analysis, allows the evaluation of the integrity of this new type-collection. The hypothetical possibility of the incorporation of Szeletian artifacts (i.e., leaf points) into the site formation processes can therefore be refuted. PMID:18951613

  12. Welding electrode for peripheral welds of A-1 reactor pressure vessel

    International Nuclear Information System (INIS)

    The properties are outlined of the VUZ-AC1-52 welding electrode used in welding the Bohunice A-1 reactor pressure vessel. The mechanical properties of welded joints after the final thermal treatment are summed up. (J.K.)

  13. ITER concept definition. V.1

    International Nuclear Information System (INIS)

    Under the auspices of the International Atomic Energy Agency (IAEA), an agreement among the four parties representing the world's major fusion programs resulted in a program for conceptual design of the next logical step in the fusion program, the International Thermonuclear Experimental Reactor (ITER). The definition phase, which ended in November, 1989, is summarized in two reports: a brief summary is contained in the ITER Definition Phase Report (IAEA/ITER/DS/2); the extended technical summary and technical details of ITER are contained in this two-volume report. The first volume of this report contains the Introduction and Summary, and the remainder will appear in Volume II. In the Conceptual Design Activities phase, ITER has been defined as being a tokamak device. The basic performance parameters of ITER are given in Volume I of this report. In addition, the rationale for selection of this concept, the performance flexibility, technical issues, operations, safety, reliability, cost, and research and development needed to proceed with the design are discussed. Figs and tabs

  14. What the A-1 nuclear power plant at Jaslovske Bohunice brought and left to experts, the economy and the environment

    International Nuclear Information System (INIS)

    The construction history is outlined of A-1 at Jaslovske Bohunice, the first Czechoslovak nuclear power plant. Characteristic operating data of the plant in 1972-1977 are presented. The period following the second accident at the plant and its final shutdown is described. The adverse environmental impacts of the plant are characterized. A safe decommissioning of the plant is a problem that remains to be solved. (J.B.)

  15. Comparison of Planning, Management and Organizational Aspects of Nuclear Power Plants A1 and V1 Decommissioning

    International Nuclear Information System (INIS)

    This contribution deals with planning, management and organizational aspects of decommissioning of NPP shut down due to the accident (prototype NPP A1) and NPP shut down after normal operation (NPP V1). The A1 and V1 NPPs are located very close in Bohunice nuclear site however both plants have very different technology and operational history. The preparation of A1 NPP decommissioning strategy and relevant decommissioning plans was long term process, because the plant was shut down after the accident in 1977 and decommissioning was implemented first time in Slovakia with many specific difficulties. The decommissioning planning of V1 NPP was shorter and easier, because the plant was shut down after normal operation, there were lessons learned from the A1 NPP decommissioning planning, available legislation, available financing etc. Development of decommissioning strategies, preparation and planning for decommissioning, development of legislation for decommissioning, management of decommissioning projects and other aspects are described and compared. Lessons learned are formulated on the basis of analysis of past, ongoing and planned decommissioning activities in Slovakia. (author)

  16. Analysis of the mortality development of the population in the surroundings of Bohunice NPP using Fuzzy logic methods

    International Nuclear Information System (INIS)

    We pursue the vicinity of Bohunice NPP. The vicinity has cyclic form with radius of 30 km, what represents an area approximately 2 800 km2. This area of pursued vicinity is requisite by the security report of Bohunice NPP. To the presumptive calculations we used the complete databases of Register of death, Register of municipalities and of Register of age structure of the inhabitants of the Slovak republic from 1993 to 1999, fully-fashioned in Statistical authority of the Slovak republic. We work with databases, which don't contain personal identifications. We pursue the evolution of the mortality by the indicators of the mortality, calculated by the WHO. By the literary sources and by our experience is necessary the sum at least of three years to calculation of stable demographic and epidemiological parameters. Therefore we work with the method of short time series. The basic observed unit, which is represented by one value of the indicator, is one municipality. All our assessing analyses are calculated from triennial sums of all indicators, so we work with man-years. Advanced report is the adjusted extract from Complex report on situation of environment and health of the inhabitants in vicinity of Bohunice NPP in 1999, which was advanced by our society in March 2001. (authors)

  17. Methylmercury degradation by Pseudomonas putida V1.

    Science.gov (United States)

    Cabral, Lucélia; Yu, Ri-Qing; Crane, Sharron; Giovanella, Patricia; Barkay, Tamar; Camargo, Flávio A O

    2016-08-01

    Environmental contamination of mercury (Hg) has caused public health concerns with focuses on the neurotoxic substance methylmercury, due to its bioaccumulation and biomagnification in food chains. The goals of the present study were to examine: (i) the transformation of methylmercury, thimerosal, phenylmercuric acetate and mercuric chloride by cultures of Pseudomonas putida V1, (ii) the presence of the genes merA and merB in P. putida V1, and (iii) the degradation pathways of methylmercury by P. putida V1. Strain V1 cultures readily degraded methylmercury, thimerosal, phenylmercury acetate, and reduced mercuric chloride into gaseous Hg(0). However, the Hg transformation in LB broth by P. putida V1 was influenced by the type of Hg compounds. The merA gene was detected in P. putida V1, on the other hand, the merB gene was not detected. The sequencing of this gene, showed high similarity (100%) to the mercuric reductase gene of other Pseudomonas spp. Furthermore, tests using radioactive (14)C-methylmercury indicated an uncommon release of (14)CO2 concomitant with the production of Hg(0). The results of the present work suggest that P. putida V1 has the potential to remove methylmercury from contaminated sites. More studies are warranted to determine the mechanism of removal of methylmercury by P. putida V1. PMID:27062344

  18. Information about influence of the Bohunice V2 NPP on the environment, January 2008

    International Nuclear Information System (INIS)

    In this paper results of monitoring of chemical gaseous and liquid effluents into the Vah River as well as of radiation monitoring of Bohunice V2 NPP are presented. The radioactive effluents into atmosphere within January 2008 were: 0.19 MBq of aerosoles, 0.025 MBq of iodine-131, and 382 GBq of rare gases. For the period January 2008 these radioactive effluents into atmosphere represented 0.190 MBq (0.0002% of annually limit (AL)) of aerosoles, 0.025 MBq (0.00004 MBq of AL) of iodine-131, and 382 GBq (0.519% of AL) of rare gases. The radioactive effluents into recipient of Vah River within January 2008 were: 0.06 GBq of tritium, and 0.63 MBq of corrosive and fission products. For the period January 2008 these radioactive effluents into recipient of Vah River represented 0.06 GBq (0.0003% of AL) of tritium; 0.63 MBq (0.005% of AL) of corrosive and fission products. Dose equivalents rate for the villages in surroundings of the Mochovce NPP in January 2008 are published. Chemical effluents are also reported.

  19. Information about influence of the Bohunice V2 NPP on the environment, May 2008

    International Nuclear Information System (INIS)

    In this paper results of monitoring of chemical gaseous and liquid effluents into the Vah River as well as of radiation monitoring of Bohunice V2 NPP are presented. The radioactive effluents into atmosphere within May 2008 were: 0.29 MBq of aerosoles, 0.042 MBq of iodine-131, and 367 GBq of rare gases. For the period January - May 2008 these radioactive effluents into atmosphere represented 1.10 MBq (0.0014% of annually limit (AL)) of aerosoles, 0.159 MBq (0.00024% MBq of AL) of iodine-131, and 1.930 TBq (0.519% of AL) of rare gases. The radioactive effluents into recipient of Vah River within May 2008 were: 150.68 GBq of tritium, and 0.38 MBq of corrosive and fission products. For the period January - May 2008 these radioactive effluents into recipient of Vah River represented 855.43 GBq (4.2772% of AL) of tritium; 2.92 MBq (0.0226% of AL) of corrosive and fission products. Dose equivalents rate for the villages in surroundings of the Mochovce NPP in May 2008 are published. Chemical effluents are also reported.

  20. Information about influence of the Bohunice V2 NPP on the environment, February 2008

    International Nuclear Information System (INIS)

    In this paper results of monitoring of chemical gaseous and liquid effluents into the Vah River as well as of radiation monitoring of Bohunice V2 NPP are presented. The radioactive effluents into atmosphere within February 2008 were: 0.19 MBq of aerosoles, 0.025 MBq of iodine-131, and 344 GBq of rare gases. For the period January - February 2008 these radioactive effluents into atmosphere represented 0.37 MBq (0.0005% of annually limit (AL)) of aerosoles, 0.050 MBq (0.00008% MBq of AL) of iodine-131, and 725 GBq (0.036% of AL) of rare gases. The radioactive effluents into recipient of Vah River within February 2008 were: 100.01 GBq of tritium, and 0.61 MBq of corrosive and fission products. For the period January - February 2008 these radioactive effluents into recipient of Vah River represented 110.07 GBq (0.5504% of AL) of tritium; 1.24 MBq (0.010% of AL) of corrosive and fission products. Dose equivalents rate for the villages in surroundings of the Mochovce NPP in February 2008 are published. Chemical effluents are also reported.

  1. Retrospective study of 14C concentration in the vicinity of NPP Jaslovské Bohunice using tree rings and the AMS technique

    Science.gov (United States)

    Ješkovský, Miroslav; Povinec, Pavel P.; Steier, Peter; Šivo, Alexander; Richtáriková, Marta; Golser, Robin

    2015-10-01

    Atmospheric radiocarbon has been monitored around the Nuclear Power Plant (NPP) Jaslovské Bohunice (Slovakia) using CO2 absorption in NaOH solution since 1969. In 2012, tree ring samples were collected from Tilia cordata using an increment borer at Žlkovce monitoring station situated close to the Bohunice NPP. Each tree ring was identified and graphite targets were produced for 14C analysis by accelerator mass spectrometry. The 14C concentrations obtained from the tree-ring samples have been in a reasonable agreement with the averaged annual 14C concentrations in atmospheric CO2.

  2. Nuclear power plant (A-1 NPP) SE a.s., Bohunice A-1

    International Nuclear Information System (INIS)

    The A-1 NPP was connected to the grid on 25 December 1972. The first serious refuelling accident happened on 5 April 1976. The second accident occurred on 22 February 1977 when a fouled fuel assembly was overheated, melted, and consequently radioactivity entered the whole primary circuit of steam generators, and a portion of it also leaked into the secondary circuit. The accident was classified as INES 4 level. There were no leaks of radioactivity into environment during the accident. A programme and schedule of bringing the A-1 NPP into a radiation-safe status was precise by subsequent decrees of the Slovak Government in 1993-1994. In January 1995, the Project was submitted to Nuclear Regulatory Authority of the Slovak Republic (NRA SR) and updated schedule of works was approved by the Government of the Slovak Republic. The radiation-safe status is characterised by minimizing of excluding a risk of negative environmental impacts of a NPP. There were 439 of total of 571 spent fuel assemblies transported to the former Soviet Union in 1984 through 1990. The remaining 132 assemblies are 'difficult-to-handle', ones the assemblies can not be taken out of their cases. Current solution the activities associated with transport and improvement of a safe storage of the spent fuel, issues related to processing, treatment, and storage of liquid radioactive wastes is represented by Bohunice treatment centre that has been built since 1993. In addition to Slovak partners, there are also foreign ones who are involved in bringing A-1 NPP into a radiation-safe status. The largest share of works is taken by British AEA Technology together with SGN, France. Other European countries are involved in A-1 NPP decommissioning, too, by providing technical assistance within PHARE programmes. Japan also provides funding of a broad programme of information exchange about NPPs decommissioning. Activities of nuclear safety inspectors were performed according to NRA SR yearly plan of inspection

  3. ICARE/CATHARE V1. Application to a PWR 900 MWe severe accident sequence

    Energy Technology Data Exchange (ETDEWEB)

    Zabiego, Magali; Fichot, Florian; Guillard, Valia; Barrachin, Marc; Melis, Stephane; Chatelard, Patrick; Camous, Francine [Commissariat a l' Energie Atomique, Institut de Protection et de Surete Nucleaire, DRS/SEMAR/LECTA, Centre d' Etudes de Cadarache, St-Paul-Les-Durance Cedex (France); Lefevre, Bertrand [Communications et Systems, Centre d' Etudes de Cadarache, St-Paul-Lez-Durance (France)

    2000-11-01

    In the first part of this paper, a brief description of the V1 version of the ICARE/CATHARE software is presented. The new models developed by IPSN are described here. An application of this version to a French PWR 900 MWe is then shown. Although a description of the whole circuit is possible with ICARE/CATHARE V1, the present application is restricted to the reactor vessel. The results show the progression of the core degradation and the relocation of an important amount of corium in the reactor lower head. This calculation demonstrates the capacity of the code to provide a physically grounded simulation of the whole scenario. (author)

  4. METEOR v1.0 - User's Guide

    International Nuclear Information System (INIS)

    This script is a User's Guide for the software package METEOR for statistical analysis of meteorological data series. The original version of METEOR have been developed by Ph.D. Elena Palomo, CIEMAT-IER, GIMASE. It is built by linking programs and routines written in FORTRAN 77 and it adds the graphical capabilities of GNUPLOT. The shape of this toolbox was designed following the criteria of modularity, flexibility and agility criteria. All the input, output and analysis options are structured in three main menus: i) the first is aimed to evaluate the quality of the data set; ii) the second is aimed for pre-processing of the data; and iii) the third is aimed towards the statistical analyses and for creating the graphical outputs. Actually the information about METEOR is constituted by three documents written in spanish: 1) METEOR v1.0: User's guide; 2) METEOR v1.0: A usage example; 3) METEOR v1.0: Design and structure of the software package. (Author)

  5. Reactors

    International Nuclear Information System (INIS)

    Purpose: To provide a spray cooling structure wherein the steam phase in a bwr reactor vessel can sufficiently be cooled and the upper cap and flanges in the vessel can be cooled rapidly which kept from direct contaction with cold water. Constitution: An apertured shielding is provided in parallel spaced apart from the inner wall surface at the upper portion of a reactor vessel equipped with a spray nozzle, and the lower end of the shielding and the inner wall of the vessel are closed to each other so as to store the cooling water. Upon spray cooling, cooling water jetting out from the nozzle cools the vapor phase in the vessel and then hits against the shielding. Then the cooling water mostly falls as it is, while partially enters through the apertures to the back of the shielding plate, abuts against stoppers and falls down. The stoppers are formed in an inverted L shape so that the spray water may not in direct contaction with the inner wall of the vessel. (Horiuchi, T.)

  6. Analysis of the NPP-V1 primary circuit fast cooldown

    International Nuclear Information System (INIS)

    Results of thermal-hydraulic calculations of the NPP-V1 primary circuit fast cooldown during small leakage through openings of diameter 20, 32 and 50 mm as well as analyses of cooldown following the steam pipeline break at nominal and null reactor power are given in this paper. 4 refs, 24 figs, 1 tab

  7. Investigation of reactor pressure vessel steels after radiation degradations

    International Nuclear Information System (INIS)

    The degradation of reactor pressure vessel (RPV) steel is a complex process depending on many factors (thermal and radiation treatment, chemical compositions, preparing conditions, ageing, operation environment, etc.). This paper describes tests based on Nondestructive Methods used for evaluation of material characterisation at Slovenske Elektrarne a.s. Positron Annihilation Spectroscopy (PAS), Moessbauer Spectroscopy (MS) and Transmission Electron Microscopy (TEM) investigate microstructure changes of Reactor Pressure Vessel steels caused neutrons irradiation. There are showed results of investigation of reactor pressure vessel steel specimens after five years irradiation in reactor nature by mentioned NDT methods. Investigated specimens has been prepared for the Extended surveillance specimen program which has run out on the 3rd and 4th units of NPP Jaslovske Bohunice and for the Modified surveillance specimen program in the 1st and 2nd unit which is continued in NPP Mochovce (Slovakia). PAS and MS spectra showed that the degradation of the steel properties associated with the effects of neutron irradiation can be well detected. The samples from RPV base metal (15Kh2MFA) and weld metal (Sv 10KhMFT) were measured by PAS and MS before and after irradiation. Samples have been irradiated in VVER-440 reactor (units 3rd and 4th in Bohunice as well as 1st and 2nd units Mochovce) by neutron fluency from 7.8 1023 m-2 up to 2.5 1024 m-2. Measurement results are presented and discussed in detail.(author)

  8. Increasing of leak-tightness of hermetic zone and other important components in NPPs

    International Nuclear Information System (INIS)

    The performed by VUEZ resealing works in the hermetic compartments/containment of WWER 440 and WWER 1000 NPPs in Slovakia (Jaslovske Bohunice V-1 NPP, Jaslovske Bohunice V-2 NPP, Mochovce NPP), the Czech Republic (Dukovany NPP, Temelin NPP) and Hungary (Pask NPP) are presented. The leakage rate from hermetic compartments at individual NPP reactor units are shown.The VUEZ activities in field of resealing of weld joints in pools and tanks in the Jaslovske Bohunice V-1 NPP and innovation of the seal of reactor pit protective hood (kolpak) are described. The principle of operation and practical experience of the SMU-V system implemented in the Jaslovske Bohunice V-1 NPP (WWER 440 - V 230) for NPP primary circuit leakage monitoring are also given

  9. Borate compound content reduction in liquid radioactive waste from nuclear power plants with VVER reactor

    International Nuclear Information System (INIS)

    This paper describes the current status of liquid waste (evaporator concentrates) inventory at V-1 and V-2 NPPs in Jaslovske Bohunice and the intention to separate boron from them with respect to waste minimisation and improvement of physical and chemical properties for further waste treatment and conditioning. Preliminary results of laboratory experiments concerned to borate crystallisation after pH adjustment with nitric or formic acid performed in the 1998 are given. At the present time laboratory experiments continuing - next acids, coagulation with carbon oxide, electrolytic process, ion exchange resin, study of decontamination factors, immobilization of boric acid, decrease radioactivity, purification of boron-contained compounds. Slovenske Elektrarne have accumulated 7,000 m3 of evaporator concentrates containing 100-180 g/l borate. In order to make more storage space available, it is proposed to remove some of the borate in the liquor by precipitation as sodium tetraborate and immobilise in either cement of bitumen. The supernate can be further volume reduced by evaporation and returned to the tanks. Slovenske Elektrarne are currently evaluating acid addition to the pH 12-13 concentrate to reduce the borate solubility. However, this adds to the salt burden of the waste through this chemical addition -thus creating future increases in conditioning and disposal costs. Boric acid is used in pressurized water as a soluble neutron poison to control reactivity and also to assure a safety margin in the spent fuel pool and during refuelling operations. Boric acid is also present in the water reserved for injection into the reactor in the event of postulated accidents. (author)

  10. Implementation of results of science and technology development project ''Automated system of nuclear power plant control'' at the Bohunice plant

    International Nuclear Information System (INIS)

    The implementation of the automated control system at the Jaslovske Bohunice nuclear power plant is taking place in two stages. In the first stage the main computer centre was built with an ES 1055 M computer which has been in operation since January 1985. In the following year, 6 local network terminals of type ES 7927 were installed and one multiplexer ES 8371 for the control of the network. All the equipment operates reliably, the ES 7039 printers are not so reliable. The weakest element are large-size magnetic disc memories. In the next stage, the construction is envisaged of a terminal network with SM 4-20 and SM 52/11 computers and 7202 terminals. The contribution of the implementation of computer technology so far has been in the field of maintenance where it has allowed to centrally plan repairs of some 15,000 items and to coordinate the activities of sub-contractors. Also positive are results in the field of measurement and control technology where the reliability is being evaluated of some 20,000 measurement circuits and elements, and their preventive maintenance and repairs planned. Briefly summed up are items for further increasing the contribution of the deployment of computer technology in nuclear power plants. (Z.M.)

  11. Extreme variability among mammalian V1R gene families

    OpenAIRE

    Janet M Young; Massa, Hillary F.; Hsu, Li; Trask, Barbara J

    2010-01-01

    We report an evolutionary analysis of the V1R gene family across 37 mammalian genomes. V1Rs comprise one of three chemosensory receptor families expressed in the vomeronasal organ, and contribute to pheromone detection. We first demonstrate that Trace Archive data can be used effectively to determine V1R family sizes and to obtain sequences of most V1R family members. Analyses of V1R sequences from trace data and genome assemblies show that species-specific expansions previously observed in o...

  12. Sodium void experiment and analysis on FCA Assembly V-1

    International Nuclear Information System (INIS)

    As a part of the mock-up experiment for Japan Experimental Fast Reactor (JOYO) in FCA, a sodium void experiment and analysis has been carried out on Assembly V-1. Sodium cans (50.8 x 50.8 x 6.3 mm3) in the core were replaced by the empty cans. Small reactivity change associated with the replacement was measured using the calibrated control rod and large one was measured by the subcritical method. The analysis was performed using one-dimensional calculations mainly with the JAERI-Fast set. In some cases, the ABBN Set was also used. The main results obtained are as follows; (1) Radial distribution of the single channel void-effect is nearly flat. (2) Single channel and wide region void-effects calculated with the JAERI-FAST set agree fairly well with the experimental ones if the streaming effect is taken into account. (3) As to axial distribution of the void-effect, agreement between the calculated and experimental values is very poor in the central region. (author)

  13. Acidosis differentially modulates inactivation in NaV1.2, NaV1.4, and NaV1.5 channels

    Directory of Open Access Journals (Sweden)

    PeterRuben

    2012-06-01

    Full Text Available NaV channels play a crucial role in neuronal and muscle excitability. Using whole-cell recordings we studied effects of low extracellular pH on the biophysical properties of NaV1.2, NaV1.4, and NaV1.5, expressed in cultured mammalian cells. Low pH produced different effects on different channel subtypes. Whereas NaV1.4 exhibited very low sensitivity to acidosis, primarily limited to partial block of macroscopic currents, the effects of low pH on gating in NaV1.2 and NaV1.5 were profound. In NaV1.2 low pH reduced apparent valence of steady-state fast inactivation, shifted the τ(V to depolarizing potentials and decreased channels availability during onset to slow and use-dependent inactivation. In contrast, low pH delayed open-state inactivation in NaV1.5, right-shifted the voltage-dependence of window current, and increased channel availability during onset to slow and use-dependent inactivation. These results suggest that protons affect channel availability in an isoform-specific manner. A computer model incorporating these results demonstrates their effects on membrane excitability.

  14. Positron annihilation studies of neutron irradiated and thermally treated reactor pressure vessel steels

    International Nuclear Information System (INIS)

    Positron annihilation lifetime measurements using the pulsed low energy positron system (PLEPS) were applied for the first time for the investigation of defects of irradiated and thermally treated reactor pressure vessel (RPV) steels. PLEPS results showed that the changes in the microstructure of the RPV-steel properties caused by neutron irradiation and post-irradiation thermal treatment can be detected. The samples originated from the Russian 15Kh2MFA and Sv10KhMFT steels, commercially used at WWER-440 reactors, were irradiated near the core at NPP Bohunice (Slovakia) to neutron fluences in the range from 7.8x1023 to 2.5x1024 m-2

  15. Sipping equipment for leak testing of fuel assemblies in VVER-440 reactors

    International Nuclear Information System (INIS)

    Sipping equipment for the Soviet-type VVER-440 pressurized water reactors was developed on the basis of the proven in-core sipping technique used for boiling water reactor fuel assemblies. The main components of the system are the sipping hood with seven test positions, the control panel for system operation and sample collection, and the manifold connection line. During testing the upper ends of the hexagonal fuel assemblies are lifted into the air-filled sipping hood to interrupt the coolant flow by means of pneumatically actuated grippers. The first equipment of this kind has been in use in the nuclear plant Jaslovske-Bohunice, Czechoslovakia, since 1986. (orig.)

  16. Advanced CA technologies and remotely controlled manipulators used for the decontamination of the A-1 NPP Jaslovske Bohunice, Slovak Republic

    International Nuclear Information System (INIS)

    This paper deals with the main activities and results of the Nuclear Power Plants Research Institute (VUJE) Trnava in the fields of development of remotely operated manipulators and robots for decontamination and dismantling. D and D of the Active Water Purifying Station (AWPS) of A-1 NPP Jaslovske Bohunice was chosen as a pilot project for the application of advanced CA technologies and manipulators for D and D tasks. The presence of radioactive, toxic or hazardous materials limits personnel access to facilities. Very often there are not enough up-to-date drawings of the installed technology. Therefore, in preparation phase of decontamination, a 3D Laser scanner and software 3Dipsos were involved as modelling technology and civil construction of the facility. Examples of acquired data and created 3D models are presented. Many D and D tasks have to be performed remotely. This paper describes the main features of developed remotely controlled manipulators. A movable manipulator MT-15 is dedicated for recognition and analysing tasks in hostile environment. A general purpose manipulator MT-80 is used for heavy duties in D and D. A long reach manipulator DENAR-41 was developed for the decontamination of underground waste storage tanks. Mock up tests of the afore-mentioned manipulators were performed before they were used in D and D tasks. Moreover the software EUCLID and IGRIP are used for simulation, analysing and optimisation of decontamination or dismantling tasks. This procedure leads to safe and more effective realisation of decontamination and dismantling tasks. The obtained results are also used for future development of suitable manipulators. The description of the initial and present state of contamination and radiation level in AWPS is presented in this paper. Experience with utilisation of advanced CA technology for acquiring as built models, development of manipulators and simulation of D and D tasks are described. (author)

  17. Diagnostics of components of primary and secondary circuits of WWER-440 nuclear power plants

    International Nuclear Information System (INIS)

    A brief description is presented of the monitoring diagnostic system installed in both units of the V-1 nuclear power plant in Jaslovske Bohunice. The system manufactured by Brueel and Kjaer, Denmark, operates on the principle of evaluating vibroacoustic signals from selected components of the primary and secondary circuits. Both reactors of the V-2 nuclear power plant in Jaslovske Bohunice are equipped with similar systems manufactured by West German company KWU and home manufacturers. (Z.M.)

  18. Structure and Organization of Computing (Draft v1)

    OpenAIRE

    Denning, Peter J.

    2012-01-01

    Overview of the CS field's structure including historical evolution, body of knowledge, great principles, and relationships with other fields.An article for CRC Handbook of Computer Science and Engineering DRAFT v1– 5/24/12

  19. Mineralogical determination, distribution ration, speciation and radionuclides mobility in soil samples from objects 41 and 44/10 NPP Jaslovske Bohunice

    International Nuclear Information System (INIS)

    Mineralogical characterization of a soil from the Nuclear Power Plant Jaslovske Bohunice object 41 and 44/10 was performed by x-ray diffraction method and surface measuring. It was find that the main component was smectite but other minerals like quartz, illite, chlorite and K-feldspar, were observed. Sorption and speciation of 137Cs, 85Sr, 241Am and 60Co in the mix soil was done with continuous leaching and Tessier scheme. It was found that distribution ration for Co and Cs is the highest. Strontium was in ionic form, Cs was leached with nitric acid, americium was fixed on carbonate fraction and cobalt was predominantly leached with reduction solutions as can be observed from the Tessier sequence method. Sorption of iodine on the soil used in the experiment was negligible (authors)

  20. CRISTAL V1: Criticality package for burn up credit calculations

    International Nuclear Information System (INIS)

    The first version of the CRISTAL package, created and validated as part of a joint project between IRSN, COGEMA and CEA, was delivered to users in November 1999. This fruitful cooperation between IRSN, COGEMA and CEA has been pursued until 2003 with the development and the validation of the package CRISTAL V1, whose main objectives are to improve the criticality safety studies including the Burn up Credit effect. (author)

  1. Ongoing Slow Fluctuations in V1 Impact on Visual Perception.

    Science.gov (United States)

    Wohlschläger, Afra M; Glim, Sarah; Shao, Junming; Draheim, Johanna; Köhler, Lina; Lourenço, Susana; Riedl, Valentin; Sorg, Christian

    2016-01-01

    The human brain's ongoing activity is characterized by intrinsic networks of coherent fluctuations, measured for example with correlated functional magnetic resonance imaging signals. So far, however, the brain processes underlying this ongoing blood oxygenation level dependent (BOLD) signal orchestration and their direct relevance for human behavior are not sufficiently understood. In this study, we address the question of whether and how ongoing BOLD activity within intrinsic occipital networks impacts on conscious visual perception. To this end, backwardly masked targets were presented in participants' left visual field only, leaving the ipsi-lateral occipital areas entirely free from direct effects of task throughout the experiment. Signal time courses of ipsi-lateral BOLD fluctuations in visual areas V1 and V2 were then used as proxies for the ongoing contra-lateral BOLD activity within the bilateral networks. Magnitude and phase of these fluctuations were compared in trials with and without conscious visual perception, operationalized by means of subjective confidence ratings. Our results show that ipsi-lateral BOLD magnitudes in V1 were significantly higher at times of peak response when the target was perceived consciously. A significant difference between conscious and non-conscious perception with regard to the pre-target phase of an intrinsic-frequency regime suggests that ongoing V1 fluctuations exert a decisive impact on the access to consciousness already before stimulation. Both effects were absent in V2. These results thus support the notion that ongoing slow BOLD activity within intrinsic networks covering V1 represents localized processes that modulate the degree of readiness for the emergence of visual consciousness. PMID:27601986

  2. METEOR v1.0 - A usage example

    International Nuclear Information System (INIS)

    This script describes a detailed example of the use of the software package METEOR for statistical analysis of meteorological data series. A real spanish meteorological data set is chosen to show the capabilities of METEOR. Output files and resultant plots provided of their interpretations are compiled in three appendixes. The original version of METEOR have been developed by Ph. D.Elena Palomo, CIEMAT-IER, GIASE. It is built by linking programs and routines written in FORTRAN 77 and it adds the graphical capabilities of GNUPLOT. The shape of this toolbox was designed following the criteria of modularity, flexibility and agility criteria. All the input, output and analysis options are structured in three main menus: i) the first is aimed to evaluate the quality of the data set; ii) the second is aimed for pre-processing of the data; and iii) the third is aimed towards the statistical analyses and for creating the graphical outputs. Actually the information about METEOR is constituted by three documents written is spanish: 1) METEOR v1.0: User's guide; 2) METEOR v1.0: A usage example; 3) METEOR v1 .0: Design and structure of the software package. (Author)

  3. Control of WWER-440 nuclear reactor

    International Nuclear Information System (INIS)

    The V-1 reactor control systems are described. The data acquisition and processing system fulfils four main functions, ie., reactor start-up and power increase to 10% of the rated power, automatic power control within 3% and 110% of the rated power, reactivity compensation, and reactor protection. The automatic control system ensures constant steam pressure maintained with an accuracy of +-0.05 MPa. Reactivity compensation and spatial power distribution is mainly safeguarded by boric acid control. The V-1 reactor protection system has four levels of accident protection depending on the gravity of the failure. The philosophy of automation of the V-1 reactor control and protection system is based on autonomous automatic controlers and on the direct control of the individual sets and technological equipment. In conclusion, development trends are briefly outlined of control and protection systems of light water reactor power plants. (Z.M.)

  4. Vasopressin V1a, but not V1b, receptors within the PVN of lactating rats mediate maternal care and anxiety-related behaviour.

    Science.gov (United States)

    Bayerl, Doris S; Hönig, Jennifer N; Bosch, Oliver J

    2016-05-15

    The brain neuropeptide arginine-vasopressin (AVP) mediates a wide range of social behaviours via its V1a (V1aR) but also its V1b receptor (V1bR). With respect to maternal behaviour, V1bR are still less investigated, whereas V1aR have been shown repeatedly to trigger maternal behaviour, depending on the brain region. Here, we aimed to study the role of both V1aR and V1bR within the hypothalamic paraventricular nucleus (PVN), a major source of AVP, in maternal care (lactation day (LD) 1), maternal motivation in the pup retrieval test (LD 3) and anxiety-related behaviour on the elevated plus maze (EPM; LD 5) by acute local infusion of receptor subtype-specific antagonists for V1aR (d(CH2)5Tyr(Me)(2)AVP) or V1bR (SSR149415). Furthermore, we compared V1bR expression in the PVN of virgin versus lactating rats (LD 4). Our results demonstrate that within the PVN neither V1bR mRNA (qPCR) nor protein (Western Blot) content differed between virgin and lactating rats. Regarding behaviour, acute antagonism of V1aR, but not of V1bR, decreased the occurrence of nursing as well as anxiety-related behaviour as reflected by higher percentage of time spent on and of entries into the open arms of the EPM. Maternal motivation was not affected by any treatment. In summary, we demonstrate subtype-specific involvement of V1 receptors within the PVN in mediating various maternal behaviours. The lack of effects after V1bR blockade reveals that AVP acts mainly via V1aR in the PVN, at least in lactating rats, to mediate maternal care and anxiety. PMID:26909846

  5. METEOR v1.0 - A usage example; METEOR v1.0 - Un ejemplo de uso

    Energy Technology Data Exchange (ETDEWEB)

    Palomo, E.

    1994-07-01

    This script describes a detailed example of the use of the software package METEOR for statistical analysis of meteorological data series. A real spanish meteorological data set is chosen to show the capabilities of METEOR. Output files and resultant plots provided of their interpretations are compiled in three appendixes. The original version of METEOR have been developed by Ph. D.Elena Palomo, CIEMAT-IER, GIASE. It is built by linking programs and routines written in FORTRAN 77 and it adds the graphical capabilities of GNUPLOT. The shape of this toolbox was designed following the criteria of modularity, flexibility and agility criteria. All the input, output and analysis options are structured in three main menus: i) the first is aimed to evaluate the quality of the data set; ii) the second is aimed for pre-processing of the data; and iii) the third is aimed towards the statistical analyses and for creating the graphical outputs. Actually the information about METEOR is constituted by three documents written is spanish: 1) METEOR v1.0: User's guide; 2) METEOR v1.0: A usage example; 3) METEOR v1 .0: Design and structure of the software package. (Author)

  6. METEOR v1.0 - User's Guide; METEOR v1.0 - Guia de Usuarios

    Energy Technology Data Exchange (ETDEWEB)

    Palomo, E.

    1994-07-01

    This script is a User's Guide for the software package METEOR for statistical analysis of meteorological data series. The original version of METEOR have been developed by Ph.D. Elena Palomo, CIEMAT-IER, GIMASE. It is built by linking programs and routines written in FORTRAN 77 and it adds the graphical capabilities of GNUPLOT. The shape of this toolbox was designed following the criteria of modularity, flexibility and agility criteria. All the input, output and analysis options are structured in three main menus: i) the first is aimed to evaluate the quality of the data set; ii) the second is aimed for pre-processing of the data; and iii) the third is aimed towards the statistical analyses and for creating the graphical outputs. Actually the information about METEOR is constituted by three documents written in spanish: 1) METEOR v1.0: User's guide; 2) METEOR v1.0: A usage example; 3) METEOR v1.0: Design and structure of the software package. (Author)

  7. Reconstruction of instrumentation and control system (SKR)

    International Nuclear Information System (INIS)

    For the first time extensive upgrades have been performed in all safety related areas of units with WWER 440/230 reactors. One of the most important actions was the replacement of the safety and safety related instrumentation and control. The state of the art digital safety instrumentation and control system TELEPERM XS has been implemented in units 1 and 2 of the Bohunice V1 power plant. The requirements as deduced from safety assessments conducted by commissions of international experts have been fulfilled, so that Bohunice V1 after this gradual reconstruction has been upgraded to an internationally accepted safety level for the remainder of its service life. (author)

  8. Orientation Maps in V1 and Non-Euclidean Geometry.

    Science.gov (United States)

    Afgoustidis, Alexandre

    2015-12-01

    In the primary visual cortex, the processing of information uses the distribution of orientations in the visual input: neurons react to some orientations in the stimulus more than to others. In many species, orientation preference is mapped in a remarkable way on the cortical surface, and this organization of the neural population seems to be important for visual processing. Now, existing models for the geometry and development of orientation preference maps in higher mammals make a crucial use of symmetry considerations. In this paper, we consider probabilistic models for V1 maps from the point of view of group theory; we focus on Gaussian random fields with symmetry properties and review the probabilistic arguments that allow one to estimate pinwheel densities and predict the observed value of π. Then, in order to test the relevance of general symmetry arguments and to introduce methods which could be of use in modeling curved regions, we reconsider this model in the light of group representation theory, the canonical mathematics of symmetry. We show that through the Plancherel decomposition of the space of complex-valued maps on the Euclidean plane, each infinite-dimensional irreducible unitary representation of the special Euclidean group yields a unique V1-like map, and we use representation theory as a symmetry-based toolbox to build orientation maps adapted to the most famous non-Euclidean geometries, viz. spherical and hyperbolic geometry. We find that most of the dominant traits of V1 maps are preserved in these; we also study the link between symmetry and the statistics of singularities in orientation maps, and show what the striking quantitative characteristics observed in animals become in our curved models. PMID:26082007

  9. SAIKOSAPONIN v-1 FROM ROOTS OF BUPLEURUM CHINENSE DC.

    Institute of Scientific and Technical Information of China (English)

    QIN-XIANG LIU; HONG LIANG; YU-YING ZHAO; BIN WANG; WEN-XIU YANG; YI YU

    2001-01-01

    Three triterpenoidal saponins, saikosaponin v-l(1), 6″-O-acetyl-saikosaponin b2 (2) and 6"-O acetyl-saikosaponin d(3) were isolated from the roots of the title plant and the structures were identified on the basis of spectral analysis. Saikosaponin v-1 is a new compound, which was identified as 3β,16α,23,28-tetrahydroxy-olean-ll,13(18)-dien-30-oic acid-3-O-β-D-glucopyra nosyl-(1 → 3)-β-D-fucopyranosyl-30-O-xylitol ester.

  10. cDNA library Table: wdV1 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available wdV1 NA wdV1 C108 wing disc fifth instar larval stage D1 mixed pBluescript SK- EcoR...1 for 5' Xho1for 3' sequenced from T3 primer (5' -> 3') AV405269-AV405596 wdV1[number],wdV1[number]X ...

  11. TASS code topical report. V.1 TASS code technical manual

    International Nuclear Information System (INIS)

    TASS 1.0 code has been developed at KAERI for the initial and reload non-LOCA safety analysis for the operating PWRs as well as the PWRs under construction in Korea. TASS code will replace various vendor's non-LOCA safety analysis codes currently used for the Westinghouse and ABB-CE type PWRs in Korea. This can be achieved through TASS code input modifications specific to each reactor type. The TASS code can be run interactively through the keyboard operation. A simimodular configuration used in developing the TASS code enables the user easily implement new models. TASS code has been programmed using FORTRAN77 which makes it easy to install and port for different computer environments. The TASS code can be utilized for the steady state simulation as well as the non-LOCA transient simulations such as power excursions, reactor coolant pump trips, load rejections, loss of feedwater, steam line breaks, steam generator tube ruptures, rod withdrawal and drop, and anticipated transients without scram (ATWS). The malfunctions of the control systems, components, operator actions and the transients caused by the malfunctions can be easily simulated using the TASS code. This technical report describes the TASS 1.0 code models including reactor thermal hydraulic, reactor core and control models. This TASS code models including reactor thermal hydraulic, reactor core and control models. This TASS code technical manual has been prepared as a part of the TASS code manual which includes TASS code user's manual and TASS code validation report, and will be submitted to the regulatory body as a TASS code topical report for a licensing non-LOCA safety analysis for the Westinghouse and ABB-CE type PWRs operating and under construction in Korea. (author). 42 refs., 29 tabs., 32 figs

  12. AREST-CT V1.0 software verification

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Y.; Engel, D.W.; McGrail, B.P.; Lessor, K.S.

    1995-07-01

    The Analyzer for Radionuclide Source-Term with Chemical Transport (AREST-CT) is a scientific computer code designed for performance assessments of engineered barrier system (EBS) concepts for the underground storage of nuclear waste, including high-level, intermediate, and low-level wastes. The AREST-CT code has features for analyzing the degradation of and release of radionuclides from the waste form, chemical reactions that depend on time and space, and transport of the waste and other products through the EBS. This document provides a description of the verification testing that has been performed on the initial version of ARESTCT (V1.0). Software verification is the process of confirming that the models and algorithms have been correctly implemented into a computer code. Software verification for V1.0 consisted of testing the individual modules (unit tests) and a test of the fully-coupled model (integration testing). The integration test was done by comparing the results from AREST-CT with the results from the reactive transport code CIRF.A. The test problem consisted of a 1-D analysis of the release, transport, and precipitation of {sup 99}{Tc} in an idealized LLW disposal system. All verification tests showed that AREST-CT works properly and in accordance with design specifications.

  13. AREST-CT V1.0 software verification

    International Nuclear Information System (INIS)

    The Analyzer for Radionuclide Source-Term with Chemical Transport (AREST-CT) is a scientific computer code designed for performance assessments of engineered barrier system (EBS) concepts for the underground storage of nuclear waste, including high-level, intermediate, and low-level wastes. The AREST-CT code has features for analyzing the degradation of and release of radionuclides from the waste form, chemical reactions that depend on time and space, and transport of the waste and other products through the EBS. This document provides a description of the verification testing that has been performed on the initial version of ARESTCT (V1.0). Software verification is the process of confirming that the models and algorithms have been correctly implemented into a computer code. Software verification for V1.0 consisted of testing the individual modules (unit tests) and a test of the fully-coupled model (integration testing). The integration test was done by comparing the results from AREST-CT with the results from the reactive transport code CIRF.A. The test problem consisted of a 1-D analysis of the release, transport, and precipitation of 99 Tc in an idealized LLW disposal system. All verification tests showed that AREST-CT works properly and in accordance with design specifications

  14. Fatigue of materials and structures. v. 1,2

    International Nuclear Information System (INIS)

    Published in two volumes, the conference proceedings contain 82 contributions, 9 of which have been inputted in INIS. These were concerned with the measurement and evaluation of fatigue characteristics during low-cycle load of materials such as steels for nuclear reactor pressure vessels and other components. (B.S.)

  15. SIGMA Release v1.2 - Capabilities, Enhancements and Fixes

    Energy Technology Data Exchange (ETDEWEB)

    Mahadevan, Vijay [Argonne National Lab. (ANL), Argonne, IL (United States); Grindeanu, Iulian R. [Argonne National Lab. (ANL), Argonne, IL (United States); Ray, Navamita [Argonne National Lab. (ANL), Argonne, IL (United States); Jain, Rajeev [Argonne National Lab. (ANL), Argonne, IL (United States); Wu, Danqing [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-09-30

    In this report, we present details on SIGMA toolkit along with its component structure, capabilities, and feature additions in FY15, release cycles, and continuous integration process. These software processes along with updated documentation are imperative to successfully integrate and utilize in several applications including the SHARP coupled analysis toolkit for reactor core systems funded under the NEAMS DOE-NE program.

  16. Appendices

    International Nuclear Information System (INIS)

    A survey of nuclear materials seized on the territory of Slovak Republic as well as survey of main economic indicators of Nuclear Regulatory Authority of the Slovak Republic (NRA SR) in 1995 are presented. Graphic presentation of the operation history of Bohunice V-1 and V-2 reactors as well as statistically data are given

  17. Safety of nuclear installations in the Slovak Republic

    International Nuclear Information System (INIS)

    This report describes all nuclear installations in the Slovak Republic. It informs the public about the safety of nuclear installations. The spent fuel activities and nuclear wastes storage matters are discussed separately ((NPP Bohunice V-1, NPP Bohunice V-2, NPP Mochovce, NPP Bohunice A-1, Radioactive wastes repository Mochovce, Interim spent fuel storage Bohunice)

  18. Nuclear Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hogerton, John

    1964-01-01

    This pamphlet describes how reactors work; discusses reactor design; describes research, teaching, and materials testing reactors; production reactors; reactors for electric power generation; reactors for supply heat; reactors for propulsion; reactors for space; reactor safety; and reactors of tomorrow. The appendix discusses characteristics of U.S. civilian power reactor concepts and lists some of the U.S. reactor power projects, with location, type, capacity, owner, and startup date.

  19. Activity report on neutron scattering research. V. 1, 1994

    International Nuclear Information System (INIS)

    In April, 1993, the Neutron Scattering Laboratory attached to the Institute for Solid State Physics, University of Tokyo, was newly established in Tokai, Ibaraki Prefecture, to promote nationwide users' programs for utilizing the university-owned neutron instruments installed at the JRR-3M reactor of Japan Atomic Energy Research Institute. This upgraded reactor (20 MW, the cold source is installed) has drastically expanded the number of users and research areas since 1990 when it became operational. Currently 8 and 3 out of 18 new spectrometers in total at the JRR-3M are owned by ISSP and Tohoku University, respectively, while the remaining 7 spectrometers belong to JAERI. In addition, 3 conventional spectrometers in the 30 years old JRR-2 reactor (10 MW) have also supported research activities. This is the first issue of 'Activity report on neutron scattering research', and it is to be published annually. In this report, the brief history of neutron scattering research, the users' programs, the committees, the neutron scattering instruments available at the JRR-3M and the JRR-2M, the activity reports on structures and excitation, magnetism, superconductors, liquid and glass, material science, polymers, biology and instrumentation, and publication list are reported. (K.I.)

  20. Design basis and design features of WWER-440 model 213 nuclear power plants. Reference plant: Bohunice V2 (Slovakia)

    International Nuclear Information System (INIS)

    The prime objective of the IAEA Technical Co-operation Project on Evaluation of Safety Aspects of WWER-440 model 213 NPPs is to co-ordinate and to integrate assistance to national organizations in studying selected aspects of safety for the same type of reactors. Consequently, the study integrated the results generated by national activities carried out in the Czech Republic, Hungary, Slovakia and Ukraine and co-ordinated through the IAEA. Valuable assistance in carrying out the tasks was also provided by Bulgaria and Poland. A set of publications is being prepared to present the results of the project. The publications are intended to facilitate the review and utilization of the results of the project. They are also providing assistance in further refinement and/or extension of plant specific safety evaluation of model 213 NPPs. This Technical Document addressing the design basis and safety related design features of WWER-440 model 213 plants is the first of the series to be published. It is hoped that this document will be useful to anyone working in the field of WWER safety, and in particular to experts planning, executing or reviewing studies related to the subject. Refs, 36 figs, tabs

  1. Vibrations of main components of nuclear power plant V-1 primary circuit in steady-state regimes

    International Nuclear Information System (INIS)

    The dynamic stability was studied of the reactor pressure vessel, the main circulating pumps, the main shut-off valves and steam generators in the V-1 power plant. The measurement of vibrations of the pressure vessel, the pump body and its support, the gear box of the valve drive and of the steam generator body was conducted using piezoelectric accelerometers. The measurement results are tabulated and shown graphically. In-service vibration monitoring is prescribed only for main circulating pumps in which a displacement amplitude of 50 μm for the pump body and its electric drive and 80 μm for auxiliary equipment are considered to be the permissible level. The reactor and the steam generator in steady state are considered as stable bodies with the exception of the shock load of the steam generator. (Z.M.)

  2. Ultrasound periodic inspections of reactor pressure vessels

    International Nuclear Information System (INIS)

    Two versions are described of ultrasonic equipment for periodic inspections of reactor pressure vessels. One uses the principle of exchangeable programmators with solid-state logic while the other uses programmable logic with semiconductor memories. The equipment is to be used for inspections of welded joints on the upper part of the V-1 reactor pressure vessel. (L.O.)

  3. CATHENA model of a shield circuit for ITER (v.1)

    International Nuclear Information System (INIS)

    This report contains the description of the CATHENA network model of a shield circuit for the ITER (International Thermo-nuclear Experimental Reactor) heat transport system. The model has been tested to demonstrate its ability to simulate the thermalhydraulic behaviour of such a loop during both steady-state operation and transient conditions. The CATHENA code is a general two-fluid thermalhydraulic code. The report also presents the circuit conditions during steady state operation and documents two loss-of-coolant scenarios simulated with the model. A description of the thermalhydraulic behaviour of the circuit as it empties is provided. (Author) (21 figs., tab., 12 refs.)

  4. Chapter No.3. Assessment and inspection of nuclear installations

    International Nuclear Information System (INIS)

    The assessment activity of UJD in relation to nuclear installation lies in assessment of safety documentation for constructions realised as nuclear installations, or construction through which changes on nuclear installations are realised. The assessment activity of UJD in 2001 was focused on National Repository of Radwaste in Mochovce, on Radwaste conditioning and treatment technology in Jaslovske Bohunice and on the assessment of documentation for the project of modernisation of Bohunice V-2 NPPs which is under preparation. The assessment of the technical condition of equipment, important in terms of nuclear safety, primarily based on results of in-service inspections and surveillance testing of safety related components and systems, is also a part of the safety assessment of nuclear installation operation. The inspectors take part in training courses and participate in other technical meetings and workshops organised by the IAEA and also take part in special training courses organised by the Nuclear Authorities of European countries, USA and Japan. Bohunice V-1 NPP is equipped with two reactors of WWER 440 type V-230 and was put into operation in 1978-1980 as one of the last nuclear power plants with this type of reactor. Both units of NPP V-1 Bohunice operated in 2001 according to the requirements of energy dispatching at nominal power, or in a regime of tertiary regulation. November 2000, a mission of experts invited by UJD and delegated by IAEA took place at the Bohunice NPPs. The mission members together with experts of the plant operator assessed the safety of the units of WWER-440/V-230 of Bohunice V-1 NPP after the reconstruction. The members of the mission prepared the report on the current status of safety of these units for the IAEA. In 2001, UJD by its decision, issued the approval for further operation of both reactor units of Bohunice V-1 NPP. In sense of the relevant decree on operational events, 20 events have been recorded, at Bohunice V-1 NPP in

  5. 26 CFR 1.414(v)-1 - Catch-up contributions.

    Science.gov (United States)

    2010-04-01

    ... 26 Internal Revenue 5 2010-04-01 2010-04-01 false Catch-up contributions. 1.414(v)-1 Section 1.414(v)-1 Internal Revenue INTERNAL REVENUE SERVICE, DEPARTMENT OF THE TREASURY (CONTINUED) INCOME TAX (CONTINUED) INCOME TAXES Pension, Profit-Sharing, Stock Bonus Plans, Etc. § 1.414(v)-1 Catch-up...

  6. Vasopressin receptors V1a and V2 are not osmosensors

    DEFF Research Database (Denmark)

    Lykke, Kasper; Assentoft, Mette; Fenton, Robert A;

    2015-01-01

    in AQP4-dependent water permeability was observed, although osmotic challenges failed to mimic vasopressin-dependent V1aR-mediated internalization of AQP4. Direct monitoring of inositol phosphate (IP) production of V1aR-expressing COS-7 cells demonstrated an efficient vasopressin-dependent response....... The V1aR-dependent response was monitored indirectly via its effects on aquaporin 4 (AQP4) when heterologously expressed in Xenopus oocytes and V1aR and V2R function was directly monitored following heterologous expression in COS-7 cells. A tendency toward an osmotically induced, V1aR-mediated reduction...

  7. Safety improvement of nuclear power plants with WWER-440 reactors type V-230

    International Nuclear Information System (INIS)

    Safety analysis was performed for the V-230 type WWER-440 un of the V-1 nuclear power plant at Jaslovske Bohunice in Czechoslovakia. As compared with the improved V-213 type, differences occur mainly in the automated control systems of technological processes and in the main circulation pumps. The Soviet 1986 recommendations for increasing the V-1 nuclear power plant safety are given. It is concluded that all aspects have to be taken into consideration when making decisions with respect t the reconstruction of the V-1 units. For instance, owing to the low investment costs the price of 1 MWh power generated at this plant is 100 CSC lower than at the V-2 nuclear power plant; and this favorable relation would be disturbed by in-depth reconstruction. Hence, the decisions to be made must take into account the plant operation economy, the technical state of the pressure devices as well as the out-of-dateness of the safety conception, which, however, may seem different today and in 5 to 10 years when the reconstruction will be accomplished. (Z.M.). 4 tabs., 1 ref

  8. DeCART v1.2 User's Manual

    International Nuclear Information System (INIS)

    DeCART (Deterministic Core Analysis based on Ray Tracing) is a whole core neutron transport code capable of direct subpin level flux calculation at power generating conditions. It does not require a priori homogenization nor group condensation needed in conventional reactor physics calculations. The depletion and transient calculation capabilities are also available. This manual serves as a self-sufficient guide to use the code. First of all, the various features of the code are explained which encompass various modeling options as well as the basic calculation functionalities. The instructions for running the code are also given with a description of the output files generated. Next, the underlying concepts and principles of preparing a DeCART model for a problem under consideration are presented. Each part of the input needed to specify the geometry, material composition, thermal operating condition, program execution control parameters are explained with examples. The descriptions of all the input cards are then followed. Finally, various sample model inputs ranging from a simple 2D pin cell to a realistic 3D core problem, steady-state to transient problems, and from rectangular to hexagonal core problems are presented

  9. DeCART v1.1 user's manual

    International Nuclear Information System (INIS)

    DeCART (Deterministic Core Analysis based on Ray Tracing) is a whole core neutron transport code capable of direct subpin level flux calculation at power generating conditions. It does not require a priori homogenization nor group condensation needed in conventional reactor physics calculations. The depletion and transient calculation capabilities are also available. This manual serves as a self-sufficient guide to use the code. First of all, the various features of the code are explained which encompass various modeling options as well as the basic calculation functionalities. The instructions for running the code are also given with a description of the output files generated. Next, the underlying concepts and principles of preparing a DeCART model for a problem under consideration are presented. Each part of the input needed to specify the geometry, material composition, thermal operating condition, program execution control parameters are explained with examples. The descriptions of all the input cards are then followed. Finally, various sample model inputs ranging from a simple 2D pin cell to a realistic 3D core problem, steady-state to transient problems, are presented

  10. Severe accidents in nuclear power plants. V.1

    International Nuclear Information System (INIS)

    The International Symposium on Severe Accidents in Nuclear Power Plants, organized by the International Atomic Energy Agency and co-sponsored by the Nuclear Energy Agency of the OECD, was held in Sorrento, Italy, from 21 to 25 March 1988. The symposium was attended by over 300 participants from 35 Member States and 4 organizations. There were 72 oral presentations and 28 poster presentations. In addition, a special session devoted to the publication entitled Basic Safety Principles for Nuclear Power Plants was organized by the International Nuclear Safety Advisory Group (INSAG) in the form of a panel discussion. The objective of the symposium was to provide a forum for an international exchange of information on the scientific and technical aspects of severe accidents, and on the rationale and implementation of severe accident practices in participating countries. All the presentations were divided into three chapters: National positions and practices on severe accidents (14 papers); Accident initiation and analysis (21 papers); Non-water cooled power reactors (5 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

  11. Skills enhancement in the nuclear power sector: education upgrading, training, and the Nuclear Power Plant Personnel Training Centre

    International Nuclear Information System (INIS)

    The article gives an overview of how the needs of the Slovak power sector and nuclear industry with respect to personnel skills and training are addressed and satisfied. The needs are driven by the recent significant legislative changes, continuing modernization of the Bohunice V-2 units, preparation of the Bohunice V-1 units for shutdown, and completion of the Mochovce 3 and 4 units, in connection with the licence holder's recruitment and training of qualified and competent staff. The forms, methods and means used within the theoretical and practical training, including the use of a reactor simulator, are highlighted. (author)

  12. Kinetic Analysis of Membrane Potential Dye Response to NaV1.7 Channel Activation Identifies Antagonists with Pharmacological Selectivity against NaV1.5.

    Science.gov (United States)

    Finley, Michael; Cassaday, Jason; Kreamer, Tony; Li, Xinnian; Solly, Kelli; O'Donnell, Greg; Clements, Michelle; Converso, Antonella; Cook, Sean; Daley, Chris; Kraus, Richard; Lai, Ming-Tain; Layton, Mark; Lemaire, Wei; Staas, Donnette; Wang, Jixin

    2016-06-01

    The NaV1.7 voltage-gated sodium channel is a highly valued target for the treatment of neuropathic pain due to its expression in pain-sensing neurons and human genetic mutations in the gene encoding NaV1.7, resulting in either loss-of-function (e.g., congenital analgesia) or gain-of-function (e.g., paroxysmal extreme pain disorder) pain phenotypes. We exploited existing technologies in a novel manner to identify selective antagonists of NaV1.7. A full-deck high-throughput screen was developed for both NaV1.7 and cardiac NaV1.5 channels using a cell-based membrane potential dye FLIPR assay. In assay development, known local anesthetic site inhibitors produced a decrease in maximal response; however, a subset of compounds exhibited a concentration-dependent delay in the onset of the response with little change in the peak of the response at any concentration. Therefore, two methods of analysis were employed for the screen: one to measure peak response and another to measure area under the curve, which would capture the delay-to-onset phenotype. Although a number of compounds were identified by a selective reduction in peak response in NaV1.7 relative to 1.5, the AUC measurement and a subsequent refinement of this measurement were able to differentiate compounds with NaV1.7 pharmacological selectivity over NaV1.5 as confirmed in electrophysiology. PMID:26861708

  13. V1 neurons respond to luminance changes faster than contrast changes

    OpenAIRE

    Wen-Liang Wang; Ran Li; Jian Ding; Louis Tao; Da-Peng Li; Yi Wang(Kavli Institute for the Physics and Mathematics of the Universe, Todai Institutes for Advanced Study, University of Tokyo (WPI), 5-1-5 Kashiwanoha, Kashiwa, Chiba 277-8583, Japan)

    2015-01-01

    Luminance and contrast are two major attributes of objects in the visual scene. Luminance and contrast information received by visual neurons are often updated simultaneously. We examined the temporal response properties of neurons in the primary visual cortex (V1) to stimuli whose luminance and contrast were simultaneously changed by 50 Hz. We found that response tuning to luminance changes precedes tuning to contrast changes in V1. For most V1 neurons, the onset time of response tuning to l...

  14. Adaptive gain modulation in V1 explains contextual modifications during bisection learning.

    Directory of Open Access Journals (Sweden)

    Roland Schäfer

    2009-12-01

    Full Text Available The neuronal processing of visual stimuli in primary visual cortex (V1 can be modified by perceptual training. Training in bisection discrimination, for instance, changes the contextual interactions in V1 elicited by parallel lines. Before training, two parallel lines inhibit their individual V1-responses. After bisection training, inhibition turns into non-symmetric excitation while performing the bisection task. Yet, the receptive field of the V1 neurons evaluated by a single line does not change during task performance. We present a model of recurrent processing in V1 where the neuronal gain can be modulated by a global attentional signal. Perceptual learning mainly consists in strengthening this attentional signal, leading to a more effective gain modulation. The model reproduces both the psychophysical results on bisection learning and the modified contextual interactions observed in V1 during task performance. It makes several predictions, for instance that imagery training should improve the performance, or that a slight stimulus wiggling can strongly affect the representation in V1 while performing the task. We conclude that strengthening a top-down induced gain increase can explain perceptual learning, and that this top-down signal can modify lateral interactions within V1, without significantly changing the classical receptive field of V1 neurons.

  15. Proceedings of the 2. General Congress of Nuclear Energy - v.1

    International Nuclear Information System (INIS)

    The papers arranged in the following fields: safety analysis and licensing; reactor physics; nuclear physics; reactor operation; reactor engineering and nuclear fuel analysis; scince and technology of materials; and thermohydraulic, are presented. (M.C.K.)

  16. Long-range cortical connections give rise to a robust velocity map of V1.

    Science.gov (United States)

    Sheridan, Phillip

    2015-11-01

    This paper proposes a two-dimensional velocity model (2DVM) of the primary visual cortex (V1). The model's novel aspect is that it specifies a particular pattern of long-range cortical temporal connections, via the Connection Algorithm, and shows how the addition of these connections to well-known spatial properties of V1 transforms V1 into a velocity map. The map implies a number of organizational properties of V1: (1) the singularity of each orientation pinwheel contributes to the detection of slow-moving spots across the visual field; (2) the speed component of neuronal velocity selectivity decreases monotonically across each joint orientation contour line for parallel motion and increases monotonically for orthogonal motion; (3) the cells that are direction selective to slow-moving objects are situated in the periphery of V1; and (4) neurons in distinct pinwheels tend to be connected to neurons with similar tuning preferences in other pinwheels. The model accounts for various types of known illusionary perceptions of human vision: perceptual filling-in, illusionary orientation and visual crowding. The three distinguishing features of 2DVM are: (1) it unifies the functional properties of the conventional energy model of V1; (2) it directly relates the functional properties to the known structure of the upper layers of V1; and (3) it implies that the spatial selectivity features of V1 are side effects of its more important role as a velocity map of the visual field. PMID:26343820

  17. Vasopressin receptors V1a and V2 are not osmosensors.

    Science.gov (United States)

    Lykke, Kasper; Assentoft, Mette; Fenton, Robert A; Rosenkilde, Mette M; MacAulay, Nanna

    2015-08-01

    Herein, we investigated whether G protein-coupled signaling via the vasopressin receptors of the V1a and V2 subtypes (V1aR and V2R) could be obtained as a direct response to hyperosmolar challenges and/or whether hyperosmolar challenges could augment classical vasopressin-dependent V1aR signaling. The V1aR-dependent response was monitored indirectly via its effects on aquaporin 4 (AQP4) when heterologously expressed in Xenopus oocytes and V1aR and V2R function was directly monitored following heterologous expression in COS-7 cells. A tendency toward an osmotically induced, V1aR-mediated reduction in AQP4-dependent water permeability was observed, although osmotic challenges failed to mimic vasopressin-dependent V1aR-mediated internalization of AQP4. Direct monitoring of inositol phosphate (IP) production of V1aR-expressing COS-7 cells demonstrated an efficient vasopressin-dependent response that was, however, independent of hyperosmotic challenges. Similarly, the cAMP production by the V2R was unaffected by hyperosmotic challenges although, in contrast to the V1aR, the V2R displayed an ability to support alternative signaling (IP production) at higher concentration of vasopressin. V1aR and V2R respond directly to vasopressin exposure, but they do not have an ability to act as osmo- or volume sensors when exposed to an osmotic gradient in the absence or presence of vasopressin. PMID:26311834

  18. Properties of V1 neurons tuned to conjunctions of visual features: application of the V1 saliency hypothesis to visual search behavior.

    Directory of Open Access Journals (Sweden)

    Li Zhaoping

    Full Text Available From a computational theory of V1, we formulate an optimization problem to investigate neural properties in the primary visual cortex (V1 from human reaction times (RTs in visual search. The theory is the V1 saliency hypothesis that the bottom-up saliency of any visual location is represented by the highest V1 response to it relative to the background responses. The neural properties probed are those associated with the less known V1 neurons tuned simultaneously or conjunctively in two feature dimensions. The visual search is to find a target bar unique in color (C, orientation (O, motion direction (M, or redundantly in combinations of these features (e.g., CO, MO, or CM among uniform background bars. A feature singleton target is salient because its evoked V1 response largely escapes the iso-feature suppression on responses to the background bars. The responses of the conjunctively tuned cells are manifested in the shortening of the RT for a redundant feature target (e.g., a CO target from that predicted by a race between the RTs for the two corresponding single feature targets (e.g., C and O targets. Our investigation enables the following testable predictions. Contextual suppression on the response of a CO-tuned or MO-tuned conjunctive cell is weaker when the contextual inputs differ from the direct inputs in both feature dimensions, rather than just one. Additionally, CO-tuned cells and MO-tuned cells are often more active than the single feature tuned cells in response to the redundant feature targets, and this occurs more frequently for the MO-tuned cells such that the MO-tuned cells are no less likely than either the M-tuned or O-tuned neurons to be the most responsive neuron to dictate saliency for an MO target.

  19. Properties of V1 neurons tuned to conjunctions of visual features: application of the V1 saliency hypothesis to visual search behavior.

    Science.gov (United States)

    Zhaoping, Li; Zhe, Li

    2012-01-01

    From a computational theory of V1, we formulate an optimization problem to investigate neural properties in the primary visual cortex (V1) from human reaction times (RTs) in visual search. The theory is the V1 saliency hypothesis that the bottom-up saliency of any visual location is represented by the highest V1 response to it relative to the background responses. The neural properties probed are those associated with the less known V1 neurons tuned simultaneously or conjunctively in two feature dimensions. The visual search is to find a target bar unique in color (C), orientation (O), motion direction (M), or redundantly in combinations of these features (e.g., CO, MO, or CM) among uniform background bars. A feature singleton target is salient because its evoked V1 response largely escapes the iso-feature suppression on responses to the background bars. The responses of the conjunctively tuned cells are manifested in the shortening of the RT for a redundant feature target (e.g., a CO target) from that predicted by a race between the RTs for the two corresponding single feature targets (e.g., C and O targets). Our investigation enables the following testable predictions. Contextual suppression on the response of a CO-tuned or MO-tuned conjunctive cell is weaker when the contextual inputs differ from the direct inputs in both feature dimensions, rather than just one. Additionally, CO-tuned cells and MO-tuned cells are often more active than the single feature tuned cells in response to the redundant feature targets, and this occurs more frequently for the MO-tuned cells such that the MO-tuned cells are no less likely than either the M-tuned or O-tuned neurons to be the most responsive neuron to dictate saliency for an MO target. PMID:22719829

  20. V1R promoters are well conserved and exhibit common putative regulatory motifs

    Directory of Open Access Journals (Sweden)

    Lane Robert P

    2007-07-01

    Full Text Available Abstract Background The mouse vomeronasal organ (VNO processes chemosensory information, including pheromone signals that influence reproductive behaviors. The sensory neurons of the VNO express two types of chemosensory receptors, V1R and V2R. There are ~165 V1R genes in the mouse genome that have been classified into ~12 divergent subfamilies. Each sensory neuron of the apical compartment of the VNO transcribes only one of the repertoire of V1R genes. A model for mutually exclusive V1R transcription in these cells has been proposed in which each V1R gene might compete stochastically for a single transcriptional complex. This model predicts that the large repertoire of divergent V1R genes in the mouse genome contains common regulatory elements. In this study, we have characterized V1R promoter regions by comparative genomics and by mapping transcription start sites. Results We find that transcription is initiated from ~1 kb promoter regions that are well conserved within V1R subfamilies. While cross-subfamily homology is not evident by traditional methods, we developed a heuristic motif-searching tool, LogoAlign, and applied this tool to identify motifs shared within the promoters of all V1R genes. Our motif-searching tool exhibits rapid convergence to a relatively small number of non-redundant solutions (97% convergence. We also find that the best motifs contain significantly more information than those identified in controls, and that these motifs are more likely to be found in the immediate vicinity of transcription start sites than elsewhere in gene blocks. The best motifs occur near transcription start sites of ~90% of all V1R genes and across all of the divergent subfamilies. Therefore, these motifs are candidate binding sites for transcription factors involved in V1R co-regulation. Conclusion Our analyses show that V1R subfamilies have broad and well conserved promoter regions from which transcription is initiated. Results from a new

  1. Dynamic evolution of V1R putative pheromone receptors between Mus musculus and Mus spretus

    Directory of Open Access Journals (Sweden)

    Getman Mike

    2009-02-01

    Full Text Available Abstract Background The mammalian vomeronasal organ (VNO expresses two G-protein coupled receptor gene families that mediate pheromone responses, the V1R and V2R receptor genes. In rodents, there are ~150 V1R genes comprising 12 subfamilies organized in gene clusters at multiple chromosomal locations. Previously, we showed that several of these subfamilies had been extensively modulated by gene duplications, deletions, and gene conversions around the time of the evolutionary split of the mouse and rat lineages, consistent with the hypothesis that V1R repertoires might be involved in reinforcing speciation events. Here, we generated genome sequence for one large cluster containing two V1R subfamilies in Mus spretus, a closely related and sympatric species to Mus musculus, and investigated evolutionary change in these repertoires along the two mouse lineages. Results We describe a comparison of spretus and musculus with respect to genome organization and synteny, as well as V1R gene content and phylogeny, with reference to previous observations made between mouse and rat. Unlike the mouse-rat comparisons, synteny seems to be largely conserved between the two mouse species. Disruption of local synteny is generally associated with differences in repeat content, although these differences appear to arise more from deletion than new integrations. Even though unambiguous V1R orthology is evident, we observe dynamic modulation of the functional repertoires, with two of seven V1Rb and one of eleven V1Ra genes lost in spretus, two V1Ra genes becoming pseudogenes in musculus, two additional orthologous pairs apparently subject to strong adaptive selection, and another divergent orthologous pair that apparently was subjected to gene conversion. Conclusion Therefore, eight of the 18 (~44% presumptive V1Ra/V1Rb genes in the musculus-spretus ancestor appear to have undergone functional modulation since these two species diverged. As compared to the rat

  2. N Reactor

    Data.gov (United States)

    Federal Laboratory Consortium — The last of Hanfordqaodmasdkwaspemas7ajkqlsmdqpakldnzsdflss nine plutonium production reactors to be built was the N Reactor.This reactor was called a dual purpose...

  3. European validation of ASTEC-V1 through the EVITA project

    International Nuclear Information System (INIS)

    version V1 allows simulating complete scenarios including the front-end phase. Both developing organisations, GRS and IRSN, which will continue to assure the code maintenance beyond EVITA, ensure that the EVITA outcomes will be respected for the future ASTEC development. Some of the above needed improvements are already foreseen, as well as the extension to Boiling Water Reactors. Further recommendations are given to improve: - Management of input decks: tools for automatic check, standard inputs for generic plant applications; - Visualisation / post-processing (remark: actually the GRS visualisation tool ATLAS will be coupled to the next code version); - Users' support, including: continuous training courses (not only for beginners, but for experienced users too), wish for faster response of the ASTEC Maintenance team, more complete and detailed code documentation. The plant applications with the first version of ASTEC V1 showed that the code is still not so robust that a sequence is calculated up to a foreseen end. Suggestions are made especially for increasing the robustness of the coupling of the two new modules CESAR-DIVA that calculate the circuit thermal hydraulics and the core degradation. With respect to computing time, the EVITA users - researchers, licensing authorities and industry - accepted the definition elaborated in the VASA project as target, that a full sequence calculation (incl. post-processing) should not need more than 12 hours. The progress since the beginning of the project where only a preliminary code version was available is important. The actual version allows to simulate the entire sequence of events during a severe accident. Besides, a first level of validation was attained successfully within the project. As EVITA has very successfully made the first step into the intention to provide end-users (like utilities, vendors and licensing authorities) with a well validated European integral code for the simulation of severe accidents in NPPs, the

  4. Ranolazine inhibits NaV1.5-mediated breast cancer cell invasiveness and lung colonization

    OpenAIRE

    Driffort, Virginie; Gillet, Ludovic; Bon, Emeline; Marionneau-Lambot, Séverine; Oullier, Thibauld; Joulin, Virginie; Collin, Christine; Pagès, Jean-Christophe; Jourdan, Marie-Lise; Chevalier, Stéphan; Bougnoux, Philippe; Le Guennec, Jean-Yves; Besson, Pierre; Roger, Sébastien

    2014-01-01

    Background NaV1.5 voltage-gated sodium channels are abnormally expressed in breast tumours and their expression level is associated with metastatic occurrence and patients’ death. In breast cancer cells, NaV1.5 activity promotes the proteolytic degradation of the extracellular matrix and enhances cell invasiveness. Findings In this study, we showed that the extinction of NaV1.5 expression in human breast cancer cells almost completely abrogated lung colonisation in immunodepressed mice (NMRI ...

  5. Determination of burnup balance for nuclear reactor fuel on the basis of γ-spectrometric determination of fission products

    International Nuclear Information System (INIS)

    Results are given of experimental investigations in one of the versions of the method for determination of the balance of nuclear fuel burnup process by means of the γ-spectrometry of fission products. In the version being considered a balance of the burnup process was determined on the base of 106Ru, 134Cs.Activity was measured by means of a γ-spectrometer with Ge counter. Investigations were done on the natural uranium metal fuel from the heavy-water moderated reactor of the first Czechoslovakian nuclear power plant A1 in Yaslovske Bohunice. Possibility was checked of determination of the fuel burnup depth as well as of the isotope ratio and content of plutonium. Results were compared with the control data which had been obtained on the base of the mass-spectrometry of U, Pu and Nd. The reasors for deviations were estimated in the cases when they were greater tan error in the control data

  6. Looming sensitive cortical regions without V1 input: evidence from a patient with bilateral cortical blindness

    Directory of Open Access Journals (Sweden)

    Alexis Hervais-Adelman

    2015-10-01

    This demonstrates that looming motion is processed in the absence of awareness through direct subcortical projections to areas involved in multisensory processing of motion and saliency that bypass V1.

  7. Two temporal channels in human V1 identified using fMRI

    OpenAIRE

    Horiguchi, Hiroshi; Nakadomari, Satoshi; Misaki, Masaya; Wandell, Brian A.

    2009-01-01

    Human visual sensitivity to a fairly broad class of dynamic stimuli can be modeled accurately using two temporal channels. Here, we analyze fMRI measurements of the temporal step response to spatially uniform stimuli to estimate these channels in human primary visual cortex (V1). In agreement with the psychophysical literature, the V1 fMRI temporal responses are modeled accurately as a mixture of two (transient and sustained) channels. We derive estimates of the relative contributions from th...

  8. Topographic Organization of V1 Projections through the Corpus Callosum in Humans

    OpenAIRE

    Saenz, M.; Fine, I

    2010-01-01

    The visual cortex in each hemisphere is linked to the opposite hemisphere by axonal projections that pass through the splenium of the corpus callosum. Visual–callosal connections in humans and macaques are found along the V1/V2 border where the vertical meridian is represented. Here we identify the topography of V1 vertical midline projections through the splenium within six human subjects with normal vision using diffusion-weighted MR imaging and probabilistic diffusion tractography. Tractog...

  9. Protein kinase A modulation of CaV1.4 calcium channels

    Science.gov (United States)

    Sang, Lingjie; Dick, Ivy E.; Yue, David T.

    2016-07-01

    The regulation of L-type Ca2+ channels by protein kinase A (PKA) represents a crucial element within cardiac, skeletal muscle and neurological systems. Although much work has been done to understand this regulation in cardiac CaV1.2 Ca2+ channels, relatively little is known about the closely related CaV1.4 L-type Ca2+ channels, which feature prominently in the visual system. Here we find that CaV1.4 channels are indeed modulated by PKA phosphorylation within the inhibitor of Ca2+-dependent inactivation (ICDI) motif. Phosphorylation of this region promotes the occupancy of calmodulin on the channel, thus increasing channel open probability (PO) and Ca2+-dependent inactivation. Although this interaction seems specific to CaV1.4 channels, introduction of ICDI1.4 to CaV1.3 or CaV1.2 channels endows these channels with a form of PKA modulation, previously unobserved in heterologous systems. Thus, this mechanism may not only play an important role in the visual system but may be generalizable across the L-type channel family.

  10. Protein kinase A modulation of CaV1.4 calcium channels.

    Science.gov (United States)

    Sang, Lingjie; Dick, Ivy E; Yue, David T

    2016-01-01

    The regulation of L-type Ca(2+) channels by protein kinase A (PKA) represents a crucial element within cardiac, skeletal muscle and neurological systems. Although much work has been done to understand this regulation in cardiac CaV1.2 Ca(2+) channels, relatively little is known about the closely related CaV1.4 L-type Ca(2+) channels, which feature prominently in the visual system. Here we find that CaV1.4 channels are indeed modulated by PKA phosphorylation within the inhibitor of Ca(2+)-dependent inactivation (ICDI) motif. Phosphorylation of this region promotes the occupancy of calmodulin on the channel, thus increasing channel open probability (PO) and Ca(2+)-dependent inactivation. Although this interaction seems specific to CaV1.4 channels, introduction of ICDI1.4 to CaV1.3 or CaV1.2 channels endows these channels with a form of PKA modulation, previously unobserved in heterologous systems. Thus, this mechanism may not only play an important role in the visual system but may be generalizable across the L-type channel family. PMID:27456671

  11. Topographic organization of V1 projections through the corpus callosum in humans.

    Science.gov (United States)

    Saenz, M; Fine, I

    2010-10-01

    The visual cortex in each hemisphere is linked to the opposite hemisphere by axonal projections that pass through the splenium of the corpus callosum. Visual-callosal connections in humans and macaques are found along the V1/V2 border where the vertical meridian is represented. Here we identify the topography of V1 vertical midline projections through the splenium within six human subjects with normal vision using diffusion-weighted MR imaging and probabilistic diffusion tractography. Tractography seed points within the splenium were classified according to their estimated connectivity profiles to topographic subregions of V1, as defined by functional retinotopic mapping. First, we report a ventral-dorsal mapping within the splenium with fibers from ventral V1 (representing the upper visual field) projecting to the inferior-anterior corner of the splenium and fibers from dorsal V1 (representing the lower visual field) projecting to the superior-posterior end. Second, we also report an eccentricity gradient of projections from foveal-to-peripheral V1 subregions running in the anterior-superior to posterior-inferior direction, orthogonal to the dorsal-ventral mapping. These results confirm and add to a previous diffusion MRI study (Dougherty et al., 2005) which identified a dorsal/ventral mapping of human splenial fibers. These findings yield a more detailed view of the structural organization of the splenium than previously reported and offer new opportunities to study structural plasticity in the visual system. PMID:20553894

  12. Monitoring of primary circuit and reactor of NPP A-1

    International Nuclear Information System (INIS)

    Nuclear Power Plant A-1 in Jaslovske Bohunice was commissioned in 1972. Heavy water moderated, carbon dioxide cooled channel type reactor was shut down after two accidents in 1977. During more serious second accident, the reduced coolant flow caused local overheating of the fuel and consequent damage/melting of the fuel channel. Both accidents had led to the damage of several fuel assemblies with extensive local damage of fuel claddings. As a consequence, the main cooling circuit was significantly contaminated by fission products and long-life alpha nuclides. The detailed monitoring of dose rates, smearable contamination and sampling of contamination was performed. Extended monitoring in reacto vessel, primary circuit pipes, turbo-compressors, steam generators, main valves, gas tanks and also heavy water system with collectors, coolers, distilling and purification station, pumps and valves was done. Appropriate devices and procedures for the monitoring and examination of the installations were prepared and applied. Obtained results will serve for the future planning of the decontamination and decommissioning works. The 3-D model of the reactor that had been developed as part of this Project proved invaluable for orientation, visualisation, planning and analysis of results. Dose rates were measured in the technological channels from the reactor hall floor to the bottom of the hot gas chamber in decrements of 1 m and 0.5 m. The highest absolute values of dose rates were found in channels located in the middle of the reactor (up to 1900 mGy/h in the active zone region). It is estimated that the total contaminated area of primary circuit equipment (pipework, steam generators and turbo-compressors) is some 48 000 m2. It follows that the total gamma contamination is of the order of 1014 to 1015 Bq and total alpha contamination 1011 to 1013 Bq. The total amount of deposits in the gas circuit is about 14.3 tons. (authors)

  13. METEOR v1.0 - Design and structure of the software package; METEOR v1.0 - Estructura y modulos informaticos

    Energy Technology Data Exchange (ETDEWEB)

    Palomo, E.

    1994-07-01

    This script describes the structure and the separated modules of the software package METEOR for the statistical analysis of meteorological data series. It contains a systematic description of the subroutines of METEOR and, also, of the required shape for input and output files. The original version of METEOR have been developed by Ph.D. Elena Palomo, CIEMAT-IER, GIMASE. It is built by linking programs and routines written in FORTRAN 77 and it adds thc graphical capabilities of GNUPLOT. The shape of this toolbox was designed following the criteria of modularity, flexibility and agility criteria. All the input, output and analysis options are structured in three main menus: i) the first is aimed to evaluate the quality of the data set; ii) the second is aimed for pre-processing of the data; and iii) the third is aimed towards the statistical analyses and for creating the graphical outputs. Actually the information about METEOR is constituted by three documents written in spanish: 1) METEOR v1.0: User's guide; 2) METEOR v1.0: A usage example; 3) METEOR v 1.0: Design and structure of the software package. (Author)

  14. Proceedings of the 1. General Congress of Nuclear Energy. v. 1

    International Nuclear Information System (INIS)

    The proceedings of 1 General Congress of Nuclear Energy are presented. All fields related to nuclear energy are enclosed. In the first part the following fields are shown: safety analysis, science and technology of materials, nuclear materials, nuclear laws, education and trainning, reactor physics, nuclear physics, quality assurance, mathematical models, reactor operation, safeguards, advanced technologies, thermohydraulic and reactor licensing. (M.C.K.)

  15. Reactor Physics

    International Nuclear Information System (INIS)

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised

  16. Reactor Physics

    International Nuclear Information System (INIS)

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised

  17. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

  18. Monitoring of I-131 after Fukushima nuclear power plant disaster and a correction of contribution of I-131 in the discharges of Slovenske elektrarne, Bohunice nuclear power plant

    International Nuclear Information System (INIS)

    After the earthquake and subsequent tsunami in March 2011 Fukushima nuclear power reactors in Japan were damaged. As a result of damage of reactors escaped into air iodine radioactive isotopes which were dispersed by air masses over Europe and Slovakia. Isotope I-131 was identified in samples of the atmosphere and the abstraction of Radiation Control SE EBO. The air from the atmosphere contaminated with isotopes of iodine from the Fukushima ventilation systems that do not contain iodine filters, sucked into the interior of the controlled area, then released in organised way and then measured in the ventilation chimneys of EBO NPP. The measured values thus entered a balance of radioactive discharges. Drain of I-131 from SE EBO was in that period plus a contribution coming from Fukushima NPP and measured activity I-131 had to be corrected.

  19. Reactor operation

    CERN Document Server

    Shaw, J

    2013-01-01

    Reactor Operation covers the theoretical aspects and design information of nuclear reactors. This book is composed of nine chapters that also consider their control, calibration, and experimentation.The opening chapters present the general problems of reactor operation and the principles of reactor control and operation. The succeeding chapters deal with the instrumentation, start-up, pre-commissioning, and physical experiments of nuclear reactors. The remaining chapters are devoted to the control rod calibrations and temperature coefficient measurements in the reactor. These chapters also exp

  20. Reactor safeguards

    CERN Document Server

    Russell, Charles R

    2013-01-01

    Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactor

  1. Serodeconversion of HIV Antibody-Positive AIDS Patients Following Treatment with V-1 Immunitor

    Directory of Open Access Journals (Sweden)

    Aldar S. Bourinbaiar

    2008-10-01

    Full Text Available It is extremely rare when HIV seropositive adult patients experience spontaneous loss of antibodies, that is, seroreversion. The disappearance of HIV antibodies was occasionally attributed to iatrogenic intervention—serodeconversion. Such interventions include: HAART; oral interferon; Chinese herbal remedies; and therapeutic AIDS vaccines derived from pooled blood. Oral therapeutic, alloimmune AIDS vaccine, V-1 Immunitor (V1, was administered to 60000 HIV-positive Thai patients. The administration of V1 resulted in serodeconversion among 23 individuals. The patient group consisted of 9 females (39% and 14 males (61% including two 2-year-old boys. The age range was 2–58 years with mean/median 29/29.3 years. Patients were tested seropositive for HIV at least once before being enrolled on V1. The duration of treatment until discovery of seronegative status ranged between 2 weeks and 15 months with average/median 7.2/8 months. Time to seronegativity was correlated with baseline disease stage (R=0.62; P=.002. The seronegative status was positively associated with V1-induced undetectable or low viral load (R=0.65; P=.0008. The odds ratio analysis comparing the outcome of our study with published surveys of diagnostic accuracy of laboratory tests suggested that the probability of HIV antibody testing error was remote (P<.000001. The possible causes responsible for this unusual phenomenon are discussed.

  2. Two temporal channels in human V1 identified using fMRI.

    Science.gov (United States)

    Horiguchi, Hiroshi; Nakadomari, Satoshi; Misaki, Masaya; Wandell, Brian A

    2009-08-01

    Human visual sensitivity to a fairly broad class of dynamic stimuli can be modeled accurately using two temporal channels. Here, we analyze fMRI measurements of the temporal step response to spatially uniform stimuli to estimate these channels in human primary visual cortex (V1). In agreement with the psychophysical literature, the V1 fMRI temporal responses are modeled accurately as a mixture of two (transient and sustained) channels. We derive estimates of the relative contributions from these two channels at a range of eccentricities. We find that all portions of V1 contain a significant transient response. The central visual field representation includes a significant sustained response, but the amplitude of the sustained channel signal declines with eccentricity. The sustained signals may reflect the emphasis on pattern recognition and color in the central visual field; the dominant transient response in the visual periphery may reflect responses in the human visual attention system. PMID:19361561

  3. Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Martens, Frederick H. [Argonne National Laboratory; Jacobson, Norman H.

    1968-09-01

    This booklet discusses research reactors - reactors designed to provide a source of neutrons and/or gamma radiation for research, or to aid in the investigation of the effects of radiation on any type of material.

  4. V1a vasopressin receptors maintain normal blood pressure by regulating circulating blood volume and baroreflex sensitivity

    OpenAIRE

    Koshimizu, Taka-aki; Nasa, Yoshihisa; Tanoue, Akito; Oikawa, Ryo; Kawahara, Yuji; Kiyono, Yasushi; ADACHI, TETSUYA; Tanaka, Toshiki; Kuwaki, Tomoyuki; Mori, Toyoki; Takeo, Satoshi; Okamura, Hitoshi; Tsujimoto, Gozoh

    2006-01-01

    Arginine-vasopressin (AVP) is a hormone that is essential for both osmotic and cardiovascular homeostasis, and exerts important physiological regulation through three distinct receptors, V1a, V1b, and V2. Although AVP is used clinically as a potent vasoconstrictor (V1a receptor-mediated) in patients with circulatory shock, the physiological role of vasopressin V1a receptors in blood pressure (BP) homeostasis is ill-defined. In this study, we investigated the functional roles of the V1a recept...

  5. Correlation Study of PtfV1 with Heart-Qi Deficiency Syndrome in Patients with Hypertensive Left Ventricular Hypertrophy

    Institute of Scientific and Technical Information of China (English)

    杨传华; 陆峰

    2002-01-01

    @@ It is generally believed that the change of p-wave terminal force in lead V1 (PtfV1) is associated with the inner diameter of left atrium, left ventricular compliance,and ventricular diastolic function. The increase of negative value of PtfV1 in essential hypertensive (EH) patients with left ventricular hypertrophy (LVH) indicates the cardiac function may be damaged. In order to explore the relationship between Heart-Qi Deficiency Syndrome (HQDS) of TCM and PtfV1 level in hypertensive LVH patients, correlation analysis of scores of Heart-Qi Deficiency Syndrome and negative value of PtfV1 was made by the authors.

  6. Research reactors

    International Nuclear Information System (INIS)

    This article proposes an overview of research reactors, i.e. nuclear reactors of less than 100 MW. Generally, these reactors are used as neutron generators for basic research in matter sciences and for technological research as a support to power reactors. The author proposes an overview of the general design of research reactors in terms of core size, of number of fissions, of neutron flow, of neutron space distribution. He outlines that this design is a compromise between a compact enough core, a sufficient experiment volume, and high enough power densities without affecting neutron performance or its experimental use. The author evokes the safety framework (same regulations as for power reactors, more constraining measures after Fukushima, international bodies). He presents the main characteristics and operation of the two families which represent almost all research reactors; firstly, heavy water reactors (photos, drawings and figures illustrate different examples); and secondly light water moderated and cooled reactors with a distinction between open core pool reactors like Melusine and Triton, pool reactors with containment, experimental fast breeder reactors (Rapsodie, the Russian BOR 60, the Chinese CEFR). The author describes the main uses of research reactors: basic research, applied and technological research, safety tests, production of radio-isotopes for medicine and industry, analysis of elements present under the form of traces at very low concentrations, non destructive testing, doping of silicon mono-crystalline ingots. The author then discusses the relationship between research reactors and non proliferation, and finally evokes perspectives (decrease of the number of research reactors in the world, the Jules Horowitz project)

  7. Reactor physics and reactor computations

    International Nuclear Information System (INIS)

    Mathematical methods and computer calculations for nuclear and thermonuclear reactor kinetics, reactor physics, neutron transport theory, core lattice parameters, waste treatment by transmutation, breeding, nuclear and thermonuclear fuels are the main interests of the conference

  8. Research reactors

    International Nuclear Information System (INIS)

    There are currently 284 research reactors in operation, and 12 under construction around the world. Of the operating reactors, nearly two-thirds are used exclusively for research, and the rest for a variety of purposes, including training, testing, and critical assembly. For more than 50 years, research reactor programs have contributed greatly to the scientific and educational communities. Today, six of the world's research reactors are being shut down, three of which are in the USA. With government budget constraints and the growing proliferation concerns surrounding the use of highly enriched uranium in some of these reactors, the future of nuclear research could be impacted

  9. Reactor container

    International Nuclear Information System (INIS)

    Object: To provide a jet and missile protective wall of a configuration being inflated toward the center of a reactor container on the inside of a body of the reactor container disposed within a biological shield wall to thereby increase safety of the reactor container. Structure: A jet and missile protective wall comprised of curved surfaces internally formed with a plurality of arch inflations filled with concrete between inner and outer iron plates and shape steel beam is provided between a reactor container surrounded by a biological shield wall and a thermal shield wall surrounding the reactor pressure vessel, and an adiabatic heat insulating material is filled in space therebetween. (Yoshino, Y.)

  10. Adaptation to visual stimulation modifies the burst firing property of V1 neurons%Adaptation to visual stimulation modifies the burst firing property of V1neurons

    Institute of Scientific and Technical Information of China (English)

    Rui-Long LIU; Ke WANG; Jian-Jun MENG; Tian-Miao HUA; Zhen LIANG; Min-Min XI

    2013-01-01

    The mean firing rate of visual cortical neurons is reduced after prolonged visual stimulation,but the underlying process by which this occurs as well as the biological significance of this phenomenon remains unknown.Computational neuroscience studies indicate that high-frequency bursts in stimulus-driven responses can be transmitted across synapses more reliably than isolated spikes,and thus may carry accurate stimulus-related information.Our research examined whether or not adaptation affects the burst firing property of visual cortical neurons by examining changes in the burst firing changes of V1 neurons during adaptation to the preferred visual stimulus.The results show that adaptation to prolonged visual stimulation significantly decreased burst frequency (bursts/s) and burst length (spikes/burst),but increased burst duration and the interspike interval within bursts.These results suggest that the adaptation of V1 neurons to visual stimulation may result in a decrease of feedforward response gain but an increase of functional activities from lateral and/or feedback connections,which could lead to a reduction in the effectiveness of adapted neurons in transmitting information to its driven neurons.

  11. Calculational experimental examination and ensuring of equipment and pipelines seismic resistance at starting and operating water-cooled and moderated reactor WWER-type NPPs. Final report

    International Nuclear Information System (INIS)

    The results of testing of equipment at Bohunice NPP and pipeline systems at Unit 3 of Kozloduy NPP (WWER-440 type reactors) are presented in this Final Report. These results side by side with experimental values of natural frequencies and decrements also include experimental data about vibration modes of tested equipment and pipelines. For the first time the results of new calculational-experimental examination of equipment seismic resistance at Unit 2 of Armenian NPP are presented. At Kozloduy NPP direction's request the planed additional tests of some selected items were put off on 1997. Instead of postponed tests we carried out detailed analysis of our past inspections of numerous equipment seismic resistance at the Unit 5 of Kozloduy NPP. Experimental data with results of additional analysis are presented

  12. The role of primary visual cortex (V1) in visual awareness.

    NARCIS (Netherlands)

    V.A.F. Lamme; H. Super; R. Landman; P.R. Roelfsema; H. Spekreijse

    2000-01-01

    Neurophysiological data from V1 recordings in awake monkeys were examined in light of 2 general classes of visual awareness (VA)models. In model type 1, VA is seen as being mediated either by a particular set of areas or pathways, or alternatively by a specific set of neurons. In these models, the r

  13. Statistical analysis of the vibration loading of the reactor internals and fuel assemblies of reactor units type WWER-440 from deferent projects

    International Nuclear Information System (INIS)

    In this paper the following items have been presented: 1) Vibration noise instrument channels; 2) Vibration loading characteristics of control assemblies, internals and design peculiarities of internals of WWER-440 deferent projects; 3) Coolant flow rate through the reactor, reactor core, fuel assemblies and control assemblies for different projects WWER-440 and 4) Noise measurements of coolant speed per channel. The change of auto power spectrum density of absolute displacement detector signal for the last 12 years of SUS monitoring of the Kola NPP unit 2; the coherence functions groups between two SPND of the same level for the Kola NPP unit 1; the measured coolant flow rate at Paks NPP and the auto power spectrum density group of SPND signals from 11 neutron measuring channels of the Kola NPP unit 1 are given. The main factors of vibration loading of internals and fuel assemblies for Kola NPP units 1-4, Bohunice NPP units 1 and 2 and Novovoronezh NPP units 3 and 4 are also discussed

  14. Proceedings of the 13. annual conference of the Canadian Nuclear Society. V. 1

    International Nuclear Information System (INIS)

    Volume 1 of the proceedings of the 13. annual conference of the Canadian Nuclear Society includes sessions on the following topics: reactor physics, new concepts and technology, fuel behaviour, reactor design, safety analysis, fuel channel behaviour, equipment and design qualification. The individual papers have been abstracted separately

  15. Reactor building

    International Nuclear Information System (INIS)

    The whole reactor building is accommodated in a shaft and is sealed level with the earth's surface by a building ceiling, which provides protection against penetration due to external effects. The building ceiling is supported on walls of the reactor building, which line the shaft and transfer the vertical components of forces to the foundations. The thickness of the walls is designed to withstand horizontal pressure waves in the floor. The building ceiling has an opening above the reactor, which must be closed by cover plates. Operating equipment for the reactor can be situated above the building ceiling. (orig./HP)

  16. Heterogeneous reactors

    International Nuclear Information System (INIS)

    The microscopic study of a cell is meant for the determination of the infinite multiplication factor of the cell, which is given by the four factor formula: K(infinite) = n(epsilon)pf. The analysis of an homogeneous reactor is similar to that of an heterogeneous reactor, but each factor of the four factor formula can not be calculated by the formulas developed in the case of an homogeneous reactor. A great number of methods was developed for the calculation of heterogeneous reactors and some of them are discussed. (Author)

  17. MREG V1.1 : a multi-scale image registration algorithm for SAR applications.

    Energy Technology Data Exchange (ETDEWEB)

    Eichel, Paul H.

    2013-08-01

    MREG V1.1 is the sixth generation SAR image registration algorithm developed by the Signal Processing&Technology Department for Synthetic Aperture Radar applications. Like its predecessor algorithm REGI, it employs a powerful iterative multi-scale paradigm to achieve the competing goals of sub-pixel registration accuracy and the ability to handle large initial offsets. Since it is not model based, it allows for high fidelity tracking of spatially varying terrain-induced misregistration. Since it does not rely on image domain phase, it is equally adept at coherent and noncoherent image registration. This document provides a brief history of the registration processors developed by Dept. 5962 leading up to MREG V1.1, a full description of the signal processing steps involved in the algorithm, and a user's manual with application specific recommendations for CCD, TwoColor MultiView, and SAR stereoscopy.

  18. Explosive Model Tarantula V1/JWL++ Calibration of LX-17: #2

    Energy Technology Data Exchange (ETDEWEB)

    Souers, P C; Vitello, P

    2009-05-01

    Tarantula V1 is a kinetic package for reactive flow codes that seeks to describe initiation, failure, dead zones and detonation simultaneously. The most important parameter is P1, the pressure between the initiation and failure regions. Both dead zone formation and failure can be largely controlled with this knob. However, V1 does failure with low settings and dead zones with higher settings, so that it cannot fulfill its purpose in the current format. To this end, V2 is under test. The derivation of the initiation threshold P0 is discussed. The derivation of the initiation pressure-tau curve as an output of Tarantula shows that the initiation package is sound. A desensitization package is also considered.

  19. Dependence of V2 illusory contour response on V1 cell properties and topographic organization.

    Science.gov (United States)

    Cohen, Amelia; Buia, Calin; Tiesinga, Paul

    2014-06-01

    An illusory contour is an image that is perceived as a contour in the absence of typical contour characteristics, such as a change in luminance or chromaticity across the stimulus. In cats and primates, cells that respond to illusory contours are sparse in cortical area V1, but are found in greater numbers in cortical area V2. We propose a model capable of illusory contour detection that is based on a realistic topographic organization of V1 cells, which reproduces the responses of individual cell types measured experimentally. The model allows us to explain several experimentally observed properties of V2 cells including variability in orientation tuning and inducer spacing preference. As a practical application, the model can be used to estimate the relationship between the severity of a cortical injury in the primary visual cortex and the deterioration of V2 cell responses to real and illusory contours. PMID:24801874

  20. Nonlinear V1 responses to natural scenes revealed by neural network analysis.

    Science.gov (United States)

    Prenger, Ryan; Wu, Michael C-K; David, Stephen V; Gallant, Jack L

    2004-01-01

    A key goal in the study of visual processing is to obtain a comprehensive description of the relationship between visual stimuli and neuronal responses. One way to guide the search for models is to use a general nonparametric regression algorithm, such as a neural network. We have developed a multilayer feed-forward network algorithm that can be used to characterize nonlinear stimulus-response mapping functions of neurons in primary visual cortex (area V1) using natural image stimuli. The network is capable of extracting several known V1 response properties such as: orientation and spatial frequency tuning, the spatial phase invariance of complex cells, and direction selectivity. We present details of a method for training networks and visualizing their properties. We also compare how well conventional explicit models and those developed using neural networks can predict novel responses to natural scenes. PMID:15288891

  1. BSND and ATP6V1G3: Novel Immunohistochemical Markers for Chromophobe Renal Cell Carcinoma

    OpenAIRE

    SHINMURA, KAZUYA; Igarashi, Hisaki; Kato, Hisami; Koda, Kenji; Ogawa, Hiroshi; Takahashi, Seishiro; Otsuki, Yoshiro; Yoneda, Tatsuaki; Kawanishi, Yuichi; Funai, Kazuhito; Takayama, Tatsuya; Ozono, Seiichiro; Sugimura, Haruhiko

    2015-01-01

    Abstract Differentiating between chromophobe renal cell carcinoma (RCC) and other RCC subtypes can be problematic using routine light microscopy. This study aimed to identify novel immunohistochemical markers useful for a differential diagnosis between chromophobe RCC and other RCC subtypes. We selected 3 genes (including BSND and ATP6V1G3) that showed specific transcriptional expression in chromophobe RCC using expression data (n = 783) from The Cancer Genome Atlas (TCGA) database. A subsequ...

  2. BSND and ATP6V1G3: Novel Immunohistochemical Markers for Chromophobe Renal Cell Carcinoma

    Science.gov (United States)

    Shinmura, Kazuya; Igarashi, Hisaki; Kato, Hisami; Koda, Kenji; Ogawa, Hiroshi; Takahashi, Seishiro; Otsuki, Yoshiro; Yoneda, Tatsuaki; Kawanishi, Yuichi; Funai, Kazuhito; Takayama, Tatsuya; Ozono, Seiichiro; Sugimura, Haruhiko

    2015-01-01

    Abstract Differentiating between chromophobe renal cell carcinoma (RCC) and other RCC subtypes can be problematic using routine light microscopy. This study aimed to identify novel immunohistochemical markers useful for a differential diagnosis between chromophobe RCC and other RCC subtypes. We selected 3 genes (including BSND and ATP6V1G3) that showed specific transcriptional expression in chromophobe RCC using expression data (n = 783) from The Cancer Genome Atlas (TCGA) database. A subsequent immunohistochemical examination of 186 RCCs obtained in our patient series resulted in a strong diffuse positivity of BSND and ATP6V1G3 proteins (both of which are involved in the regulation of membrane transport) in all the chromophobe RCC specimens (23/23 cases, 100%) but not in the clear cell RCC specimens (0/153 cases, 0%) or the papillary RCC specimens (0/10 cases, 0%). BSND and ATP6V1G3 protein expressions were also detected in renal oncocytoma (13/14 cases, 92.9%) and in the distal nephron, including the collecting duct, in the normal kidney. A computational analysis of TCGA data suggested that DNA methylation was involved in the differential expression pattern of both genes among RCC subtypes. Finally, an immunohistochemical analysis showed lung carcinomas were negative (0/85 cases, 0%) for the expression of both proteins. These results suggest that BSND and ATP6V1G3 are excellent novel immunohistochemical markers for differentiating between chromophobe RCC and other subtypes of RCC, including clear cell and papillary RCCs.

  3. Evaluation of the Early Access STR Kit v1 on the Ion Torrent PGM™ platform.

    Science.gov (United States)

    Guo, Fei; Zhou, Yishu; Liu, Feng; Yu, Jiao; Song, He; Shen, Hongying; Zhao, Bin; Jia, Fei; Hou, Guangwei; Jiang, Xianhua

    2016-07-01

    The Early Access STR Kit v1 is designed to detect 25-plex loci with next generation sequencing (NGS) technology on the Ion Torrent PGM™ platform, including 16 of 20 expanded Combined DNA Index System (CODIS) core loci (CSF1PO, D1S1656, D2S1338, D2S441, D3S1358, D5S818, D7S820, D8S1179, D10S1248, D13S317, D16S539, D19S433, D21S11, TH01, TPOX and vWA), 8 non-CODIS core loci (D1S1677, D2S1776, D4S2408, D5S2500.AC008791, D6S1043, D6S474, D9S2157 and D14S1434) and Amelogenin. In this study, we compared the Early Access STR Kit v1 with the Ion Torrent™ HID STR 10-plex to find out its improvements and explored an appropriate analytical threshold to enhance the performance. In addition, seven experiments were conducted to evaluate the Early Access STR Kit v1 such as studies of repeatability, concordance, sensitivity, mixtures, degraded samples, case-type samples and pedigrees. Other than a little discordance (0.95%) with CE-STR results observed at D21S11, NGS-STR results correctly reflected the sample being tested. Repeatable results were obtained from both initial PCRs and emPCRs aside from a few variations of allele coverage. Full profiles could be obtained from 100pg input DNA and >48.84% profiles from 10pg input DNA. Mixtures were easily detected at 9:1 and 1:9 ratios. This system could be adapted to case-type samples and degraded samples. As a whole, the Early Access STR Kit v1 is a robust, reliable and reproducible assay for NGS-STR typing and a potential tool for human identification. PMID:27082757

  4. GEOCLIM reloaded (v 1.0): a new coupled earth system model for past climate change

    OpenAIRE

    S. Arndt; Regnier, P.; Y. Goddéris; Y. Donnadieu

    2011-01-01

    We present a new version of the coupled Earth system model GEOCLIM. The new release, GEOCLIM reloaded (v 1.0), links the existing atmosphere and weathering modules to a novel, temporally and spatially resolved model of the global ocean circulation, which provides a physical framework for a mechanistic description of the marine biogeochemical dynamics of carbon, nitrogen, phosphorus and oxygen. The ocean model is also coupled to a fully formulated, vertically resolved diagenetic model. GEOCLIM...

  5. Poblano v1.0 : a Matlab toolbox for gradient-based optimization.

    Energy Technology Data Exchange (ETDEWEB)

    Dunlavy, Daniel M.; Acar, Evrim (Sandia National Laboratories, Livermore, CA); Kolda, Tamara Gibson (Sandia National Laboratories, Livermore, CA)

    2010-03-01

    We present Poblano v1.0, a Matlab toolbox for solving gradient-based unconstrained optimization problems. Poblano implements three optimization methods (nonlinear conjugate gradients, limited-memory BFGS, and truncated Newton) that require only first order derivative information. In this paper, we describe the Poblano methods, provide numerous examples on how to use Poblano, and present results of Poblano used in solving problems from a standard test collection of unconstrained optimization problems.

  6. Precise visuotopic organization of the blind spot representation in primate V1.

    Science.gov (United States)

    Azzi, João C B; Gattass, Ricardo; Lima, Bruss; Soares, Juliana G M; Fiorani, Mario

    2015-06-01

    The optic disk is a region of the retina consisting mainly of ganglion cell axons and blood vessels, which generates a visual scotoma known as the blind spot (BS). Information present in the surroundings of the BS can be used to complete the missing information. However, the neuronal mechanisms underlying these perceptual phenomena are poorly understood. We investigate the topography of the BS representation (BSR) in cortical area V1 of the capuchin monkey, using single and multiple electrodes. Receptive fields (RFs) of neurons inside the BSR were investigated using two distinct automatic bias-free mapping methods. The first method (local mapping) consisted of randomly flashing small white squares. For the second mapping method (global mapping), we used a single long bar that moved in one of eight directions. The latter stimulus was capable of eliciting neuronal activity inside the BSR, possibly attributable to long-range surround activity taking place outside the borders of the BSR. Importantly, we found that the neuronal activity inside the BSR is organized topographically in a manner similar to that found in other portions of V1. On average, the RFs inside the BS were larger than those outside. However, no differences in orientation or direction tuning were found between the two regions. We propose that area V1 exhibits a continuous functional topographic map, which is not interrupted in the BSR, as expected by the distribution of photoreceptors in the retina. Thus V1 topography is better described as "visuotopic" rather than as a discontinuous "retinotopic" map. PMID:25761953

  7. Context matters: the illusive simplicity of macaque V1 receptive fields.

    Science.gov (United States)

    Haslinger, Robert; Pipa, Gordon; Lima, Bruss; Singer, Wolf; Brown, Emery N; Neuenschwander, Sergio

    2012-01-01

    Even in V1, where neurons have well characterized classical receptive fields (CRFs), it has been difficult to deduce which features of natural scenes stimuli they actually respond to. Forward models based upon CRF stimuli have had limited success in predicting the response of V1 neurons to natural scenes. As natural scenes exhibit complex spatial and temporal correlations, this could be due to surround effects that modulate the sensitivity of the CRF. Here, instead of attempting a forward model, we quantify the importance of the natural scenes surround for awake macaque monkeys by modeling it non-parametrically. We also quantify the influence of two forms of trial to trial variability. The first is related to the neuron's own spike history. The second is related to ongoing mean field population activity reflected by the local field potential (LFP). We find that the surround produces strong temporal modulations in the firing rate that can be both suppressive and facilitative. Further, the LFP is found to induce a precise timing in spikes, which tend to be temporally localized on sharp LFP transients in the gamma frequency range. Using the pseudo R(2) as a measure of model fit, we find that during natural scene viewing the CRF dominates, accounting for 60% of the fit, but that taken collectively the surround, spike history and LFP are almost as important, accounting for 40%. However, overall only a small proportion of V1 spiking statistics could be explained (R(2)∼5%), even when the full stimulus, spike history and LFP were taken into account. This suggests that under natural scene conditions, the dominant influence on V1 neurons is not the stimulus, nor the mean field dynamics of the LFP, but the complex, incoherent dynamics of the network in which neurons are embedded. PMID:22802940

  8. BSND and ATP6V1G3: Novel Immunohistochemical Markers for Chromophobe Renal Cell Carcinoma.

    Science.gov (United States)

    Shinmura, Kazuya; Igarashi, Hisaki; Kato, Hisami; Koda, Kenji; Ogawa, Hiroshi; Takahashi, Seishiro; Otsuki, Yoshiro; Yoneda, Tatsuaki; Kawanishi, Yuichi; Funai, Kazuhito; Takayama, Tatsuya; Ozono, Seiichiro; Sugimura, Haruhiko

    2015-06-01

    Differentiating between chromophobe renal cell carcinoma (RCC) and other RCC subtypes can be problematic using routine light microscopy. This study aimed to identify novel immunohistochemical markers useful for a differential diagnosis between chromophobe RCC and other RCC subtypes. We selected 3 genes (including BSND and ATP6V1G3) that showed specific transcriptional expression in chromophobe RCC using expression data (n = 783) from The Cancer Genome Atlas (TCGA) database. A subsequent immunohistochemical examination of 186 RCCs obtained in our patient series resulted in a strong diffuse positivity of BSND and ATP6V1G3 proteins (both of which are involved in the regulation of membrane transport) in all the chromophobe RCC specimens (23/23 cases, 100%) but not in the clear cell RCC specimens (0/153 cases, 0%) or the papillary RCC specimens (0/10 cases, 0%). BSND and ATP6V1G3 protein expressions were also detected in renal oncocytoma (13/14 cases, 92.9%) and in the distal nephron, including the collecting duct, in the normal kidney. A computational analysis of TCGA data suggested that DNA methylation was involved in the differential expression pattern of both genes among RCC subtypes. Finally, an immunohistochemical analysis showed lung carcinomas were negative (0/85 cases, 0%) for the expression of both proteins. These results suggest that BSND and ATP6V1G3 are excellent novel immunohistochemical markers for differentiating between chromophobe RCC and other subtypes of RCC, including clear cell and papillary RCCs. PMID:26091477

  9. Synoptic Pan-European Landslide Susceptibility Assessment: The ELSUS 1000 v1 Map

    OpenAIRE

    Gunther, Andreas; HERVAS JAVIER; Van Den Eeckhaut, Miet; Malet, Jean-Philippe; Reichenbach, Paola

    2014-01-01

    In order to identify areas in Europe susceptible to landslides in the context of the EU Soil Thematic Strategy and the associated Proposal for a Soil Framework Directive, a harmonised approach encompassing geographically-nested susceptibility assessments (“Tiers”) and, where possible, the use of comparable datasets as input criteria for susceptibility modelling was devised. The first version of the 1 km grid size European Landslide Susceptibility Map (ELSUS 1000 v1), covering the EU and neigh...

  10. Neural activities in V1 create the bottom-up saliency map of natural scenes.

    Science.gov (United States)

    Chen, Cheng; Zhang, Xilin; Wang, Yizhou; Zhou, Tiangang; Fang, Fang

    2016-06-01

    A saliency map is the bottom-up contribution to the deployment of exogenous attention. It, as well as its underlying neural mechanism, is hard to identify because of the influence of top-down signals. A recent study showed that neural activities in V1 could create a bottom-up saliency map (Zhang et al. in Neuron 73(1):183-192, 2012). In this paper, we tested whether their conclusion can generalize to complex natural scenes. In order to avoid top-down influences, each image was presented with a low contrast for only 50 ms and was followed by a high contrast mask, which rendered the whole image invisible to participants (confirmed by a forced-choice test). The Posner cueing paradigm was adopted to measure the spatial cueing effect (i.e., saliency) by an orientation discrimination task. A positive cueing effect was found, and the magnitude of the cueing effect was consistent with the saliency prediction of a computational saliency model. In a following fMRI experiment, we used the same masked natural scenes as stimuli and measured BOLD signals responding to the predicted salient region (relative to the background). We found that the BOLD signal in V1, but not in other cortical areas, could well predict the cueing effect. These results suggest that the bottom-up saliency map of natural scenes could be created in V1, providing further evidence for the V1 saliency theory (Li in Trends Cogn Sci 6(1):9-16, 2002). PMID:26879771

  11. METEOR v1.0 - Design and structure of the software package

    International Nuclear Information System (INIS)

    This script describes the structure and the separated modules of the software package METEOR for the statistical analysis of meteorological data series. It contains a systematic description of the subroutines of METEOR and, also, of the required shape for input and output files. The original version of METEOR have been developed by Ph.D. Elena Palomo, CIEMAT-IER, GIMASE. It is built by linking programs and routines written in FORTRAN 77 and it adds thc graphical capabilities of GNUPLOT. The shape of this toolbox was designed following the criteria of modularity, flexibility and agility criteria. All the input, output and analysis options are structured in three main menus: i) the first is aimed to evaluate the quality of the data set; ii) the second is aimed for pre-processing of the data; and iii) the third is aimed towards the statistical analyses and for creating the graphical outputs. Actually the information about METEOR is constituted by three documents written in spanish: 1) METEOR v1.0: User's guide; 2) METEOR v1.0: A usage example; 3) METEOR v 1.0: Design and structure of the software package. (Author)

  12. Outbursting Comet P/2010 V1 (Ikeya-Murakami): A Miniature Comet Holmes

    CERN Document Server

    Ishiguro, Masateru; Hanayama, Hidekazu; Usui, Fumihiko; Sekiguchi, Tomohiko; Yanagisawa, Kenshi; Kuroda, Daisuke; Yoshida, Michitoshi; Ohta, Kouji; Kawai, Nobuyuki; Miyaji, Takeshi; Fukushima, Hideo; Watanabe, Jun-ichi

    2014-01-01

    Short-period comet P/2010 V1 (Ikeya-Murakami, hereafter V1) was discovered visually by two amateur astronomers. The appearance of the comet was peculiar, consisting of an envelope, a spherical coma near the nucleus and a tail extending in the anti-solar direction. We investigated the brightness and the morphological development of the comet by taking optical images with ground-based telescopes. Our observations show that V1 experienced a large-scale explosion between UT 2010 October 31 and November 3. The color of the comet was consistent with the Sun (g'-RC=0.61+-0.20, RC-IC=0.20+-0.20, and B-RC=0.93+-0.25), suggesting that dust particles were responsible for the brightening. We used a dynamical model to understand the peculiar morphology, and found that the envelope consisted of small grains (0.3-1 micron) expanding at a maximum speed of 500+-40 m/s, while the tail and coma were composed of a wider range of dust particle sizes (0.4-570 micron) and expansion speeds 7-390 m/s. The total mass of ejecta is ~5x1...

  13. Septal oxytocin administration impairs peer affiliation via V1a receptors in female meadow voles.

    Science.gov (United States)

    Anacker, Allison M J; Christensen, Jennifer D; LaFlamme, Elyssa M; Grunberg, Diana M; Beery, Annaliese K

    2016-06-01

    The peptide hormone oxytocin (OT) plays an important role in social behaviors, including social bond formation. In different contexts, however, OT is also associated with aggression, social selectivity, and reduced affiliation. Female meadow voles form social preferences for familiar same-sex peers under short, winter-like day lengths in the laboratory, and provide a means of studying affiliation outside the context of reproductive pair bonds. Multiple lines of evidence suggest that the actions of OT in the lateral septum (LS) may decrease affiliative behavior, including greater density of OT receptors in the LS of meadow voles that huddle less. We infused OT into the LS of female meadow voles immediately prior to cohabitation with a social partner to determine its effects on partner preference formation. OT prevented the formation of preferences for the partner female. Co-administration of OT with a specific OT receptor antagonist did not reverse the effect, but co-administration of OT with a specific vasopressin 1a receptor (V1aR) antagonist did, indicating that OT in the LS likely acted through V1aRs to decrease partner preference. Receptor autoradiography revealed dense V1aR binding in the LS of female meadow voles. These results suggest that the LS is a brain region that may be responsible for inhibitory effects of OT administration on affiliation, which will be important to consider in therapeutic administrations of OT. PMID:26974500

  14. Spatial Attention and Temporal Expectation Under Timed Uncertainty Predictably Modulate Neuronal Responses in Monkey V1.

    Science.gov (United States)

    Sharma, Jitendra; Sugihara, Hiroki; Katz, Yarden; Schummers, James; Tenenbaum, Joshua; Sur, Mriganka

    2015-09-01

    The brain uses attention and expectation as flexible devices for optimizing behavioral responses associated with expected but unpredictably timed events. The neural bases of attention and expectation are thought to engage higher cognitive loci; however, their influence at the level of primary visual cortex (V1) remains unknown. Here, we asked whether single-neuron responses in monkey V1 were influenced by an attention task of unpredictable duration. Monkeys covertly attended to a spot that remained unchanged for a fixed period and then abruptly disappeared at variable times, prompting a lever release for reward. We show that monkeys responded progressively faster and performed better as the trial duration increased. Neural responses also followed monkey's task engagement-there was an early, but short duration, response facilitation, followed by a late but sustained increase during the time monkeys expected the attention spot to disappear. This late attentional modulation was significantly and negatively correlated with the reaction time and was well explained by a modified hazard function. Such bimodal, time-dependent changes were, however, absent in a task that did not require explicit attentional engagement. Thus, V1 neurons carry reliable signals of attention and temporal expectation that correlate with predictable influences on monkeys' behavioral responses. PMID:24836689

  15. Robust Supersolidity in the V1- V2 Extended Bose-Hubbard Model

    Science.gov (United States)

    Greene, Nicole; Pixley, Jedediah

    2016-05-01

    Motivated by ultra-cold atomic gases with long-range interactions in an optical lattice we study the effects of the next-nearest neighbor interaction on the extended Bose-Hubbard model on a square lattice. Using the variational Gutzwiller approach with a four-site unit cell we determine the ground state phase diagrams as a function of the model parameters. We focus on the interplay of each interaction between the nearest neighbor (V1) , the next-nearest neighbor (V2) , and the onsite repulsion (U). We find various super-solid phases that can be described by one of the ordering wave-vectors (π, 0), (0, π) , and (π, π) . In the limits V1, V2 U we find phases reminiscent of the limit V2 = 0 but with a richer super solid structure. For V1 qualitatively new super solid phase that is quite stable and occupies a large region of the phase diagram. For sufficiently strong interactions we find various Mott and charge density wave (CDW) insulating phases that can be understood in the classical limit (i.e. no inter-site tunneling). We characterize the nature of each quantum phase transition between Mott/CDW to super-solid to superfluid at the mean field level.

  16. Robust Supersolidity in the V1- V2 Extended Bose-Hubbard Model

    Science.gov (United States)

    Greene, Nicole; Pixley, Jedediah

    2016-05-01

    Motivated by ultra-cold atomic gases with long-range interactions in an optical lattice we study the effects of the next-nearest neighbor interaction on the extended Bose-Hubbard model on a square lattice. Using the variational Gutzwiller approach with a four-site unit cell we determine the ground state phase diagrams as a function of the model parameters. We focus on the interplay of each interaction between the nearest neighbor (V1) , the next-nearest neighbor (V2) , and the onsite repulsion (U). We find various super-solid phases that can be described by one of the ordering wave-vectors (π, 0), (0, π) , and (π, π) . In the limits V1, V2 U we find phases reminiscent of the limit V2 = 0 but with a richer super solid structure. For V1

  17. Responsiveness of the major birch allergen Bet v 1 scaffold to the gastric environment: Impact on structure and allergenic activity

    DEFF Research Database (Denmark)

    Sancho, Ana I; Wangorsch, Andrea; Jensen, Bettina M;

    2011-01-01

    Four Bet v 1 homologous food allergens from celeriac (rApi g 1), apple (rMal d 1), peach (rPru p 1) and hazelnut (rCor a 1), were used to probe the structural responsiveness of the Bet v 1 scaffold to gastric digestion conditions and its impact on allergenicity.......Four Bet v 1 homologous food allergens from celeriac (rApi g 1), apple (rMal d 1), peach (rPru p 1) and hazelnut (rCor a 1), were used to probe the structural responsiveness of the Bet v 1 scaffold to gastric digestion conditions and its impact on allergenicity....

  18. Structures of HIV-1-Env V1V2 with broadly neutralizing antibodies reveal commonalities that enable vaccine design

    OpenAIRE

    Gorman, Jason; Soto, Cinque; Yang, Max M.; Davenport, Thaddeus M.; Guttman, Miklos; Robert T Bailer; Chambers, Michael; Chuang, Gwo-Yu; DeKosky, Brandon J.; Doria-Rose, Nicole A.; Druz, Aliaksandr; Ernandes, Michael J.; Georgiev, Ivelin S.; Jarosinski, Marissa C.; Joyce, M. Gordon

    2015-01-01

    Broadly neutralizing antibodies (bNAbs) against HIV-1-Env V1V2 arise in multiple donors. However, atomic-level interactions had only been determined with antibodies from a single donor, making commonalities in recognition uncertain. Here we report the co-crystal structure of V1V2 with antibody CH03 from a second donor and model Env interactions of antibody CAP256-VRC26 from a third. These V1V2-directed bNAbs utilized strand-strand interactions between a protruding antibody loop and a V1V2 str...

  19. Plasma reactor

    OpenAIRE

    Molina Mansilla, Ricardo; Erra Serrabasa, Pilar; Bertrán Serra, Enric

    2008-01-01

    [EN] A plasma reactor that can operate in a wide pressure range, from vacuum and low pressures to atmospheric pressure and higher pressures. The plasma reactor is also able to regulate other important settings and can be used for processing a wide range of different samples, such as relatively large samples or samples with rough surfaces.

  20. Reactor physics

    International Nuclear Information System (INIS)

    Progress in research on reactor physics in 1997 at the Belgian Nuclear Research Centre SCK/CEN is described. Activities in the following four domains are discussed: core physics, ex-core neutron transport, experiments in Materials Testing Reactors, international benchmarks

  1. International Conference Nuclear Energy in Central Europe 99, V. 1. Proceedings

    International Nuclear Information System (INIS)

    International Conference Nuclear Energy in Central Europe is an annual meeting of the Nuclear Society of Slovenia. The proceedings contain 101 articles from Slovenia, surrounding countries and countries of the Central and Eastern European Region. Topics are: Reactor Physics, Research Reactors, Thermal Hydraulics, Structural Analysis, Probabilistic Safety Assessment, Severe Accidents, NPP Operation, Nuclear Energy and Public, Radioactive Waste, Radiological Protection and Environmental Issues, Nuclear Methods and Monte Carlo and Deterministic Transport Calculations

  2. Effects of grain size on high temperature creep of fine grained, solution and dispersion hardened V-1.6Y-8W-0.8TiC

    International Nuclear Information System (INIS)

    Creep resistance is the major concern of vanadium and its alloys for fusion reactor structural applications. In order to elucidate the effects of grain size on the creep behavior of solution and dispersion strengthened vanadium alloys, V-1.6Y-8W-0.8TiC specimens with fine grain sizes from 0.58 to 1.45 μm were prepared by mechanical alloying and HIP without any plastic working and tested at 1073 K and 250 MPa in vacuum. It is shown that the creep resistance of V-1.6Y-8W-0.8TiC depends strongly on grain size and increases with increasing grain size: The creep life for the grain size of 1.45 μm is almost one order longer than that of 0.58 μm, and about two orders longer than that of V-4Cr-4Ti (NIFS-Heat 2) although the grain size of V-4Cr-4Ti is as large as 17.8 μm. The observed creep behavior is discussed in terms of grain size effects on dislocation glide and grain boundary sliding.

  3. Compact Reactor

    International Nuclear Information System (INIS)

    Weyl's Gauge Principle of 1929 has been used to establish Weyl's Quantum Principle (WQP) that requires that the Weyl scale factor should be unity. It has been shown that the WQP requires the following: quantum mechanics must be used to determine system states; the electrostatic potential must be non-singular and quantified; interactions between particles with different electric charges (i.e. electron and proton) do not obey Newton's Third Law at sub-nuclear separations, and nuclear particles may be much different than expected using the standard model. The above WQP requirements lead to a potential fusion reactor wherein deuterium nuclei are preferentially fused into helium nuclei. Because the deuterium nuclei are preferentially fused into helium nuclei at temperatures and energies lower than specified by the standard model there is no harmful radiation as a byproduct of this fusion process. Therefore, a reactor using this reaction does not need any shielding to contain such radiation. The energy released from each reaction and the absence of shielding makes the deuterium-plus-deuterium-to-helium (DDH) reactor very compact when compared to other reactors, both fission and fusion types. Moreover, the potential energy output per reactor weight and the absence of harmful radiation makes the DDH reactor an ideal candidate for space power. The logic is summarized by which the WQP requires the above conditions that make the prediction of DDH possible. The details of the DDH reaction will be presented along with the specifics of why the DDH reactor may be made to cause two deuterium nuclei to preferentially fuse to a helium nucleus. The presentation will also indicate the calculations needed to predict the reactor temperature as a function of fuel loading, reactor size, and desired output and will include the progress achieved to date

  4. Outbursting comet P/2010 V1 (Ikeya-Murakami): A miniature comet Holmes

    International Nuclear Information System (INIS)

    The short-period comet P/2010 V1 (Ikeya-Murakami, hereafter V1) was discovered visually by two amateur astronomers. The appearance of the comet was peculiar, consisting of an envelope, a spherical coma near the nucleus and a tail extending in the anti-solar direction. We investigated the brightness and the morphological development of the comet by taking optical images with ground-based telescopes. Our observations show that V1 experienced a large-scale explosion between UT 2010 October 31 and November 3. The color of the comet was consistent with the Sun (g' – R C = 0.61 ± 0.20, R C – I C = 0.20 ± 0.20, and B – R C = 0.93 ± 0.25), suggesting that dust particles were responsible for the brightening. We used a dynamical model to understand the peculiar morphology, and found that the envelope consisted of small grains (0.3-1 μm) expanding at a maximum speed of 500 ± 40 m s–1, while the tail and coma were composed of a wider range of dust particle sizes (0.4-570 μm) and expansion speeds 7-390 m s–1. The total mass of ejecta is ∼5 × 108 kg and kinetic energy ∼5 × 1012 J. These values are much smaller than in the historic outburst of 17P/Holmes in 2007, but the energy per unit mass (1 × 104 J kg–1) is comparable. The energy per unit mass is about 10% of the energy released during the crystallization of amorphous water ice suggesting that crystallization of buried amorphous ice can supply the mass and energy of the outburst ejecta.

  5. Outbursting comet P/2010 V1 (Ikeya-Murakami): A miniature comet Holmes

    Energy Technology Data Exchange (ETDEWEB)

    Ishiguro, Masateru [Department of Physics and Astronomy, Seoul National University, Gwanak, Seoul 151-742 (Korea, Republic of); Jewitt, David [Department of Earth, Planetary and Space Sciences, University of California at Los Angeles, 595 Charles Young Drive East, Los Angeles, CA 90095-1567 (United States); Hanayama, Hidekazu; Miyaji, Takeshi; Fukushima, Hideo; Watanabe, Jun-ichi [Ishigakijima Astronomical Observatory, National Astronomical Observatory of Japan, Ishigaki, Okinawa 907-0024 (Japan); Usui, Fumihiko [Department of Astronomy, Graduate School of Science, The University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-0033 (Japan); Sekiguchi, Tomohiko [Department of Teacher Training, Hokkaido University of Education, 9 Hokumon, Asahikawa 070-8621 (Japan); Yanagisawa, Kenshi; Kuroda, Daisuke [Okayama Astrophysical Observatory, National Astronomical Observatory of Japan, Asaguchi, Okayama 719-0232 (Japan); Yoshida, Michitoshi [Hiroshima Astrophysical Science Center, Hiroshima University, 1-3-1 Kagamiyama, Higashi-Hiroshima, Hiroshima 739-8526 (Japan); Ohta, Kouji [Department of Astronomy, Kyoto University, Kyoto 606-8502 (Japan); Kawai, Nobuyuki [Department of Physics, Tokyo Institute of Technology, 2-12-1 Ookayama, Meguro-ku, Tokyo 152-8551 (Japan)

    2014-05-20

    The short-period comet P/2010 V1 (Ikeya-Murakami, hereafter {sup V}1{sup )} was discovered visually by two amateur astronomers. The appearance of the comet was peculiar, consisting of an envelope, a spherical coma near the nucleus and a tail extending in the anti-solar direction. We investigated the brightness and the morphological development of the comet by taking optical images with ground-based telescopes. Our observations show that V1 experienced a large-scale explosion between UT 2010 October 31 and November 3. The color of the comet was consistent with the Sun (g' – R {sub C} = 0.61 ± 0.20, R {sub C} – I {sub C} = 0.20 ± 0.20, and B – R {sub C} = 0.93 ± 0.25), suggesting that dust particles were responsible for the brightening. We used a dynamical model to understand the peculiar morphology, and found that the envelope consisted of small grains (0.3-1 μm) expanding at a maximum speed of 500 ± 40 m s{sup –1}, while the tail and coma were composed of a wider range of dust particle sizes (0.4-570 μm) and expansion speeds 7-390 m s{sup –1}. The total mass of ejecta is ∼5 × 10{sup 8} kg and kinetic energy ∼5 × 10{sup 12} J. These values are much smaller than in the historic outburst of 17P/Holmes in 2007, but the energy per unit mass (1 × 10{sup 4} J kg{sup –1}) is comparable. The energy per unit mass is about 10% of the energy released during the crystallization of amorphous water ice suggesting that crystallization of buried amorphous ice can supply the mass and energy of the outburst ejecta.

  6. Mechanism of osthole inhibition of vascular Ca(v)1.2 current.

    Science.gov (United States)

    Fusi, Fabio; Sgaragli, Giampietro; Ha, Le Minh; Cuong, Nguyen Manh; Saponara, Simona

    2012-04-01

    Osthole is a coumarin extracted from Cnidium monnieri (L.) Cusson. The medicinal plant is widely used in Vietnamese as well as Chinese traditional medicine as a vasodilating and antihypertensive agent. Here we have tested the proposition that the block of Ca(v)1.2 channels is mainly responsible for its vascular activity. An in-depth analysis of the effect of osthole on Ca(v)1.2 current (I(Ca1.2)) was performed in rat tail artery myocytes using the whole-cell patch-clamp method. Osthole decreased I(Ca1.2) in a concentration- and voltage-dependent manner. At holding potentials of -50 and -80mV, the pIC(50) values were 4.78±0.07 and 4.36±0.08, respectively; the latter corresponded to the drug apparent dissociation constant for resting channels, K(R), of 47.8μM. Osthole speeded up the inactivation kinetics of I(Ca1.2) and shifted the voltage dependence of the inactivation curve to more negative potentials in a concentration-dependent manner, with an apparent dissociation constant for inactivated channels (K(I)) of 6.88μM. Block of I(Ca1.2) was frequency-dependent and the rate of recovery from inactivation was slowed down. In conclusion, osthole is a vascular Ca(v)1.2 channel antagonist stabilizing the channel in its inactivated state. This mechanism may account for the systolic blood pressure reduction induced by the drug in animal models of hypertension and points to osthole as a lead for the development of novel antihypertensive agents. PMID:22329900

  7. GOVORNE ZMOŽNOSTI OTROK V 1. RAZREDU OSNOVNE ŠOLE

    OpenAIRE

    Rosenstein, Nežika

    2015-01-01

    Človeku je dano, da lahko komunicira s svetom s pomočjo govora, ki pa ni prirojen, ampak se ga je potrebno naučiti. Učimo se ga od rojstva in ga utrjujemo celo življenje. Poleg staršev in okolice so zelo pomembni dejavniki razvoja govora vzgojitelji ter šolski učitelji, ki poleg učenja govor razvijajo, spremljajo in opozarjajo na morebitne napake in težave pri govorjenju. V magistrski nalogi z naslovom Govorne zmožnosti otrok v 1. razredu osnovne šole smo v teoretičnem delu predstavili de...

  8. Isotope dependent predissociation in the C1Σ+, v=0 and v=1 states of

    International Nuclear Information System (INIS)

    Rotationally resolved spectral lines in the C-X(1, 0) band of carbon monoxide are investigated under high resolution using a coherent vacuum ultraviolet laser source, continuously tunable near 107 nm. Transition frequencies are determined by calibrating against a reference standard of iodine lines, recorded with saturation spectroscopy in the visible range, yielding an absolute accuracy of 0.003 cm-1 in the vacuum ultraviolet. Improved molecular constants for the excited state are derived and no effects of perturbation are found at the present level of accuracy. Line broadening measurements result in information on the excited state lifetime of the C1Σ+, v = 1 state for five natural isotopomers of carbon monoxide: τ(12C17O) = 280 ps, τ(12C18O) = 210 ps, τ(13C16O) = 295 ps, τ(13C17O) = 160 ps, and τ(13C18O) = 150 ps. Within the accuracy of the present measurements no effects of J-dependent lifetimes were observed, for neither of the isotopomers. In addition direct time domain measurements of the lifetime of the C1Σ+, v = 0 and v = 1 states of the main isotopomer are performed in a pump-probe experiment using a picosecond VUV-laser, yielding τ(12C16O) = 1780 ps for v = 0 and τ(12C16O) = 625 ps for v = 1. For C1Σ+, v = 0 in 12C16O and 13C16O the same lifetime is found; this lifetime matches experimental values of the oscillator strength and hence supports previous results showing pure radiative decay in this state; the error margins however do not exclude some low level of predissociation. The measurements indicate that the C1Σ+, v = 0 state of the 13C18O isotopomer is predissociated with an estimated yield of 17% (i.e. above the level of predissociation for 12C16O.) From the combined data predissociation yields upon excitation of the C1Σ+, v = 1 state are derived, lying in the range 0.84-0.91 for the five less abundant isotopomers; for the main 12C16O isotopomer a strongly deviating predissociation yield of 0.65 is deduced. (orig.)

  9. Modelo hidrológico DR2-2013© SAGA v1.1

    OpenAIRE

    López-Vicente, Manuel; López-Montero, Teresa; Navas Izquierdo, Ana

    2014-01-01

    [EN] The DR2-2013© SAGA v1.1 module is the second programmed version (January 2014) of the third version (June 2013) of the GIS-based water balance Distributed Rainfall-Runoff (DR2) model. The DR2 model estimates for each month of the year the average: i) Time (Tp, s) and ii) volume to ponding, iii) the soil water content or Actual Available Water (Waa, mm), iv) the depth of Effective Cumulative Runoff (CQeff, mm) and the v) Soil Moisture Status (SMS, 7 wetness-drought categories) against wat...

  10. t-channel factorization description of γγ->V1V2

    International Nuclear Information System (INIS)

    A t-channel factorization model is used to estimate cross sections for the processes γγ->V1V2. Whenever V=rho, the width of the rho has been included in the calculations. The channels γγ->rho0rho0, rho0phi, phiphi, ωω, rho0ω and rho+rho- are calculated for two quasi-real photons. Predictions are also given for the process γsup(*)γ->rho0rho0 for virtual photon mass squared Q22. Our results are consistent with all available experimental data. (orig.)

  11. NEUTRONIC REACTOR

    Science.gov (United States)

    Anderson, H.L.

    1960-09-20

    A nuclear reactor is described comprising fissionable material dispersed in graphite blocks, helium filling the voids of the blocks and the spaces therebetween, and means other than the helium in thermal conductive contact with the graphite for removing heat.

  12. NUCLEAR REACTOR

    Science.gov (United States)

    Miller, H.I.; Smith, R.C.

    1958-01-21

    This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

  13. Nuclear reactors

    International Nuclear Information System (INIS)

    This draft chart contains graphical symbols from which the type of (nuclear) reactor can be seen. They will serve as illustrations for graphical sketches. Important features of the individual reactor types are marked out graphically. The user can combine these symbols to characterize a specific reactor type. The basic graphical symbol is a square with a point in the centre. Functional groups can be depicted for closer specification. If two functional groups are not clearly separated, this is symbolized by a dotted line or a channel. Supply and discharge lines for coolant, moderator and fuel are specified in accordance with DIN 2481 and can be further specified by additional symbols if necessary. The examples in the paper show several different reactor types. (orig./AK)

  14. Upgrade of main separation planes (HDR) of steam generator primary and secondary headers and side manholes

    International Nuclear Information System (INIS)

    Repairs performed during the Bohunice V-1 reactor and Bohunice V-2 reactor operation are briefly described. Grooves were repaired in all headers in turn. Crack indications were found in the border area between the austenitic weld deposit and the basic material, and the sealing surfaces of primary header covers were repaired by local grinding-out and welding. Special devices and technologies were developed for this purpose. An upgrade of the main separation planes was elaborated in order to replace nickel seals with graphite-based seals. The upgrade technology has already been applied to 2 pieces of primary header covers, the other upgrade technologies will be applied starting from 1999. (M.D.)

  15. Nuclear energetics as environmentally affable source - present and and future

    International Nuclear Information System (INIS)

    In this paper the situation in nuclear energetics in the world in 2000 year is presented. Climatic changes initiated by burning of the fossil fuels an influence of nuclear energetics are discussed. Author informs that European Union and U.S.A. supports developing of nuclear energetics. Nuclear phobia from radiation risk of some inhabitants is compared with risks of other man activities. Possibilities of the electricity production by alternative sources are compared. Liability of the Slovak Republic for decommissioning of two reactor of the V-1 Jaslovske Bohunice NPP in 2006 and 2008, which is compared with the Program of safety improvement of these reactors are discussed. Author and Slovak Nuclear Society accept gladly the suggestion of government of the Slovak Republic that they reassess this liability. The best alternative for decommissioned Jaslovske Bohunice NPP will be the completion of the 3rd and 4th blocks of the Mochovce NPP

  16. Multifunctional reactors

    OpenAIRE

    Westerterp, K.R.

    1992-01-01

    Multifunctional reactors are single pieces of equipment in which, besides the reaction, other functions are carried out simultaneously. The other functions can be a heat, mass or momentum transfer operation and even another reaction. Multifunctional reactors are not new, but they have received much emphasis in research in the last decade. A survey is given of modern developments and the first successful applications on a large scale. It is explained why their application in many instances is ...

  17. NUCLEAR REACTOR

    Science.gov (United States)

    Anderson, C.R.

    1962-07-24

    A fluidized bed nuclear reactor and a method of operating such a reactor are described. In the design means are provided for flowing a liquid moderator upwardly through the center of a bed of pellets of a nentron-fissionable material at such a rate as to obtain particulate fluidization while constraining the lower pontion of the bed into a conical shape. A smooth circulation of particles rising in the center and falling at the outside of the bed is thereby established. (AEC)

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    In order to reduce neutron embrittlement of the pressue vessel of an LWR, blanked off elements are fitted at the edge of the reactor core, with the same dimensions as the fuel elements. They are parallel to each other, and to the edge of the reactor taking the place of fuel rods, and are plates of neutron-absorbing material (stainless steel, boron steel, borated Al). (HP)

  19. Breeder reactors

    International Nuclear Information System (INIS)

    The reasons for the development of fast reactors are briefly reviewed (a propitious neutron balance oriented towards a maximum uranium burnup) and its special requirements (cooling, fissile material density and reprocessing) discussed. The three stages in the French program of fast reactor development are outlined with Rapsodie at Cadarache, Phenix at Marcoule, and Super Phenix at Creys-Malville. The more specific features of the program of research and development are emphasized: kinetics and the core, the fuel and the components

  20. Uniaxial creep behavior of nanostructured, solution and dispersion hardened V-1.4Y-7W-9Mo-0.7TiC with different grain sizes

    International Nuclear Information System (INIS)

    Highlights: → The major concern for nanostructured V is poor creep resistance due to grain boundary sliding. → Significant enhancement of creep resistance in nanostructured V has been achieved using V-1.4Y-7W-9Mo-0.7TiC. → The enhancement owes to solute W and Mo, dispersoids of Y2O3 and TiC and grain size (GS) adjustment. → The creep life of V-1.4Y-7W-9Mo-0.7TiC increases by a factor 30 by increasing GS from 0.6 to 2.2 μm. → The creep life for 2.2 μm GS is two orders longer than that of primary candidate V-4Cr-4Ti (GS: ∼18 μm). - Abstract: Nanostructured vanadium (V) alloys are expected to exhibit high performance under neutron irradiation environments. However, their ultra-fine or refined grains cause significant decrease in flow stress at high temperatures due to grain boundary sliding (GBS), which is the major concern for their high-temperature structural applications such as future fusion reactors. The contribution of GBS to plastic deformation is known to depend strongly on grain size (GS) and may give more significant influence on long-time creep test results than on short-time tensile test results. In order to improve the creep resistance through elucidation of the effect of GS on the uniaxial creep behavior of nanostructured V alloys, a solution and dispersion hardened V alloy, V-1.4Y-7W-9Mo-0.7TiC (in wt%), with GSs from 0.58 to 2.16 μm was developed by mechanical alloying and HIP processes, followed by annealing at 1473-1773 K, and creep tested at 1073 K and 250 MPa in vacuum. It is shown that the creep resistance of V-1.4Y-7W-9Mo-0.7TiC increases monotonically with GS: The creep life for the alloy with 2.16 μm in GS is as long as 114 h, which is longer by factors of 2-30 than those for the other finer grained alloys and by two orders than that for coarse-grained V-4Cr-4Ti (Nifs heat2, GS: 17.8 μm) that is a primary candidate material for fusion reactor structural applications. The minimum (steady state) creep rate decreases with

  1. Adaptation of the simple or complex nature of V1 receptive fields to visual statistics.

    Science.gov (United States)

    Fournier, Julien; Monier, Cyril; Pananceau, Marc; Frégnac, Yves

    2011-08-01

    Receptive fields in primary visual cortex (V1) are categorized as simple or complex, depending on their spatial selectivity to stimulus contrast polarity. We studied the dependence of this classification on visual context by comparing, in the same cell, the synaptic responses to three classical receptive field mapping protocols: sparse noise, ternary dense noise and flashed Gabor noise. Intracellular recordings revealed that the relative weights of simple-like and complex-like receptive field components were scaled so as to make the same receptive field more simple-like with dense noise stimulation and more complex-like with sparse or Gabor noise stimulations. However, once these context-dependent receptive fields were convolved with the corresponding stimulus, the balance between simple-like and complex-like contributions to the synaptic responses appeared to be invariant across input statistics. This normalization of the linear/nonlinear input ratio suggests a previously unknown form of homeostatic control of V1 functional properties, optimizing the network nonlinearities to the statistical structure of the visual input. PMID:21765424

  2. CaV1.3 as pacemaker channels in adrenal chromaffin cells: specific role on exo- and endocytosis?

    Science.gov (United States)

    Comunanza, Valentina; Marcantoni, Andrea; Vandael, David H; Mahapatra, Satyajit; Gavello, Daniela; Carabelli, Valentina; Carbone, Emilio

    2010-01-01

    Voltage-gated L-type calcium channels (LTCCs) are expressed in adrenal chromaffin cells. Besides shaping the action potential (AP), LTCCs are involved in the excitation-secretion coupling controlling catecholamine release and in Ca (2+) -dependent vesicle retrieval. Of the two LTCCs expressed in chromaffin cells (CaV1.2 and CaV1.3), CaV1.3 possesses the prerequisites for pacemaking spontaneously firing cells: low-threshold, steep voltage-dependence of activation and slow inactivation. By using CaV1 .3 (-/-) KO mice and the AP-clamp it has been possible to resolve the time course of CaV1.3 pacemaker currents, which is similar to that regulating substantia nigra dopaminergic neurons. In mouse chromaffin cells CaV1.3 is coupled to fast-inactivating BK channels within membrane nanodomains and controls AP repolarization. The ability to carry subthreshold Ca (2+) currents and activate BK channels confers to CaV1.3 the unique feature of driving Ca (2+) loading during long interspike intervals and, possibly, to control the Ca (2+) -dependent exocytosis and endocytosis processes that regulate catecholamine secretion and vesicle recycling. PMID:21084859

  3. Post-test analysis of the Bethsy experiment 9.1b with ASTEC V1.2 code for CESAR thermal-hydraulic module validation

    International Nuclear Information System (INIS)

    The CESAR thermal-hydraulic module of ASTEC V1.2 code has been validated by means of the analysis of one experiment carried out in the Bethsy facility which simulates a French 900 MWe PWR reactor. The test under investigation is the loss-of-coolant accident 9.1b test (OECD ISP No. 27) which consists in a 2 inch cold leg break, while the high pressure injection system is assumed to be unavailable. Starting from a Bethsy nodalisation similar to the one employed in PWR reactor applications with the ASTEC code, the Bethsy 9.1b test has been analyzed in detail with CESAR. In order to reduce the discrepancies found between code results and test measurements, some nodalisation improvements have been identified and implemented in the original model by means of sensitivity studies. In the present paper, the results of the code are presented in comparison with the experimental data. The occurrence of major events and the time evolution of main thermal-hydraulic parameters of both primary and secondary circuits are well predicted by CESAR. (author)

  4. Characterization of PR-10 genes from eight Betula species and detection of Bet v 1 isoforms in birch pollen

    Directory of Open Access Journals (Sweden)

    van't Westende Wendy PC

    2009-03-01

    Full Text Available Abstract Background Bet v 1 is an important cause of hay fever in northern Europe. Bet v 1 isoforms from the European white birch (Betula pendula have been investigated extensively, but the allergenic potency of other birch species is unknown. The presence of Bet v 1 and closely related PR-10 genes in the genome was established by amplification and sequencing of alleles from eight birch species that represent the four subgenera within the genus Betula. Q-TOF LC-MSE was applied to identify which PR-10/Bet v 1 genes are actually expressed in pollen and to determine the relative abundances of individual isoforms in the pollen proteome. Results All examined birch species contained several PR-10 genes. In total, 134 unique sequences were recovered. Sequences were attributed to different genes or pseudogenes that were, in turn, ordered into seven subfamilies. Five subfamilies were common to all birch species. Genes of two subfamilies were expressed in pollen, while each birch species expressed a mixture of isoforms with at least four different isoforms. Isoforms that were similar to isoforms with a high IgE-reactivity (Bet v 1a = PR-10.01A01 were abundant in all species except B. lenta, while the hypoallergenic isoform Bet v 1d (= PR-10.01B01 was only found in B. pendula and its closest relatives. Conclusion Q-TOF LC-MSE allows efficient screening of Bet v 1 isoforms by determining the presence and relative abundance of these isoforms in pollen. B. pendula contains a Bet v 1-mixture in which isoforms with a high and low IgE-reactivity are both abundant. With the possible exception of B. lenta, isoforms identical or very similar to those with a high IgE-reactivity were found in the pollen proteome of all examined birch species. Consequently, these species are also predicted to be allergenic with regard to Bet v 1 related allergies.

  5. Olfactory expression of a single and highly variable V1r pheromone receptor-like gene in fish species

    OpenAIRE

    Pfister, Patrick; Rodriguez, Ivan

    2005-01-01

    Sensory neurons expressing members of the seven-transmembrane V1r receptor superfamily allow mice to perceive pheromones. These receptors, which exhibit no sequence homology to any known protein except a weak similarity to taste receptors, have only been found in mammals. In the mouse, the V1r repertoire contains >150 members, which are expressed by neurons of the vomeronasal organ, a structure present exclusively in some tetrapod species. Here, we report the existence of a single V1r gene in...

  6. Research reactors - an overview

    Energy Technology Data Exchange (ETDEWEB)

    West, C.D.

    1997-03-01

    A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs.

  7. SHARP pre-release v1.0 - Current Status and Documentation

    Energy Technology Data Exchange (ETDEWEB)

    Mahadevan, Vijay S. [Argonne National Lab. (ANL), Argonne, IL (United States); Rahaman, Ronald O. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-09-30

    The NEAMS Reactor Product Line effort aims to develop an integrated multiphysics simulation capability for the design and analysis of future generations of nuclear power plants. The Reactor Product Line code suite’s multi-resolution hierarchy is being designed to ultimately span the full range of length and time scales present in relevant reactor design and safety analyses, as well as scale from desktop to petaflop computing platforms. In this report, building on a several previous report issued in September 2014, we describe our continued efforts to integrate thermal/hydraulics, neutronics, and structural mechanics modeling codes to perform coupled analysis of a representative fast sodium-cooled reactor core in preparation for a unified release of the toolkit. The work reported in the current document covers the software engineering aspects of managing the entire stack of components in the SHARP toolkit and the continuous integration efforts ongoing to prepare a release candidate for interested reactor analysis users. Here we report on the continued integration effort of PROTEUS/Nek5000 and Diablo into the NEAMS framework and the software processes that enable users to utilize the capabilities without losing scientific productivity. Due to the complexity of the individual modules and their necessary/optional dependency library chain, we focus on the configuration and build aspects for the SHARP toolkit, which includes capability to autodownload dependencies and configure/install with optimal flags in an architecture-aware fashion. Such complexity is untenable without strong software engineering processes such as source management, source control, change reviews, unit tests, integration tests and continuous test suites. Details on these processes are provided in the report as a building step for a SHARP user guide that will accompany the first release, expected by Mar 2016.

  8. CO (v = 1-0) emission in the molecular shock regions of OMC-1

    Science.gov (United States)

    Grasdalen, G. L.; Hackwell, John A.; Lynch, David K.; Russell, Ray W.

    1992-01-01

    Using the new Aerospace spectrometer on the Kuiper Airborne Observatory, we have obtained observations of the molecular shocks associated with OMC-1. Unexpectedly these observations reveal (b = 1-0) emission from CO at 4.6 microns superposed on a strong continuum. Our observations strongly suggest that both the emission feature and the continuum are produced in molecular shocks. Since the (v = 1-0) band of CO is only excited in high-velocity shocks, we may be observing for the first time the primary driving mechanism in these regions. Even if these features are produced by scattering, the characteristics will provide new constraints on the conditions in and the geometry of the shock regions.

  9. A nomogram of the economic effectiveness of the V-1 nuclear power plant life extension

    International Nuclear Information System (INIS)

    Economic assessment is presented of the concept variants for extending the life of the V-1 nuclear power plant after its reconstruction. The starting assumption is that in 1995 the units of this nuclear power plant will be shut down for reconstruction with the aim to increase the technological safety and for updating and renewing the equipment and circuits. The variant parameters in the evaluation were the shutdown time for the reconstruction, the reconstruction costs, and the year of terminating the plant operation after its reconstruction. A nomogram for determining the specific annual updated costs after extending the life of the power plant units and a table listing these costs are given. (P.A.). 2 figs., 1 tab

  10. Optimize of Deuteron Current of 150 keV, 1 mA Neutron Generator

    International Nuclear Information System (INIS)

    It has been characterized a 150 keV/1 mA Neutron Generator. It has been used some local components, except accelerator tube and vacuum system. To produce neutron, it has been used a deuterium gas bombarded into tritium target through reaction 3H(d,n)4He. For preliminary experiment, we used the air as an ion source. The beam current of deuteron as a function of process parameters are presented in this paper. It's found that the optimum beam current of deuteron was 1000 μA, and this conditions was achieved at accelerations voltage 30 kV, extraction voltage 5 kV, guide voltage -11 kV and vacuum 10-6 mbar. (author)

  11. Reactor utilization

    International Nuclear Information System (INIS)

    In 1962, the RA reactor was operated almost three times more than in 1961, producing total of 25 555 MWh. Diagram containing comparative data about reactor operation for 1960, 1961, and 1962, percent of fuel used and U-235 burnup shows increase in reactor operation. Number of samples irradiated was 659, number of experiments done was 16. mean powered level was 5.93 MW. Fuel was added into the core twice during the reporting year. In fact the core was increased from 56 to 68 fuel channels and later to 84 fuel channels. Fuel was added to the core when the reactivity worth decreased to the minimum operation level due to burnup. In addition to this 5 central fuel channels were exchanged with fresh fuel in february for the purpose of irradiation in the VISA-2 channel

  12. Reactor Neutrinos

    CERN Document Server

    Lasserre, T; Lasserre, Thierry; Sobel, Henry W.

    2005-01-01

    We review the status and the results of reactor neutrino experiments, that toe the cutting edge of neutrino research. Short baseline experiments have provided the measurement of the reactor neutrino spectrum, and are still searching for important phenomena such as the neutrino magnetic moment. They could open the door to the measurement of coherent neutrino scattering in a near future. Middle and long baseline oscillation experiments at Chooz and KamLAND have played a relevant role in neutrino oscillation physics in the last years. It is now widely accepted that a new middle baseline disappearance reactor neutrino experiment with multiple detectors could provide a clean measurement of the last undetermined neutrino mixing angle theta13. We conclude by opening on possible use of neutrinos for Society: NonProliferation of Nuclear materials and Geophysics.

  13. Adaptive behavior of neighboring neurons during adaptation-induced plasticity of orientation tuning in V1

    Directory of Open Access Journals (Sweden)

    Shumikhina Svetlana

    2009-12-01

    Full Text Available Abstract Background Sensory neurons display transient changes of their response properties following prolonged exposure to an appropriate stimulus (adaptation. In adult cat primary visual cortex, orientation-selective neurons shift their preferred orientation after being adapted to a non-preferred orientation. The direction of those shifts, towards (attractive or away (repulsive from the adapter depends mostly on adaptation duration. How the adaptive behavior of a neuron is related to that of its neighbors remains unclear. Results Here we show that in most cases (75%, cells shift their preferred orientation in the same direction as their neighbors. We also found that cells shifting preferred orientation differently from their neighbors (25% display three interesting properties: (i larger variance of absolute shift amplitude, (ii wider tuning bandwidth and (iii larger range of preferred orientations among the cluster of cells. Several response properties of V1 neurons depend on their location within the cortical orientation map. Our results suggest that recording sites with both attractive and repulsive shifts following adaptation may be located in close proximity to iso-orientation domain boundaries or pinwheel centers. Indeed, those regions have a more diverse orientation distribution of local inputs that could account for the three properties above. On the other hand, sites with all cells shifting their preferred orientation in the same direction could be located within iso-orientation domains. Conclusions Our results suggest that the direction and amplitude of orientation preference shifts in V1 depend on location within the orientation map. This anisotropy of adaptation-induced plasticity, comparable to that of the visual cortex itself, could have important implications for our understanding of visual adaptation at the psychophysical level.

  14. Evaluation of the I. Stage of decommissioning and implementation of the II. Stage of decommissioning of NPP V1

    International Nuclear Information System (INIS)

    In this paper author deals with following aspects: 1. Introduction of company Nuclear and Decommissioning Company, plc; 2. Evaluation of the I. stage of decommissioning and implementation of the II. Stage of decommissioning of NPP V1; (author)

  15. Na(v)1.8 channelopathy in mutant mice deficient for myelin protein zero is detrimental to motor axons

    DEFF Research Database (Denmark)

    Alvarez Herrero, Susana; Pinchenko, Volodymyr; Klein, Dennis;

    2011-01-01

    Myelin protein zero mutations were found to produce Charcot-Marie-Tooth disease phenotypes with various degrees of myelin impairment and axonal loss, ranging from the mild 'demyelinating' adult form to severe and early onset forms. Protein zero deficient homozygous mice ( ) show a severe and...... conventional nerve conduction studies, behavioural studies using rotor-rod measurements, and histological measures to assess membrane dysfunction and its progression in protein zero deficient homozygous mutants as compared with age-matched wild-type controls. The involvement of Na(V)1.8 was investigated by...... pharmacologic block using the subtype-selective Na(V)1.8 blocker A-803467 and chronically in Na(V)1.8 knock-outs. We found that in the context of dysmyelination, abnormal potassium ion currents and membrane depolarization, the ectopic Na(V)1.8 channels further impair the motor axon excitability in protein zero...

  16. Nuclear reactors

    International Nuclear Information System (INIS)

    A nuclear reactor has a large prompt negative temperature coefficient of reactivity. A reactor core assembly of a plurality of fluid-tight fuel elements is located within a water-filled tank. Each fuel element contains a solid homogeneous mixture of 50-79 w/o zirconium hydride, 20-50 w/o uranium and 0.5-1.5 W erbium. The uranium is not more than 20 percent enriched, and the ratio of hydrogen atoms to zirconium atoms is between 1.5:1 and 7:1. The core has a long lifetime, E.G., at least about 1200 days

  17. Nuclear reactors

    International Nuclear Information System (INIS)

    In a liquid cooled nuclear reactor, the combination is described for a single-walled vessel containing liquid coolant in which the reactor core is submerged, and a containment structure, primarily of material for shielding against radioactivity, surrounding at least the liquid-containing part of the vessel with clearance therebetween and having that surface thereof which faces the vessel make compatible with the liquid, thereby providing a leak jacket for the vessel. The structure is preferably a metal-lined concrete vault, and cooling means are provided for protecting the concrete against reaching a temperature at which damage would occur. (U.S.)

  18. A Selective V1A Receptor Agonist, Selepressin, Is Superior to Arginine Vasopressin and to Norepinephrine in Ovine Septic Shock*

    OpenAIRE

    He, Xinrong; Su, Fuhong; Taccone, Fabio Silvio; Laporte, Régent; Kjølbye, Anne Louise; Zhang, Jing; Xie, Keliang; Moussa, Mouhamed Djahoum; Reinheimer, Torsten Michael; Vincent, Jean-Louis

    2015-01-01

    Objective: Selective vasopressin V1A receptor agonists may have advantages over arginine vasopressin in the treatment of septic shock. We compared the effects of selepressin, a selective V1A receptor agonist, arginine vasopressin, and norepinephrine on hemodynamics, organ function, and survival in an ovine septic shock model. Design: Randomized animal study. Setting: University hospital animal research laboratory. Subjects: Forty-six adult female sheep. Interventions: Fecal peritonitis was in...

  19. Questioning the Specificity of ASRS-v1.1 to Accurately Detect ADHD in Substance Abusing Populations

    Science.gov (United States)

    Chiasson, Jean-Pierre; Stavro, Katherine; Rizkallah, Elie; Lapierre, Luc; Dussault, Maxime; Legault, Louis; Potvin, Stephane

    2012-01-01

    Objective: To assess the specificity of the Adult ADHD Self-Report Scale (ASRS-v1.1) in detecting ADHD among individuals with substance use disorders (SUDs). Method: A chart review of 183 SUD patients was conducted. Patients were screened for ADHD with the ASRS-v1.1 and were later assessed by a psychiatrist specialized in ADHD. Results: Among SUD…

  20. Ca2+ entry into neurons is facilitated by cooperative gating of clustered CaV1.3 channels

    Science.gov (United States)

    Moreno, Claudia M; Dixon, Rose E; Tajada, Sendoa; Yuan, Can; Opitz-Araya, Ximena; Binder, Marc D; Santana, Luis F

    2016-01-01

    CaV1.3 channels regulate excitability in many neurons. As is the case for all voltage-gated channels, it is widely assumed that individual CaV1.3 channels behave independently with respect to voltage-activation, open probability, and facilitation. Here, we report the results of super-resolution imaging, optogenetic, and electrophysiological measurements that refute this long-held view. We found that the short channel isoform (CaV1.3S), but not the long (CaV1.3L), associates in functional clusters of two or more channels that open cooperatively, facilitating Ca2+ influx. CaV1.3S channels are coupled via a C-terminus-to-C-terminus interaction that requires binding of the incoming Ca2+ to calmodulin (CaM) and subsequent binding of CaM to the pre-IQ domain of the channels. Physically-coupled channels facilitate Ca2+ currents as a consequence of their higher open probabilities, leading to increased firing rates in rat hippocampal neurons. We propose that cooperative gating of CaV1.3S channels represents a mechanism for the regulation of Ca2+ signaling and electrical activity. DOI: http://dx.doi.org/10.7554/eLife.15744.001 PMID:27187148

  1. What does neural plasticity tell us about role of primary visual cortex (V1 in visual awareness?

    Directory of Open Access Journals (Sweden)

    JuhaSilvanto

    2011-01-01

    Full Text Available The complete loss of visual awareness resulting from a lesion to the primary visual cortex (V1 suggests that this region is indispensable for conscious visual perception. There are however a number cases of conscious perception in the absence of V1 which appear to challenge this conclusion. These include reports of patients with bilateral V1 lesions sustained at an early age whose conscious vision has spontaneously recovered, as well as stroke patients who have recovered some conscious vision with the help of rehabilitation programs. In addition, the phenomenon of hemianopic completion and percepts induced by brain stimulation suggest that V1 may not be necessary for conscious perception in all circumstances. Furthermore, that the visual abilities in the cat are associated with the recovery of normal extrastriate tuning properties rather than emulation of V1 functions suggests that there is nothing unique about the functional properties of this region in visual awareness. Rather, the dramatic effect of a V1 lesion on visual awareness may be due to its role in providing the majority of extrastriate visual input, the loss of which abolishes normal neural responsiveness throughout the visual cortex.

  2. Structure of HIV-1 gp120 V1/V2 domain with broadly neutralizing antibody PG9

    Energy Technology Data Exchange (ETDEWEB)

    McLellan, Jason S.; Pancera, Marie; Carrico, Chris; Gorman, Jason; Julien, Jean-Philippe; Khayat, Reza; Louder, Robert; Pejchal, Robert; Sastry, Mallika; Dai, Kaifan; O’Dell, Sijy; Patel, Nikita; Shahzad-ul-Hussan, Syed; Yang, Yongping; Zhang, Baoshan; Zhou, Tongqing; Zhu, Jiang; Boyington, Jeffrey C.; Chuang, Gwo-Yu; Diwanji, Devan; Georgiev, Ivelin; Kwon, Young Do; Lee, Doyung; Louder, Mark K.; Moquin, Stephanie; Schmidt, Stephen D.; Yang, Zhi-Yong; Bonsignori, Mattia; Crump, John A.; Kapiga, Saidi H.; Sam, Noel E.; Haynes, Barton F.; Burton, Dennis R.; Koff, Wayne C.; Walker, Laura M.; Phogat, Sanjay; Wyatt, Richard; Orwenyo, Jared; Wang, Lai-Xi; Arthos, James; Bewley, Carole A.; Mascola, John R.; Nabel, Gary J.; Schief, William R.; Ward, Andrew B.; Wilson, Ian A.; Kwong, Peter D. (UWASH); (NIH); (Scripps); (Duke); (IAVI); (Maryland-MED)

    2012-12-13

    Variable regions 1 and 2 (V1/V2) of human immunodeficiency virus-1 (HIV-1) gp120 envelope glycoprotein are critical for viral evasion of antibody neutralization, and are themselves protected by extraordinary sequence diversity and N-linked glycosylation. Human antibodies such as PG9 nonetheless engage V1/V2 and neutralize 80% of HIV-1 isolates. Here we report the structure of V1/V2 in complex with PG9. V1/V2 forms a four-stranded {beta}-sheet domain, in which sequence diversity and glycosylation are largely segregated to strand-connecting loops. PG9 recognition involves electrostatic, sequence-independent and glycan interactions: the latter account for over half the interactive surface but are of sufficiently weak affinity to avoid autoreactivity. The structures of V1/V2-directed antibodies CH04 and PGT145 indicate that they share a common mode of glycan penetration by extended anionic loops. In addition to structurally defining V1/V2, the results thus identify a paradigm of antibody recognition for highly glycosylated antigens, which - with PG9 - involves a site of vulnerability comprising just two glycans and a strand.

  3. Structures of HIV-1-Env V1V2 with broadly neutralizing antibodies reveal commonalities that enable vaccine design

    Science.gov (United States)

    Gorman, Jason; Soto, Cinque; Yang, Max M.; Davenport, Thaddeus M.; Guttman, Miklos; Bailer, Robert T.; Chambers, Michael; Chuang, Gwo-Yu; DeKosky, Brandon J.; Doria-Rose, Nicole A.; Druz, Aliaksandr; Ernandes, Michael J.; Georgiev, Ivelin S.; Jarosinski, Marissa C.; Joyce, M. Gordon; Lemmin, Thomas M.; Leung, Sherman; Louder, Mark K.; McDaniel, Jonathan R.; Narpala, Sandeep; Pancera, Marie; Stuckey, Jonathan; Wu, Xueling; Yang, Yongping; Zhang, Baoshan; Zhou, Tongqing; Mullikin, James C.; Baxa, Ulrich; Georgiou, George; McDermott, Adrian B.; Bonsignori, Mattia; Haynes, Barton F.; Moore, Penny L.; Morris, Lynn; Lee, Kelly K.; Shapiro, Lawrence; Mascola, John R.; Kwong, Peter D.

    2016-01-01

    Broadly neutralizing antibodies (bNAbs) against HIV-1-Env V1V2 arise in multiple donors. However, atomic-level interactions had only been determined with antibodies from a single donor, making commonalities in recognition uncertain. Here we report the co-crystal structure of V1V2 with antibody CH03 from a second donor and model Env interactions of antibody CAP256-VRC26 from a third. These V1V2-directed bNAbs utilized strand-strand interactions between a protruding antibody loop and a V1V2 strand, but differed in their N-glycan recognition. Ontogeny analysis indicated protruding loops to develop early, with glycan interactions maturing over time. Altogether, the multidonor information suggested V1V2-directed bNAbs to form an ‘extended class’, for which we engineered ontogeny-specific antigens: Env trimers with chimeric V1V2s that interacted with inferred ancestor and intermediate antibodies. The ontogeny-based design of vaccine antigens described here may provide a general means for eliciting antibodies of a desired class. PMID:26689967

  4. Nuclear reactor

    International Nuclear Information System (INIS)

    In an improved reactor core for a high conversion BWR reactor, Pu-breeding type BWR type reactor, Pu-breeding type BWR type rector, FEBR type reactor, etc., two types of fuel assemblies are loaded such that fuel assemblies using a channel box of a smaller irradiation deformation ratio are loaded in a high conversion region, while other fuel assemblies are loaded in a burner region. This enables to suppress the irradiation deformation within an allowable limit in the high conversion region where the fast neutron flux is high and the load weight from the inside of the channel box due to the pressure loss is large. At the same time, the irradiation deformation can be restricted within an allowable limit without deteriorating the neutron economy in the burner region in which fast neutron flux is low and the load weight from the inside of the channel box is small since a channel box with smaller neutron absorption cross section or reduced wall thickness is charged. As a result, it is possible to prevent structural deformations such as swelling of the channel box, bending of the entire assemblies, bending of fuel rods, etc. (K.M.)

  5. Report of the ASSET (Assessment of Safety Significant Events Team) follow-up mission to the Bohunice (units 1-2) nuclear power plant in Slovakia 5-9 July 1993. Root cause analysis of operational events with a view to enhancing the prevention of accidents

    International Nuclear Information System (INIS)

    This Report of the IAEA Assessment of Safety Significant Events Team (ASSET) presents the results of the team's review of the status of implementation of the recommendations made by the 1988 ASSET mission to Bohunice nuclear power plant in Slovakia, and of progress made by plant management in prevention of incidents. The findings, conclusions and suggestions presented herein reflect the views of the ASSET experts. They are provided for consideration by the responsible Slovakian authorities. The ASSET team's views presented in this report are based on review of the documentation made available and on the discussions with plant staff. The report includes the official response of the operating and regulatory organizations of Slovakia to the ASSET findings and conclusions. Figs, tabs

  6. Activation of Wnt/β-catenin signaling by hydrogen peroxide transcriptionally inhibits NaV1.5 expression.

    Science.gov (United States)

    Wang, Ning; Huo, Rong; Cai, Benzhi; Lu, Yan; Ye, Bo; Li, Xiang; Li, Faqian; Xu, Haodong

    2016-07-01

    Oxidants and canonical Wnt/β-catenin signaling have been shown to decrease cardiac Na(+) channel activity by suppressing NaV1.5 expression. Our aims are to determine if hydrogen peroxide (H2O2), one oxidant of reactive oxygen species (ROS), activates Wnt/β-catenin signaling and promotes β-catenin nuclear activity, leading to suppression of NaV1.5 expression and if this suppression requires the interaction of β-catenin with its nuclear partner, TCF4 (also called TCF7L2) to decrease SCN5a promoter activity. The results demonstrated that H2O2 increased β-catenin, but not TCF4 nuclear localization determined by immunofluorescence without affecting total β-catenin protein level. Furthermore, H2O2 exerted a dose- and time-dependent suppressive effect on NaV1.5 expression. RT-PCR and/or Western blot analyses revealed that overexpressing active form of β-catenin or stabilizing β-catenin by GSK-3β inhibitors, LiCl and Bio, suppressed NaV1.5 expression in HL-1 cells. In contrast, destabilization of β-catenin by a constitutively active GSK-3β mutant (S9A) upregulated NaV1.5 expression. Whole-cell recording showed that LiCl significantly inhibited Na(+) channel activity in these cells. Using immunoprecipitation (IP), we showed that β-catenin interacted with TCF4 indicating that β-catenin as a co-transfactor, regulates NaV1.5 expression through TCF4. Analyses of the SCN5a promoter sequences among different species by using VISTA tools indicated that SCN5a promoter harbors TCF4 binding sites. Chromatin IP assays demonstrated that both β-catenin and TCF4 were recruited in the SCN5a promoter, and regulated its activity. Luciferase promoter assays exhibited that β-catenin inhibited the SCN5a promoter activity at a dose-dependent manner and this inhibition required TCF4. Small interfering (Si) RNA targeting β-catenin significantly increased SCN5a promoter activity, leading to enhanced NaV1.5 expression. As expected, β-catenin SiRNA prevents H2O2 suppressive effects

  7. Geomechanical characterisation of unsaturated Kunigel V1 bentonite: swelling and shear strength

    International Nuclear Information System (INIS)

    Document available in extended abstract form only. The development and validation of hydro-geomechanical models for bentonite buffer are one of the important subjects to appropriately evaluate long term behaviour of EBS in radioactive waste disposal. The Barcelona Basic Model (BBM), which is one extension of the modified Cam- Clay model for unsaturated and expansive soil, has been developed and widely applied to several hydro-geomechanical problems by using the coupled THM code, Code-Bright. Some advantages of the model are that hydro-geomechanical characteristics of buffer materials under saturated and partially saturated conditions are taken into account as well as the swelling characteristics due to wetting. Applicability of the BBM to consolidation and swelling behaviour of unsaturated bentonite has already been confirmed. In this study swelling characteristics of unsaturated bentonite are further discussed based on results from controlled-suction odometer tests, and in addition shear strength depending on matric suction is discussed based on controlled-suction triaxial compression tests. Swelling tests of compacted bentonite (Kunigel V1, initial dry density: 1.0 Mg/m3) under constant confined vertical net stresses (20 and 100 kPa) were performed by using controlled-suction odometer cells. Matrice suction was stepwise reduced from 500 kPa to 0 kPa by 100 kPa. It is found that swelling is more dominant in latter step of the suction change (i.e., closer steps to saturation), especially the step from 100 kPa to 0 kPa. Swelling due to wetting, i.e. decrease in matric suction is defined in the BBM. Controlled-suction triaxial compression tests of compacted bentonite (Kunigel V1, initial dry density: 1.36 Mg/m3) under both constant matric suctions (0, 300, and 500 kPa) and constant confined lateral net stresses were performed to study dependency of shear strength on matric suction. It is found that the apparent cohesion linearly increases with increase in matric

  8. The course of the V1 segment of the vertebral artery

    Directory of Open Access Journals (Sweden)

    Ranganatha Sastry V

    2006-01-01

    Full Text Available Background: It has become important to know the exact origin and course of the vertebral artery as well as the percentage of the abnormalities of these variations from the point of view of surgery, angiography and in all non-invasive procedures. In decompressive procedures and for subsequent stabilization procedures of the cervical spine, thorough knowledge of the anatomy of the vertebral artery is mandatory to avoid a potentially catastrophic injury to the vertebral artery. Aims of the Study: The present study was aimed at investigating the frequency of occurrence of the variations of the pre-transverse segment of the vertebral artery especially concerning the level of its entry into the foramen transversarium, tortuosity and size in formalin fixed adult cadavers and fetuses with the view of keeping the surgeons alert regarding the frequency of occurrence of these variations in the local subjects. Materials and Methods: The pre-transverse segment of the vertebral artery (V1 segment was studied in 19 formalin fixed cadavers (6 females and 13 males and ten formalin fixed newborn fetuses. The total length and the diameter of the V1 segment of the vertebral artery were measured in adult cadavers to the nearest millimeter using a sliding caliper. Variations in the level of entry of the vertebral artery in to the foramen transversarium and also tortuosity of the artery were noted down. Results: The vertebral artery measured a mean length of 4.9 ± 1.24 cms and a mean diameter of 3.58 ±1.59 mms. In over 71% of the cases the vertebral artery entered the foramen transversarium at the level of C6. The next highest frequency was C7 (18.42% and in small percentage of the cases at C5 (5.3%, C4 (2.6% and C3 (2.6%. The vertebral artery was found to be tortuous in nine cases (23.7%. Conclusions: Data derived from gross anatomical studies serve as an indicator of prevalence of variations within a population group. But it would be safest for the surgeon to

  9. Nuclear magnetic resonance properties of water-rich gels of Kunigel-V1 bentonite

    International Nuclear Information System (INIS)

    Kunigel-V1 bentonite was analyzed by proton nuclear magnetic resonance (NMR) spectroscopy over a wide range of water content and temperature at 0.47 T. Kunigel-V1 is a bentonite clay consisting of ∼50 wt% Na-rich montmorillonite from Yamagata, Japan, and represents a candidate for engineered barriers of underground nuclear waste disposal sites in Japan. The NMR-related properties of bentonite are also important with respect to application of the material as a mud in boreholes for NMR well logging in the geophysical exploration of disposal sites. The proton relaxation times, surface relaxivity of montmorillonite, and H2O self-diffusion coefficient, were determined in this study for water-rich gel samples of bentonite at 11.0 to 70.0degC and for bentonite weight fractions of 0 to 37.7 wt%. The proton relaxation times (T1 and T2) were measured by the inversion recovery method and Carr-Purcell-Meiboom-Gill method, respectively, and the self-diffusion coefficient of H2O molecules (D) was measured by the pulsed-gradient spin-echo method. The results showed that T1, T2, and D increased with increasing temperature, and decreased with increasing bentonite weight fraction (ω). The T1 and T2 surface-relaxivities were on the order of 10-7 m/s and also decreased with temperature. The activation energies of the T1 and T2 relaxation for the bentonite gels were significantly lower than those for bulk water (i.e., about 50 to 70%), whereas the activation energy of the diffusion process for the gels was nearly equal to that for bulk water. As a result, the normalized H2O self-diffusivity, D/D0, obeys a temperature-independent master curve described by ln(D/D0)=1.54[exp(-0.0377ω)-1], where D0 is D in bulk water and ω is in wt%. (author)

  10. Vinpocetine is a potent blocker of rat NaV1.8 tetrodotoxin-resistant sodium channels.

    Science.gov (United States)

    Zhou, Xiaoping; Dong, Xiao-Wei; Crona, James; Maguire, Maureen; Priestley, Tony

    2003-08-01

    Vinpocetine is a clinically used synthetic vincamine derivative with a diverse pharmacological profile that includes action at several ion channels, principally "generic" populations of sodium channels that give rise to tetrodotoxin-sensitive conductances. A number of cell types are known to express tetrodotoxin-resistant (TTXr) sodium conductances, the molecular bases of which have remained elusive until recently. One such TTXr channel, termed NaV1.8, is of particular interest because of its prominent and selective expression in peripheral afferent nerves. The effects of vinpocetine on TTXr channels specifically, are unknown. We have assessed the effects of the drug on cloned rat NaV1.8 channels expressed in a dorsal root ganglion-derived cell line, ND7/23. Vinpocetine produced a concentration- and state-dependent inhibition of NaV1.8 sodium channel activity. Voltage-clamp experiments revealed an approximately 3-fold increase in vinpocetine potency when whole-cell NaV1.8 conductances were elicited from relatively depolarized potentials (-35 mV; IC50 = 3.5 microM) compared with hyperpolarized holding potentials (-90 mV; IC50 = 10.4 microM). Vinpocetine also produced an approximately 22 mV leftward shift in the voltage dependence of NaV1.8 channel inactivation but did not affect the voltage range of channel activation. These properties are reminiscent of several other known sodium channel blockers and suggested that vinpocetine may exhibit frequency-dependent block. Accordingly, tonic block of NaV1.8 channels by vinpocetine (3 microM) increased proportionally with increasing depolarizing commands over the frequency range 0.1 to 1Hz. In summary, the present data demonstrate that vinpocetine is capable of blocking NaV1.8 sodium channel activity and suggest a potential additional utility in various sensory abnormalities arising from abnormal peripheral nerve activity. PMID:12730276

  11. Proceedings of the third international conference on containment design and operation. v.1

    International Nuclear Information System (INIS)

    The second international conference on containment design and operation included sessions on the following topics: performance and regulatory requirements; radionuclide behaviour; severe accident design and analysis; operation, maintenance, leaking and aging of containment systems; thermal hydraulic behaviour of containment systems; hydrogen mixing and mitigation; design methods and concepts; code validation; structural analysis and response tests; passive safety systems; aerosol behaviour; containment reliability, integrity, and risk assessment; hydrogen deflagration and detonation. Due prominence was given to CANDU and other PHWR reactors. The individual papers have been abstracted separately

  12. V1.42In1.83Mo15Se19

    Directory of Open Access Journals (Sweden)

    Michel Potel

    2010-10-01

    Full Text Available The structure of the title compound, vanadium indium pentadecamolybdenum nonadecaselenide, V1.42In1.83Mo15Se19, is isotypic with In2.9Mo15Se19 [Grüttner et al. (1979. Acta Cryst. B35, 285–292]. It is characterized by two cluster units Mo6Sei8Sea6 and Mo9Sei11Sea6 (where i represents inner and a apical atoms that are present in a 1:1 ratio. The cluster units are centered at Wyckoff positions 2b and 2c and have point-group symmetry overline{3} and overline{6}, respectively. The clusters are interconnected through additional Mo—Se bonds. In the title compound, the V3+ cations replace the trivalent indium atoms present in In2.9Mo15Se19, and a deficiency is observed on the monovalent indium site. One Mo, one Se and the V atom are situated on mirror planes, and two other Se atoms and the In atom are situated on threefold rotation axes.

  13. Oxidation characteristics of Ti-25Al-10Nb-3V-1Mo

    Science.gov (United States)

    Wallace, T. A.; Clark, R. K.; Wiedemann, K. E.; Sankaran, S. N.

    1992-01-01

    Static oxidation kinetics of the super-alpha 2 titanium-aluminide alloy Ti-25Al-10Nb-3V-1Mo (at. percent) were investigated in air over the temperature range of 650 to 1000 C using thermogravimetric analysis. The oxidation kinetics were complex at all exposure temperatures and displayed up to three distinct oxidation rates. Breakaway oxidation occurred after long exposure times at high temperatures. Oxidation products were determined using X-ray diffraction techniques, electron microprobe analysis, and energy dispersive X-ray analysis. Oxide scale morphology was examined by scanning electron microscopy of the surfaces and cross sections of oxidized specimens. The oxides during the parabolic stages were compact and multilayered, consisting primarily of TiO2 doped with Nb, a top layer of Al2O3, and a thin bottom layer of TiN. The transition between the second and third parabolic stage was found to be linked to the formation of a TiAl layer at the oxide-metal interface. Porosity was formed during the third stage, causing degradation of the oxide and the beginning of breakaway oxidation.

  14. Oxidation characteristics of Ti-25Al-10Nb-3V-1Mo intermetallic alloy

    Science.gov (United States)

    Wallace, Terryl A.; Clark, Ronald K.; Sankaran, Sankara N.; Wiedemann, Karl E.

    1990-01-01

    Static oxidation kinetics of the super-alpha 2 titanium-aluminide alloy Ti-25Al-10Nb-3V-1Mo (at. percent) were investigated in air over the temperature range of 650 to 1000 C using thermogravimetric analysis. The oxidation kinetics were complex at all exposure temperatures and displayed up to three distinct oxidation rates. Breakaway oxidation occurred after long exposure times at high temperatures. Oxidation products were determined using x ray diffraction techniques, electron microprobe analysis, and energy dispersive x ray analysis. Oxide scale morphology was examined by scanning electron microscopy of the surfaces and cross sections of oxidized specimens. The oxides during the parabolic stages were compact and multilayered, consisting primarily of TiO2 doped with Nb, a top layer of Al2O3, and a thin bottom layer of TiN. The transition between the second and third parabolic stage was found to be linked to the formation of a TiAl layer at the oxide-metal interface. Porosity was formed during the third stage, causing degradation of the oxide and the beginning of breakaway oxidation.

  15. Monochromaticity of orientation maps in v1 implies minimum variance for hypercolumn size.

    Science.gov (United States)

    Afgoustidis, Alexandre

    2015-01-01

    In the primary visual cortex of many mammals, the processing of sensory information involves recognizing stimuli orientations. The repartition of preferred orientations of neurons in some areas is remarkable: a repetitive, non-periodic, layout. This repetitive pattern is understood to be fundamental for basic non-local aspects of vision, like the perception of contours, but important questions remain about its development and function. We focus here on Gaussian Random Fields, which provide a good description of the initial stage of orientation map development and, in spite of shortcomings we will recall, a computable framework for discussing general principles underlying the geometry of mature maps. We discuss the relationship between the notion of column spacing and the structure of correlation spectra; we prove formulas for the mean value and variance of column spacing, and we use numerical analysis of exact analytic formulae to study the variance. Referring to studies by Wolf, Geisel, Kaschube, Schnabel, and coworkers, we also show that spectral thinness is not an essential ingredient to obtain a pinwheel density of π, whereas it appears as a signature of Euclidean symmetry. The minimum variance property associated to thin spectra could be useful for information processing, provide optimal modularity for V1 hypercolumns, and be a first step toward a mathematical definition of hypercolumns. A measurement of this property in real maps is in principle possible, and comparison with the results in our paper could help establish the role of our minimum variance hypothesis in the development process. PMID:25859421

  16. The catastrophic fragmentation of Comet P/2010 V1 (Ikeya-Murakami)

    CERN Document Server

    Kleyna, Jan T; Hui, Man-To; Meech, Karen J; Wainscoat, Richard; Micheli, Marco; Keane, Jacqueline V; Weaver, Harold A

    2016-01-01

    We describe 2016 January and February observations of the fragments of P/2010 V1, a comet previously observed in a 2010 October outburst (Ishiguro et al. 2014). We present photometry of the fragments, and perform simulations to infer the time of breakup. We find that the eastern-most rapidly brightening fragment ($F4$) best corresponds to the original nucleus, rather than the initial bright fragment $F1$. We compute a radial non-gravitational force $A_1$ consistent with zero, and a non--zero tangential component $A_2 = (+7.93\\pm2.26)\\times 10^{-9}\\,\\, \\rm AU \\,day^{-2} $. Monte Carlo simulations indicate that the fragments were emitted on the outbound journey well after the 2010 outburst, with bright fragment $F1$ splitting in mid--2013 and the fainter fragments within months of the 2016 January recovery. Western fragment $F7$ is the oldest, dating from 2011. We suggest that the delayed onset of the splitting is consistent with a self-propagating crystallization of water ice.

  17. The arginine vasopressin V1b receptor gene and prosociality: Mediation role of emotional empathy.

    Science.gov (United States)

    Wu, Nan; Shang, Siyuan; Su, Yanjie

    2015-09-01

    The vasopressin V1b receptor (AVPR1B) gene has been shown to be closely associated with bipolar disorder and depression. However, whether it relates to positive social outcomes, such as empathy and prosocial behavior, remains unknown. This study explored the possible role of the AVPR1B gene rs28373064 in empathy and prosociality. A total of 256 men, who were genetically unrelated, non-clinical ethnic Han Chinese college students, participated in the study. Prosociality was tested by measuring the prosocial tendencies of cognitive and emotional empathy using the Interpersonal Reactivity Index (IRI). The single nucleotide polymorphism (SNP), rs28373064, was genotyped using a polymerase chain reaction-restriction fragment length polymorphism (PCR-RFLP) analysis. The results suggest that the AVPR1B gene rs28373064 is linked to emotional empathy and prosociality. The mediation analysis indicated that the effect of the AVPR1B gene on prosociality might be mediated by emotional empathy. This study demonstrated the link between the AVPR1B gene and prosociality and provided evidence that emotional empathy might mediate the relation between the AVPR1B gene and prosociality. PMID:26354157

  18. Reactor container

    International Nuclear Information System (INIS)

    A reactor container has a suppression chamber partitioned by concrete side walls, a reactor pedestal and a diaphragm floor. A plurality of partitioning walls are disposed in circumferential direction each at an interval inside the suppression chamber, so that independent chambers in a state being divided into plurality are formed inside the suppression chamber. The partition walls are formed from the bottom portion of the suppression chamber up to the diaphragm floor to isolate pool water in a divided state. Operation platforms are formed above the suppression chamber and connected to an access port. Upon conducting maintenance, inspection or repairing, a pump is disposed in the independent chamber to transfer pool water therein to one or a plurality of other independent chambers to make it vacant. (I.N.)

  19. Reactor building

    International Nuclear Information System (INIS)

    The present invention concerns a structure of ABWR-type reactor buildings, which can increase the capacity of a spent fuel storage area at a low cost and improved earthquake proofness. In the reactor building, the floor of a spent fuel pool is made flat, and a depth of the pool water satisfying requirement for shielding is ensured. In addition, a depth of pool water is also maintained for a equipment provisionally storing pool for storing spent fuels, and a capacity for a spent fuel storage area is increased by utilizing surplus space of the equipment provisionally storing pool. Since the flattened floor of the spent fuel pool is flushed with the floor of the equipment provisionally storing pool, transfer of horizontal loads applied to the building upon occurrence of earthquakes is made smooth, to improve earthquake proofness of the building. (T.M.)

  20. Nuclear reactors

    International Nuclear Information System (INIS)

    Disclosed is a nuclear reactor cooled by a freezable liquid has a vessel for containing said liquid and comprising a structure shaped as a container, and cooling means in the region of the surface of said structure for effecting freezing of said liquid coolant at and for a finite distance from said surface for providing a layer of frozen coolant on and supported by said surface for containing said liquid coolant. In a specific example, where the reactor is sodium-cooled, the said structure is a metal-lined concrete vault, cooling is effected by closed cooling loops containing NaK, the loops extending over the lined surface of the concrete vault with outward and reverse pipe runs of each loop separated by thermal insulation, and air is flowed through cooling pipes embedded in the concrete behind the metal lining. 7 claims, 3 figures

  1. NEUTRONIC REACTORS

    Science.gov (United States)

    Anderson, J.B.

    1960-01-01

    A reactor is described which comprises a tank, a plurality of coaxial steel sleeves in the tank, a mass of water in the tank, and wire grids in abutting relationship within a plurality of elongated parallel channels within the steel sleeves, the wire being provided with a plurality of bends in the same plane forming adjacent parallel sections between bends, and the sections of adjacent grids being normally disposed relative to each other.

  2. Nuclear reactor

    International Nuclear Information System (INIS)

    The liquid metal (sodium) cooled fast breeder reactor has got fuel subassemblies which are bundled and enclosed by a common can. In order to reduce bending of the sides of the can because of the load caused by the coolant pressure the can has got a dodecagon-shaped crosssection. The surfaces of the can may be of equal width. One out of two surfaces may also be convex towards the center. (RW)

  3. Cold-aggravated pain in humans caused by a hyperactive NaV1.9 channel mutant.

    Science.gov (United States)

    Leipold, Enrico; Hanson-Kahn, Andrea; Frick, Miya; Gong, Ping; Bernstein, Jonathan A; Voigt, Martin; Katona, Istvan; Oliver Goral, R; Altmüller, Janine; Nürnberg, Peter; Weis, Joachim; Hübner, Christian A; Heinemann, Stefan H; Kurth, Ingo

    2015-01-01

    Gain-of-function mutations in the human SCN11A-encoded voltage-gated Na(+) channel NaV1.9 cause severe pain disorders ranging from neuropathic pain to congenital pain insensitivity. However, the entire spectrum of the NaV1.9 diseases has yet to be defined. Applying whole-exome sequencing we here identify a missense change (p.V1184A) in NaV1.9, which leads to cold-aggravated peripheral pain in humans. Electrophysiological analysis reveals that p.V1184A shifts the voltage dependence of channel opening to hyperpolarized potentials thereby conferring gain-of-function characteristics to NaV1.9. Mutated channels diminish the resting membrane potential of mouse primary sensory neurons and cause cold-resistant hyperexcitability of nociceptors, suggesting a mechanistic basis for the temperature dependence of the pain phenotype. On the basis of direct comparison of the mutations linked to either cold-aggravated pain or pain insensitivity, we propose a model in which the physiological consequence of a mutation, that is, augmented versus absent pain, is critically dependent on the type of NaV1.9 hyperactivity. PMID:26645915

  4. The Functional Property Changes of Muscular Na(v)1.4 and Cardiac Na(v)1.5 Induced by Scorpion Toxin BmK AGP-SYPU1 Mutants Y42F and Y5F.

    Science.gov (United States)

    Meng, Xiangxue; Xu, Yijia; Zhao, Mingyi; Wang, Fangyang; Ma, Yuanyuan; Jin, Yao; Liu, Yanfeng; Song, Yongbo; Zhang, Jinghai

    2015-05-19

    Scorpion toxins are invaluable therapeutic leads and pharmacological tools which influence the voltage-gated sodium channels. However, the details were still unclear about the structure-function relationship of scorpion toxins on VGSC subtypes. In the previous study, we reported one α-type scorpion toxin Bmk AGP-SYPU1 and its two mutants (Y5F and Y42F) which had been demonstrated to ease pain in mice acetic acid writhing test. However, the function of Bmk AGP-SYPU1 on VGSCs is still unknown. In this study, we examined the effects of BmK AGP-SYPU1 and its two mutants (Y5F and Y42F) on hNa(v)1.4 and hNa(v)1.5 heterologously expressed CHO cell lines by using Na⁺-specialized fluorescent dye and whole-cell patch clamp. The data showed that BmK AGP-SYPU1 displayed as an activator of hNa(v)1.4 and hNa(v)1.5, which might indeed contribute to its biotoxicity to muscular and cardiac system and exhibited the functional properties of both the α-type and β-type scorpion toxin. Notably, Y5F mutant exhibited lower activatory effects on hNa(v)1.4 and hNa(v)1.5 compared with BmK AGP-SYPU1. Y42F was an enhanced activator and confirmed that the conserved Tyr42 was the key amino acid involved in bioactivity or biotoxicity. These data provided a deep insight into the structure-function relationship of BmK AGP-SYPU1, which may be the guidance for engineering α-toxin with high selectivity on VGSC subtypes. PMID:25919575

  5. Nuclear reactor

    International Nuclear Information System (INIS)

    A detector having high sensitivity to fast neutrons and having low sensitivity to thermal neutrons is disposed for reducing influences of neutron detector signals on detection values of neutron fluxes when the upper end of control rod pass in the vicinity of the neutron flux detector. Namely, the change of the neutron fluxes is greater in the thermal neutron energy region while it is smaller in the fast neutron energy region. This is because the neutron absorbing cross section of B-10 used as neutron absorbers of control rods is greater in the thermal neutron region and it is smaller in the fast neutron region. As a result, increase of the neutron detection signals along with the local neutron flux change can be reduced, and detection signals corresponding to the reactor power can be obtained. Even when gang withdrawal of operating a plurality of control rods at the same time is performed, the reactor operation cycle can be measured accurately, thereby enabling to shorten the reactor startup time. (N.H.)

  6. High Temperature Structure Leak Before Break Assessment Guideline(V1.0)

    Energy Technology Data Exchange (ETDEWEB)

    Park, Chang-Gyu; Kim, Jong-Bum; Lee, Hyeong-Yeon; Joo, Young-Sang; Lee, Jae-Han

    2007-03-15

    This study describes the Leak Before Break(LBB) procedure applicable to the reactor structure of Liquid Metal Reactor(LMR) which is operated at a high temperature. The purpose of LBB in LMR is to assure the defence in depth safety. The technically advanced countries of LMR development, such as Japan, UK and France, have their own LBB evaluation code. Their procedures are investigated thoroughly and the draft edition of LBB assessment guideline for the high temperature LMR structures is proposed. The key issues are the defect initiation, the defect propagation and the fast rupture of structures under the fatigue loading or the creep-fatigue loading condition. Additionlly, the detectable defect length and crack opening evaluation for the leakage detection method are analyzed and included in this guideline. Additionally, the detectable defect length and the creep-fatigue defect growth with a circumferential through wall defect for a KALIMER-600 IHTS hot leg piping based on this high temperature LBB assessment guideline were evaluated.

  7. Transcriptional and electrophysiological consequences of KChIP2-mediated regulation of CaV1.2

    DEFF Research Database (Denmark)

    Thomsen, Morten B; Foster, Erika; Nguyen, Katherine H; Sosunov, Eugene A

    2009-01-01

    . Recently, we have reported that KChIP2 functionally modulates the cardiac Ca(V)1.2-governed L-type Ca(2+) current (I(Ca,L)) through a direct interaction between KChIP2 and the amino-terminus of Ca(V)1.2. Here, we show that KChIP2 and Ca(V)1.2 co-immunoprecipitate enhancing the biochemical support for our......IP2(-/-) mice, the action potential morphology is not altered. Furthermore, we show that the ventricular effective refractory period (VERP) is comparable in wild-type (53 +/- 5 ms) and KChIP2(-/-) mice (48 +/- 3 ms; p > 0.05). In summary, our findings document a novel function of KChIP2 and expand our...

  8. Vscape V1.1.0. An interactive tool for metastable vacua

    Science.gov (United States)

    van den Broek, Korneel

    2008-01-01

    Vscape is an interactive tool for studying the one-loop effective potential of an ungauged supersymmetric model of chiral multiplets. The program allows the user to define a supersymmetric model by specifying the superpotential. The F-terms and the scalar and fermionic mass matrices are calculated symbolically. The program then allows you to search numerically for (meta)stable minima of the one-loop effective potential. Additional commands enable you to further study specific minima, by, e.g., computing the mass spectrum for those vacua. Vscape combines the flexibility of symbolic software, with the speed of a numerical package. Program summaryProgram title:Vscape 1.1.1 Catalogue identifier: ADZW_v1_0 Program summary URL:http://cpc.cs.qub.ac.uk/summaries/ADZW_v1_0.html Program obtainable from: CPC Program Library, Queen's University, Belfast, N. Ireland Licensing provisions: Standard CPC licence, http://cpc.cs.qub.ac.uk/licence/licence.html No. of lines in distributed program, including test data, etc.: 80 507 No. of bytes in distributed program, including test data, etc.: 6 708 938 Distribution format: tar.gz Programming language: C++ Computer: Pentium 4 PC Computers: need (GNU) C++ compiler, Linux standard GNU installation (./configure; make; make install). A precompiled Windows XP version is included in the distribution package Operating system: Linux, Windows XP using cygwin RAM: 10 MB Word size: 32 bits Classification: 11.6 External routines: GSL ( http://www.gnu.org/software/gsl/), CLN ( http://www.ginac.de/CLN/), GiNaC ( http://directory.fsf.org/GiNaC.html) Nature of problem:Vscape is an interactive tool for studying the one-loop effective potential of an ungauged supersymmetric model of chiral multiplets. The program allows the user to define a supersymmetric model by specifying the superpotential. The F-terms and the scalar and fermionic mass matrices are calculated symbolically. The program then allows you to search numerically for (meta)stable minima of

  9. Reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    In a BWR type nuclear reactor, the number of first fuel assemblies (uranium) loaded in a reactor core is smaller than that of second fuel assemblies (mixed oxide), the average burnup degree upon take-out of the first fuel assemblies is reduced to less than that of the second fuel assemblies, and the number of the kinds of the fuel rods constituting the first fuel assemblies is made smaller than that of the fuel rods constituting the second fuel assemblies. As a result, the variety of the plutonium enrichment degree is reduced to make the distribution of the axial enrichment degree uniform, thereby enabling to simplify the distribution of the enrichment degree. Then the number of molding fabrication steps for MOX fuel assemblies can be reduced, thereby enabling to reduce the cost for molding and fabrication. (N.H.)

  10. Neurons in cat V1 show significant clustering by degree of tuning.

    Science.gov (United States)

    Ziskind, Avi J; Emondi, Al A; Kurgansky, Andrei V; Rebrik, Sergei P; Miller, Kenneth D

    2015-04-01

    Neighboring neurons in cat primary visual cortex (V1) have similar preferred orientation, direction, and spatial frequency. How diverse is their degree of tuning for these properties? To address this, we used single-tetrode recordings to simultaneously isolate multiple cells at single recording sites and record their responses to flashed and drifting gratings of multiple orientations, spatial frequencies, and, for drifting gratings, directions. Orientation tuning width, spatial frequency tuning width, and direction selectivity index (DSI) all showed significant clustering: pairs of neurons recorded at a single site were significantly more similar in each of these properties than pairs of neurons from different recording sites. The strength of the clustering was generally modest. The percent decrease in the median difference between pairs from the same site, relative to pairs from different sites, was as follows: for different measures of orientation tuning width, 29-35% (drifting gratings) or 15-25% (flashed gratings); for DSI, 24%; and for spatial frequency tuning width measured in octaves, 8% (drifting gratings). The clusterings of all of these measures were much weaker than for preferred orientation (68% decrease) but comparable to that seen for preferred spatial frequency in response to drifting gratings (26%). For the above properties, little difference in clustering was seen between simple and complex cells. In studies of spatial frequency tuning to flashed gratings, strong clustering was seen among simple-cell pairs for tuning width (70% decrease) and preferred frequency (71% decrease), whereas no clustering was seen for simple-complex or complex-complex cell pairs. PMID:25652921

  11. Spent fuel management in the Slovak Republic

    International Nuclear Information System (INIS)

    Presentation describes the history, present and future of the spent fuel management in the Slovak Republic. First experiences with spent fuel were gained in the seventies. Spent fuel form A-1 NPP was handled at Jaslovske Bohunice site, in order to prepare the spent fuel for the transport to the former USSR. After shut down of the A-1 NPP, all spent fuel was transported to the USSR. In 1978 first unit of V-1 NPP was set into operation. Actually there are six NPP units of the WWER type at Jaslovske Bohunice and Mochovce sites in operation in the Slovak Republic. These six units produce about 500 spent fuel assemblies per year. In 1988 an Interim spent fuel storage facility was build at Jaslovske Bohunice site. These facility stores spent fuel from four Jaslovske Bohunice units. In 2000 this facility was subject to a reconstruction, seismic upgrade and capacity enlargement. In 2004 Nuclear Regulatory Authority of the Slovak Republic approved transport container C-30 for transport of forty-eight spent fuel assemblies. The transport capacity has risen, so the number of transports could be reduced. In 2006 Slovak Electric Plc. (SE) will start transports of spent fuel from Mochovce site to Interim spent fuel storage facility (ISFSF) Jaslovske Bohunice. In addition, a project of Interim spent fuel storage facility at Mochovce site is going on. In the future Slovakia plans to find definitive solution for the spent fuel. One solution could be reprocessing and further usage in the power reactors, the other solution could be final deposition of spent fuel. (author)

  12. Activated transport in the v = 1 bilayer quantum Hall states with small tunneling energy ΔSAS = 1K

    International Nuclear Information System (INIS)

    We carried out magnetotransport experiments in the v = 1 bilayer quantum Hall state (BQHS) using a GaAs/AlAs double-quantum-well structure with tunneling energy as small as 1 K. We focus on measurements of not only activation energies but also onset temperatures of the BQHS for a wide range of the total density and the layer density imbalance. We have found that the dependency of onset temperature on the total density is different from that of the activation energy. We discuss physical interpretations of the onset temperature with relationship to finite-temperature phase transitions in the v = 1 BQHS.

  13. Persistent modification of Na{sub v}1.9 following chronic exposure to insecticides and pyridostigmine bromide

    Energy Technology Data Exchange (ETDEWEB)

    Nutter, Thomas J., E-mail: tnutter@dental.ufl.edu; Cooper, Brian Y., E-mail: bcooper@dental.ufl.edu

    2014-06-15

    Many veterans of the 1991 Gulf War (GW) returned from that conflict with a widespread chronic pain affecting deep tissues. Recently, we have shown that a 60 day exposure to the insecticides permethrin, chlorpyrifos, and pyridostigmine bromide (NTPB) had little influence on nociceptor action potential forming Na{sub v}1.8, but increased K{sub v}7 mediated inhibitory currents 8 weeks after treatment. Using the same exposure regimen, we used whole cell patch methods to examine whether the influences of NTPB could be observed on Na{sub v}1.9 expressed in muscle and vascular nociceptors. During a 60 day exposure to NTPB, rats exhibited lowered muscle pain thresholds and increased rest periods, but these measures subsequently returned to normal levels. Eight and 12 weeks after treatments ceased, DRG neurons were excised from the sensory ganglia. Whole cell patch studies revealed little change in voltage dependent activation and deactivation of Na{sub v}1.9, but significant increases in the amplitude of Na{sub v}1.9 were observed 8 weeks after exposure. Cellular studies, at the 8 week delay, revealed that NTPB also significantly prolonged action potential duration and afterhyperpolarization (22 °C). Acute application of permethrin (10 μM) also increased the amplitude of Na{sub v}1.9 in skin, muscle and vascular nociceptors. In conclusion, chronic exposure to Gulf War agents produced long term changes in the amplitude of Na{sub v}1.9 expressed in muscle and vascular nociceptors. The reported increases in K{sub v}7 amplitude may have been an adaptive response to increased Na{sub v}1.9, and effectively suppressed behavioral pain measures in the post treatment period. Factors that alter the balance between Na{sub v}1.9 and K{sub v}7 could release spontaneous discharge and produce chronic deep tissue pain. - Highlights: • Rats were treated 60 days with permethrin, chlorpyrifos and pyridostigmine bromide. • 8 weeks after treatments, Nav1.9 activation and deactivation were

  14. Topologie und Relativbewegungen stielbildender Untereinheiten der V1-ATPase aus der Tabakschwärmerraupe Manduca sexta

    OpenAIRE

    Rizzo, Vincenzo Filippo

    2004-01-01

    Durch Ablösen einzelner Untereinheiten mit Hilfe des Detergens Lauryldimethyloxid (LDAO) konnten aus der V1ATPase (A3:B3:C:D:E:F:G2:Hy) aus Manduca sexta hydrolytisch aktive Subkomplexe gewonnen werden. Diese waren A3B3DEG (176% Hydrolyseaktivität relativ zur V1ATPase), A3B3HEGF (53 %), A3B3EG (58 %) und A3B3DEGH (47 %). Der zur Hydrolyse minimal notwendige A3B3EG-Subkomplex wurde hinsichtlich der Lage der Stieluntereinheiten E und G elektronenmikroskopisch untersucht. Die Bildanalyse der mit...

  15. Safeguarding radiation protection by the V-1 nuclear power plant operator and checking the job by hygiene service bodies

    International Nuclear Information System (INIS)

    Radiation protection in the V-1 nuclear power plant is controlled by a dosimetry service unit on the basis of information on the radiation situation obtained using stationary and portable dosimetric systems. Hygiene services bodies check the work by separate tests and measurements. It was found that the radiation burden of the nuclear power staff has so far been minimal. No environmental impact has been recorded of the V-1 nuclear power plant, even when available sensitive radiometric methods were used. The radiation protection aspects of the first refuelling are also mentioned. (author)

  16. Types of Nuclear Reactors

    International Nuclear Information System (INIS)

    The presentation is based on the following areas: Types of Nuclear Reactors, coolant, moderator, neutron spectrum, fuel type, pressurized water reactor (PWR), boiling water reactor (BWR) reactor pressurized heavy water (PHWR), gas-cooled reactor, RBMK , Nuclear Electricity Generation,Challenges in Nuclear Technology Deployment,EPR, APR1400, A P 1000, A PWR, ATMEA 1, VVER-1000, A PWR, VVER 1200, Boiling Water Reactor, A BWR, A BWR -II, ESBUR, Ke ren, AREVA, Heavy Water Reactor, Candu 6, Acr-1000, HWR, Bw, Iris, CAREM NuCcale, Smart, KLT-HOS, Westinghouse small modular Reactor, Gas Cooled Reactors, PBMR.

  17. Nuclear reactor

    International Nuclear Information System (INIS)

    A nuclear reactor is described in which the core components, including fuel-rod assemblies, control-rod assemblies, fertile rod-assemblies, and removable shielding assemblies, are supported by a plurality of separate inlet modular units. These units are referred to as inlet module units to distinguish them from the modules of the upper internals of the reactor. The modular units are supported, each removable independently of the others, in liners in the supporting structure for the lower internals of the reactor. The core assemblies are removably supported in integral receptacles or sockets of the modular units. The liners, units, sockets and assemblies have inlet openings for entry of the fluid. The modular units are each removably mounted in the liners with fluid seals interposed between the opening in the liner and inlet module into which the fluid enters in the upper and lower portion of the liner. Each assembly is similarly mounted in a corresponding receptacle with fluid seals interposed between the openings where the fluid enters in the lower portion of the receptacle or fitting closely in these regions. As fluid flows along each core assembly a pressure drop is produced along the fluid so that the fluid which emerges from each core assembly is at a lower pressure than the fluid which enters the core assembly. However because of the seals interposed in the mountings of the units and assemblies the pressures above and below the units and assemblies are balanced and the units are held in the liners and the assemblies are held in the receptacles by their weights as they have a higher specific gravity than the fluid. The low-pressure spaces between each module and its liner and between each core assembly and its module is vented to the low-pressure regions of the vessel to assure that fluid which leaks through the seals does not accumulate and destroy the hydraulic balance

  18. Nuclear research reactors

    International Nuclear Information System (INIS)

    It's presented data about nuclear research reactors in the world, retrieved from the Sien (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: research reactors by countries; research reactors by type; research reactors by fuel and research reactors by purpose. (E.G.)

  19. Nuclear reactor physics course for reactor operators

    International Nuclear Information System (INIS)

    The education and training of nuclear reactor operators is important to guarantee the safe operation of present and future nuclear reactors. Therefore, a course on basic 'Nuclear reactor physics' in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The aim of the basic course on 'Nuclear Reactor Physics for reactor operators' is to provide the reactor operators with a basic understanding of the main concepts relevant to nuclear reactors. Seen the education level of the participants, mathematical derivations are simplified and reduced to a minimum, but not completely eliminated

  20. Nuclear reactor

    International Nuclear Information System (INIS)

    Cover gas spaces for primary coolant vessel, such as a reactor container, a pump vessel and an intermediate heat exchanger vessel are in communication with each other by an inverted U-shaped pressure conduit. A transmitter and a receiver are disposed to the pressure conduit at appropriate positions. If vibration frequencies (pressure vibration) from low frequency to high frequency are generated continuously from the transmitter to the inside of the communication pipe, a resonance phenomenon (air-column resonance oscillation) is caused by the inherent frequency or the like of the communication pipe. The frequency of the air-column resonance oscillation is changed by the inner diameter and the clogged state of the pipelines. Accordingly, by detecting the change of the air-column oscillation characteristics by the receiver, the clogged state of the flow channels in the pipelines can be detected even during the reactor operation. With such procedures, steams of coolants flowing entrained by the cover gases can be prevented from condensation and coagulation at a low temperature portion of the pipelines, otherwise it would lead clogging in the pipelines. (I.N.)

  1. Graded Ca2+/calmodulin-dependent coupling of voltage-gated CaV1.2 channels

    Science.gov (United States)

    Dixon, Rose E; Moreno, Claudia M; Yuan, Can; Opitz-Araya, Ximena; Binder, Marc D; Navedo, Manuel F; Santana, Luis F

    2015-01-01

    In the heart, reliable activation of Ca2+ release from the sarcoplasmic reticulum during the plateau of the ventricular action potential requires synchronous opening of multiple CaV1.2 channels. Yet the mechanisms that coordinate this simultaneous opening during every heartbeat are unclear. Here, we demonstrate that CaV1.2 channels form clusters that undergo dynamic, reciprocal, allosteric interactions. This ‘functional coupling’ facilitates Ca2+ influx by increasing activation of adjoined channels and occurs through C-terminal-to-C-terminal interactions. These interactions are initiated by binding of incoming Ca2+ to calmodulin (CaM) and proceed through Ca2+/CaM binding to the CaV1.2 pre-IQ domain. Coupling fades as [Ca2+]i decreases, but persists longer than the current that evoked it, providing evidence for ‘molecular memory’. Our findings suggest a model for CaV1.2 channel gating and Ca2+-influx amplification that unifies diverse observations about Ca2+ signaling in the heart, and challenges the long-held view that voltage-gated channels open and close independently. DOI: http://dx.doi.org/10.7554/eLife.05608.001 PMID:25714924

  2. Block of CaV1.2 Channels by Gd3+ Reveals Preopening Transitions in the Selectivity Filter

    OpenAIRE

    Babich, Olga; Reeves, John; Shirokov, Roman

    2007-01-01

    Using the lanthanide gadolinium (Gd3+) as a Ca2+ replacing probe, we investigated the voltage dependence of pore blockage of CaV1.2 channels. Gd+3 reduces peak currents (tonic block) and accelerates decay of ionic current during depolarization (use-dependent block). Because diffusion of Gd3+ at concentrations used (

  3. 76 FR 13082 - Amendment of VOR Federal Airways V-1, V-7, V-11 and V-20; Kona, HI

    Science.gov (United States)

    2011-03-10

    ... and Procedures (44 FR 11034; February 26, 1979); and (3) does not warrant preparation of a regulatory..., 40113, 40120; E.O. 10854, 24 FR 9565, 3 CFR, 1959-1963 Comp., p. 389. Sec. 71.1 0 2. The incorporation... Federal Aviation Administration 14 CFR Part 71 RIN 2120-AA66 Amendment of VOR Federal Airways V-1, V-7,...

  4. Using AppleWorks V1.3 To Construct Data Base Files for the Apple IIe Computer. Second Edition.

    Science.gov (United States)

    Schlenker, Richard M.

    This step-by-step guide to using AppleWorks V1.3 to construct database files for the Apple IIe computer covers (1) program loading; (2) selecting the add files to the desktop option; (3) naming the file; (4) the blinking block cursor; (5) naming categories or fields; (6) moving to insert data; (7) inserting data; (8) changing database file…

  5. Using AppleWorks V1.3 To Construct Word Processing Files for the Apple IIe Computer. Second Edition.

    Science.gov (United States)

    Schlenker, Richard M.

    This step-by-step guide to using AppleWorks V1.3 to construct word processing files for the Apple IIe computer covers (1) program loading; (2) selecting the add files to the desktop option; (3) selecting a different disk; (4) selecting disk 2; (5) selecting the word processor option; (6) naming the file; (7) setting tabs; (8) selecting print…

  6. Red Flags in Electrocardiogram for Emergency Physicians: Remembering Wellens’ Syndrome and Upright T wave in V1

    Directory of Open Access Journals (Sweden)

    Ozcan Yavasi, MD

    2012-05-01

    Full Text Available We present a case of Wellens’ syndrome together with upright T wave in lead V1 in a man presentingwith atypical chest pain, and we discuss the significance of its prompt recognition by the emergencyphysicians who are involved in the evaluation of patients with coronary artery disease in emergencydepartments.

  7. Red Flags in Electrocardiogram for Emergency Physicians: Remembering Wellens' Syndrome and Upright T wave in V1

    OpenAIRE

    Ozcan Yavasi, MD; Seran Unluer, MD; Serdar Bayata; Huseyin Bozdemir, MD; Adnan Pınar, MD; Erden Erol Unluer

    2012-01-01

    We present a case of Wellens’ syndrome together with upright T wave in lead V1 in a man presenting with atypical chest pain, and we discuss the significance of its prompt recognition by the emergency physicians who are involved in the evaluation of patients with coronary artery disease in emergency departments. [West J Emerg Med. 2012;13(2):160–162.

  8. Functional alterations of V1 cortex in patients with primary open angle glaucoma using functional MRI retinotopic mapping

    International Nuclear Information System (INIS)

    Objective: To evaluate the functional changes of visual cortex (V1) in patients with primary open angle glaucoma (POAG) by fMRI retinotopic mapping technology. Methods: Fifteen POAG patients and 15 healthy volunteers underwent stimulations with fMRI retinotopic mapping stimulus and contrast-reversing checkerboard patterns stimulus on a Siemens Trio 3.0 T MRI whole-body scanner for functional data collection. Comparisons of V1 fMRI responses between the glaucomatous eyes and the healthy eyes of the patients were carried out using paired samples t-test, while independent samples t-test was used to compare V1 fMRI responses and activations between the healthy eyes of patients and the age-, gender- and side- matched eyes of normal people. Differences of V1 cortical functions and visual functions were analyzed by linear correlation analysis when the glaucomatous and the healthy eyes were simulated individually., Results: (1) V1 fMRI responses of the individually stimulated glaucomatous eyes [(1.24±0.72)%] were weaker than those of the healthy eyes [(2.18±0.93)%] (t=4.757, P0.05). (2) Differences of V1 cortical functions were negatively correlated with those of visual functions in the individually stimulated glaucomatous and healthy eyes (r=-0.887, P< 0.01). (3) The activated area indexes of V1 cortexes in the healthy eyes from patients (0.72±0.12) were lower than those in the matched eyes of normal people (0.85±0.09) (t=-3.801, P<0.01) . Conclusion: Cortical function impairment was in accordance with visual function impairment in glaucoma. Located and quantified measurement with fMRI retinotopic mapping was a useful method for clinical follow-up and evaluation of functional alteration of glaucomatous visual cortex, and a potentially useful means of studying trans-synaptic degeneration of visual pathways of in vivo glaucoma. (authors)

  9. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T. (Inventor); Sahimi, Muhammad (Inventor); Fayyaz-Najafi, Babak (Inventor); Harale, Aadesh (Inventor); Park, Byoung-Gi (Inventor); Liu, Paul K. T. (Inventor)

    2011-01-01

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

  10. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T.; Sahimi, Muhammad; Fayyaz-Najafi, Babak; Harale, Aadesh; Park, Byoung-Gi; Liu, Paul K. T.

    2011-03-01

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

  11. Systematic Study of Binding of μ-Conotoxins to the Sodium Channel NaV1.4

    Directory of Open Access Journals (Sweden)

    Somayeh Mahdavi

    2014-12-01

    Full Text Available Voltage-gated sodium channels (NaV are fundamental components of the nervous system. Their dysfunction is implicated in a number of neurological disorders, such as chronic pain, making them potential targets for the treatment of such disorders. The prominence of the NaV channels in the nervous system has been exploited by venomous animals for preying purposes, which have developed toxins that can block the NaV channels, thereby disabling their function. Because of their potency, such toxins could provide drug leads for the treatment of neurological disorders associated with NaV channels. However, most toxins lack selectivity for a given target NaV channel, and improving their selectivity profile among the NaV1 isoforms is essential for their development as drug leads. Computational methods will be very useful in the solution of such design problems, provided accurate models of the protein-ligand complex can be constructed. Using docking and molecular dynamics simulations, we have recently constructed a model for the NaV1.4-μ-conotoxin-GIIIA complex and validated it with the ample mutational data available for this complex. Here, we use the validated NaV1.4 model in a systematic study of binding other μ-conotoxins (PIIIA, KIIIA and BuIIIB to NaV1.4. The binding mode obtained for each complex is shown to be consistent with the available mutation data and binding constants. We compare the binding modes of PIIIA, KIIIA and BuIIIB to that of GIIIA and point out the similarities and differences among them. The detailed information about NaV1.4-μ-conotoxin interactions provided here will be useful in the design of new NaV channel blocking peptides.

  12. Pyramidal cells in V1 of African rodents are bigger more branched and more spiny than those in primates.

    Directory of Open Access Journals (Sweden)

    Guy Elston

    2014-02-01

    Full Text Available Pyramidal cells are characterised by markedly different sized dendritic trees, branching patterns and spine density across the cortical mantle. Moreover, pyramidal cells have been shown to differ in structure among homologous cortical areas in different species; however, most of these studies have been conducted in primates. Whilst pyramidal cells have been quantified in a few cortical areas in some other species there are, as yet, no uniform comparative data on pyramidal cell structure in a homologous cortical area among species in different Orders. Here we studied layer III pyramidal cells in V1 of three species of rodents, the greater cane rat, highveld gerbil and four-striped mouse, by the same methodology used to sample data from layer III pyramidal cells in primates. The data reveal markedly different trends between rodents and primates: there is an appreciable increase in the size, branching complexity and number of spines in the dendritic trees of pyramidal cells with increasing size of V1 in the brain in rodents, whereas there is relatively little difference in primates. Moreover, pyramidal cells in rodents are larger, more branched and more spinous than those in primates. For example, the dendritic trees of pyramidal cells in V1 of the cane rat are nearly three times larger, and have more than ten times the number of spines in their basal dendritic trees, than those in V1 of the macaque (7900 and 600, respectively, which has a V1 40 times the size that of the cane rat. It remains to be determined to what extent these differences may result from developmental differences or reflect evolutionary and/or processing specializations.

  13. Thermal-deformation effect of welding on A 1 reactor pressure vessel weld joints properties and state of stress

    International Nuclear Information System (INIS)

    The methods are compared of electroslag welding and of arc welding with a view to their possible application in welding the Bohunice A-1 reactor pressure vessel. Considered are the thermal deformation effects of welding on the physical properties and the stress present in welded joints. For testing, plates were used having the dimensions of 1100x2300x200 mm and rings with 4820 mm outer diameter, 1800 mm height and 170 mm thickness made of steel CSN 413O30 modified with Ni, Al+Ti. The deformation effect of welding on the residual surface and triaxial stress, the specific stored energy, the initiation temperature of brittle crack and the critical size of the initiation defect corresponding to the thermal deformation effect of welding were determined. It was found that for electroslag welding, there is a low probability of crack formation in the joints, a low level of residual stress and a low level of specific stored energy in a relatively wide joint zone. For arc welding there is a considerable probability of defect formation in the vicinity of the sharp boundary of the joint, a high level of the triaxial state of stress in the tensile region, and a high level of specific stored energy concentrated in the narrow zone of weld joints. The recommended thermal process is given for welding pressure vessels made of the CSN 413030 steel modified with Ni, Al+Ti, and 150 to 200 mm in thickness. (J.P.)

  14. Transient analysis of the pebble-bed HTGR with the DSNP simulation language. V.1

    International Nuclear Information System (INIS)

    This is the final report of the first phase of the research contract between KFA-Julich and Soreq NRC covering the period of January 198l to December 1982. During this period most of the components necessary for the dyanmic simulation of the PNP-500 high temperature gas-cooled reactor were developed, tested and included in the DSNP library. Components available in the DSNP simulation language were modified to be applicable to compressible flow systems. The report describes each of these components and provides instructions for their application to system simulation in the DSNP. The primary, intermediate and water-steam heat removal loops were simulated and tested step by step by developing DSNP simulation programs with progressively increasing complexity. The details of each of these simulations is presented together with the partial results obtained. The partial simulations were combined to obtain a full scale PNP-500 simulation. Several accidents were studied with this simulation program particularly a turbine trip, a reactivity accident and a depressurization accident. The major conclusion from the study is that the PNP-500 is inherently a very stable and safe system under a large variety of extreme operating and accident conditions. (author)

  15. DeCART v1.2 User's Manual

    Energy Technology Data Exchange (ETDEWEB)

    Cho, J. Y.; Kim, K. S.; Kim, H. Y.; Lee, C. C.; Zee, S. Q; Joo, H. G

    2007-07-15

    DeCART (Deterministic Core Analysis based on Ray Tracing) is a whole core neutron transport code capable of direct subpin level flux calculation at power generating conditions. It does not require a priori homogenization nor group condensation needed in conventional reactor physics calculations. The depletion and transient calculation capabilities are also available. This manual serves as a self-sufficient guide to use the code. First of all, the various features of the code are explained which encompass various modeling options as well as the basic calculation functionalities. The instructions for running the code are also given with a description of the output files generated. Next, the underlying concepts and principles of preparing a DeCART model for a problem under consideration are presented. Each part of the input needed to specify the geometry, material composition, thermal operating condition, program execution control parameters are explained with examples. The descriptions of all the input cards are then followed. Finally, various sample model inputs ranging from a simple 2D pin cell to a realistic 3D core problem, steady-state to transient problems, and from rectangular to hexagonal core problems are presented.

  16. DeCART v1.1 user's manual

    Energy Technology Data Exchange (ETDEWEB)

    Cho, J. Y.; Kim, K. S.; Kim, H. Y.; Lee, C. C.; Zee, S. Q.; Joo, H. G

    2005-03-15

    DeCART (Deterministic Core Analysis based on Ray Tracing) is a whole core neutron transport code capable of direct subpin level flux calculation at power generating conditions. It does not require a priori homogenization nor group condensation needed in conventional reactor physics calculations. The depletion and transient calculation capabilities are also available. This manual serves as a self-sufficient guide to use the code. First of all, the various features of the code are explained which encompass various modeling options as well as the basic calculation functionalities. The instructions for running the code are also given with a description of the output files generated. Next, the underlying concepts and principles of preparing a DeCART model for a problem under consideration are presented. Each part of the input needed to specify the geometry, material composition, thermal operating condition, program execution control parameters are explained with examples. The descriptions of all the input cards are then followed. Finally, various sample model inputs ranging from a simple 2D pin cell to a realistic 3D core problem, steady-state to transient problems, are presented.

  17. Reactor container

    International Nuclear Information System (INIS)

    Purpose: To prevent shocks exerted on a vent head due to pool-swell caused within a pressure suppression chamber (disposed in a torus configuration around the dry well) upon loss of coolant accident in BWR type reactors. Constitution: The following relationship is established between the volume V (m3) of a dry well and the ruptured opening area A (m2) at the boundary expected upon loss of coolant accident: V >= 30340 (m) x A Then, the volume of the dry well is made larger than the ruptured open area, that is, the steam flow rate of leaking coolants upon loss of coolant accident to decrease the pressure rise in the dry well at the initial state where loss of coolant accident is resulted. Accordingly, the pressure of non-compressive gases jetted out from the lower end of the downcomer to the pool water is decreased to suppress the pool-swell. (Ikeda, J.)

  18. The V1 region of gp120 is preferentially selected during SIV/HIV transmission and is indispensable for envelope function and virus infection.

    Science.gov (United States)

    Li, Yanpeng; Dittmer, Ulf; Wang, Yan; Song, Jiping; Sun, Binlian; Yang, Rongge

    2016-06-01

    A transmission bottleneck occurs during each human immunodeficiency virus (HIV) transmission event, which allows only a few viruses to establish new infection. However, the genetic characteristics of the transmitted viruses that are preferentially selected have not been fully elucidated. Here, we analyzed amino acids changes in the envelope protein during simian immunodeficiency virus (SIV)/HIV deep transmission history and current HIV evolution within the last 15-20 years. Our results confirmed that the V1V2 region of gp120 protein, particularly V1, was preferentially selected. A shorter V1 region was preferred during transmission history, while during epidemic, HIV may evolve to an expanded V1 region gradually and thus escape immune recognition. We then constructed different HIV-1 V1 mutants using different HIV-1 subtypes to elucidate the role of the V1 region in envelope function. We found that the V1 region, although highly variable, was indispensable for virus entry and infection, probably because V1 deletion mutants exhibited impaired processing of gp160 into mature gp120 and gp41. Additionally, the V1 region affected Env incorporation. These results indicated that the V1 region played a critical role in HIV transmission and infection. PMID:27117672

  19. Effect of the Tempering Temperature on Thermal Fatigue Behavior of 4Cr5MoSiV1 and 8407 Steels%4Cr5MoSiV1,8407钢的热疲劳性能

    Institute of Scientific and Technical Information of China (English)

    许珞萍; 吴晓春; 邵光杰; 闵永安

    2001-01-01

    With the self-restricting test method, the thermal fatigue behavior of 4Cr5MoSiV1 steel and 8407 steel was investigated under the same heat treatment condition. The crack morphology and fracture surface was also analyzed. The thermal fatigue process of these steels was quantitatively investigated with a thermal fatigue damage parameter. The results indicate that thermal fatigue cracks of both steels initiate at the time between 100 to 200 cycles. The initiating cracks of 8407 steel are smaller and more equable than that in 4Cr5MoSiV1 steel. Before 1600 thermal cycles, there are not obvious difference on the thermal fatigue behavior of both steels, after 1600 thermal cycles, the degree of the thermal fatigue damage of 8407 steel is lower than that of 4Cr5MoSiV1 steel. When the tempering temperature is below 640°C, the thermal fatigue behavior of 8407 steel is slightly better than that of 4Cr5MoSiV1 steel, but when the tempering temperature exceeds 640°C, the behavior of the former seems superior. The mechanism analysis of thermal fatigue reveals that the main factor affecting thermal fatigue resistance is the thermal stability and strength or hardness of steels.%采用自约束热疲劳试验方法,对比研究了相同热处理条件的4Cr5MoSiV1,8407钢的热疲劳特性,观察分析了疲劳裂纹形貌和深度,采用热疲劳损伤因子定量研究了二种钢的热疲劳过程,结果表明:两种钢的热疲劳裂纹萌生发生在100~200次之间,8407钢热疲劳裂纹的萌生较4Cr5MoSiV1钢均匀,细小;在1600次冷热循环前,二者的热疲劳损伤程度无明显差别,在1600次冷热循环后,前者的热疲劳损伤程度低于后者; 在较低的回火温度条件下,8407钢的热疲劳抗力稍优于4Cr5MoSiV1;而在高温回火时,8407钢的热疲劳抗力高于4Cr5MoSiV1钢。分析了这二种钢的热疲劳机制,指出决定材料热疲劳裂纹抗力的是钢的热稳定性和钢的强度或硬度。

  20. Management of nuclear knowledge on an international scale using a small university research reactor

    International Nuclear Information System (INIS)

    Full text: The Atominstitut Vienna operates a 250 kW TRIGA Mark-II reactor since March 1962 used for nuclear education and training in the fields of neutron- and solid state physics, nuclear technology, reactor safety, radiochemistry, radiation protection, dosimetry, low temperature physics and fusion research. During the past 20 years about 640 students graduated with a diploma - or PhD degree from the Atominstitut attached to the University of Technology Vienna. To perform nuclear relevant academic studies the Atominstitut offers about 100 highly specialised theoretical lectures and about 10 practical courses where students have to perform experiments in small groups of four on subjects mentioned above. Although the TRIGA reactor is a rather low power research reactor it is very easy and cheap to operate and an excellent tool to transfer knowledge and experience to the younger generation. This reactor is therefore not only used by other European universities such as University of Manchester or Bratislava Technical University but also by nuclear institutions such as the GRS/Germany, NPP Bohunice and NPP Mochovce for nuclear training. On an international scale the Atominstitut co-operates closely with the nearby located IAEA in international research projects, coordinated research programs (CRP) and supplying expert services. Regular training courses are carried out for the IAEA for Safeguard Trainees, fellowship places are offered for scientists from developing countries and staff members carry out expert missions to research centres in Africa, Asia and South America. In the past 20 years more than 120 IAEA fellows from all over the world have been trained at the Atominstitut. The fellows spend between one to twelve month at the Atominstitut and are integrated in the respective work program. Experience showed that out of this fellowship a long-term relation between the institutes continues. The paper focuses especially on the transfer of knowledge between

  1. Simultaneous VLBA polarimetric observations of the v=$\\{$1,2$\\}$ J=1-0 and v=1, J=2-1 SiO maser emission toward VY CMa II: component-level polarization analysis

    CERN Document Server

    Richter, L; Jonas, J

    2016-01-01

    This paper presents a component-level comparison of the polarized v=1 J =1-0, v=2 J=1-0 and v=1 J=2-1 SiO maser emission towards the supergiant star VY CMa at milliarcsecond-scale, as observed using the VLBA at $\\lambda=7$mm and $\\lambda=3$mm. An earlier paper considered overall maser morphology and constraints on SiO maser excitation and pumping derived from these data. The goal of the current paper is to use the measured polarization properties of individual co-spatial components detected across multiple transitions to provide constraints on several competing theories for the transport of polarized maser emission. This approach minimizes the significant effects of spatial blending. We present several diagnostic tests designed to distinguish key features of competing theoretical models for maser polarization. The number of coincident features is limited by sensitivity however, particularly in the v=1 J=2-1 transition at 86 GHz, and deeper observations are needed. Preliminary conclusions based on the current ...

  2. DCPT v1.0 - New particle tracker for modeling transport in dual-continuum - User's Manual

    International Nuclear Information System (INIS)

    DCPT (Dual-Continuum Particle Tracker) V1.0 is a new software for simulating solute transport in the subsurface. It is based on the random-walk method for modeling transport processes such as advection, dispersion/diffusion, linear sorption, radioactive decay, and fracture-matrix mass exchange (in fractured porous media). The user shall provide flow-field and other parameters in the form of input files. In Comparison to several analytical and numerical solutions for a number of test cases, DCPT shows excellent performance in both accuracy and efficiency. This report serves as a user's manual of DCPT V1.0. It includes theoretical basis, numerical methods, software structure, input/output description, and examples

  3. User manual of Visual Balan V. 1.0 Interactive code for water balances and refueling estimation

    International Nuclear Information System (INIS)

    This document contains the Users Manual of Visual Balan V1.0, an updated version of Visual Balan V0.0 (Samper et al., 1997). Visual Balan V1.0 performs daily water balances in the soil, the unsaturated zone and the aquifer in a user-friendly environment which facilitates both the input data process and the postprocessing of results. The main inputs of the balance are rainfall and irrigation while the outputs are surface runoff, evapotranspiration, interception, inter flow and groundwater flow. The code evaluates all these components in a sequential manner by starting with rainfall and irrigation, which must be provided by the user, and continuing with interception, surface runoff, evapotranspiration, and potential recharge (water flux crossing the bottom of the soil). This potential recharge is the input to the unsaturated zone where water can flow horizontally as subsurface flow (inter flow) or vertically as percolation into the aquifer. (Author)

  4. VLBI observations of the V=1 and V=2 SiO masers in W Hydra and VX Sagittarius

    International Nuclear Information System (INIS)

    Previous observations established the small angular size and high brightness temperature of emission from the v=1, J=1-0 transition of SiO from the circumstellar envelopes of the supergiant VX Sgr and the Mira variable R Cas. A second VLBI experiment was performed on the SiO masers in several late type stars on 31 Oct.-2 Nov. 1978 to compare the physical characteristics of the SiO masers in the v=1 and v=2 states. With an energy separation of 1258 cm-1 (an equivalent temperature of 1753 K) between the two vibrational states, differences in excitation and pumping of the maser states may lead to different maser properties. (Auth.)

  5. Morphological Substrates for Parallel Streams of Corticogeniculate Feedback Originating in Both V1 and V2 of the Macaque Monkey.

    Science.gov (United States)

    Briggs, Farran; Kiley, Caitlin W; Callaway, Edward M; Usrey, W Martin

    2016-04-20

    Corticothalamic circuits are essential for reciprocal information exchange between the thalamus and cerebral cortex. Nevertheless, the role of corticothalamic circuits in sensory processing remains a mystery. In the visual system, afferents from retina to the lateral geniculate nucleus (LGN) and from LGN to primary visual cortex (V1) are organized into functionally distinct parallel processing streams. Physiological evidence suggests corticogeniculate feedback may be organized into parallel streams; however, little is known about the diversity of corticogeniculate neurons, their local computations, or the structure-function relationship among corticogeniculate neurons. We used a virus-mediated approach to label and reconstruct the complete dendritic and local axonal arbors of identified corticogeniculate neurons in the macaque monkey. Our results reveal morphological substrates for parallel streams of corticogeniculate feedback based on distinct classes of neurons in V1 and V2. These results support the hypothesis that distinct populations of feedback neurons provide independent and unique information to the LGN. PMID:27041497

  6. Analgesic Effects of GpTx-1, PF-04856264 and CNV1014802 in a Mouse Model of NaV1.7-Mediated Pain.

    Science.gov (United States)

    Deuis, Jennifer R; Wingerd, Joshua S; Winter, Zoltan; Durek, Thomas; Dekan, Zoltan; Sousa, Silmara R; Zimmermann, Katharina; Hoffmann, Tali; Weidner, Christian; Nassar, Mohammed A; Alewood, Paul F; Lewis, Richard J; Vetter, Irina

    2016-01-01

    Loss-of-function mutations of NaV1.7 lead to congenital insensitivity to pain, a rare condition resulting in individuals who are otherwise normal except for the inability to sense pain, making pharmacological inhibition of NaV1.7 a promising therapeutic strategy for the treatment of pain. We characterized a novel mouse model of NaV1.7-mediated pain based on intraplantar injection of the scorpion toxin OD1, which is suitable for rapid in vivo profiling of NaV1.7 inhibitors. Intraplantar injection of OD1 caused spontaneous pain behaviors, which were reversed by co-injection with NaV1.7 inhibitors and significantly reduced in NaV1.7(-/-) mice. To validate the use of the model for profiling NaV1.7 inhibitors, we determined the NaV selectivity and tested the efficacy of the reported NaV1.7 inhibitors GpTx-1, PF-04856264 and CNV1014802 (raxatrigine). GpTx-1 selectively inhibited NaV1.7 and was effective when co-administered with OD1, but lacked efficacy when delivered systemically. PF-04856264 state-dependently and selectively inhibited NaV1.7 and significantly reduced OD1-induced spontaneous pain when delivered locally and systemically. CNV1014802 state-dependently, but non-selectively, inhibited NaV channels and was only effective in the OD1 model when delivered systemically. Our novel model of NaV1.7-mediated pain based on intraplantar injection of OD1 is thus suitable for the rapid in vivo characterization of the analgesic efficacy of NaV1.7 inhibitors. PMID:26999206

  7. Regulation of the Spontaneous Augmentation of NaV1.9 in Mouse Dorsal Root Ganglion Neurons: Effect of PKA and PKC Pathways

    Directory of Open Access Journals (Sweden)

    Nobukuni Ogata

    2010-03-01

    Full Text Available Sensory neurons in the dorsal root ganglion express two kinds of tetrodotoxin resistant (TTX-R isoforms of voltage-gated sodium channels, NaV1.8 and NaV1.9. These isoforms play key roles in the pathophysiology of chronic pain. Of special interest is NaV1.9: our previous studies revealed a unique property of the NaV1.9 current, i.e., the NaV1.9 current shows a gradual and notable up-regulation of the peak amplitude during recording (“spontaneous augmentation of NaV1.9”. However, the mechanism underlying the spontaneous augmentation of NaV1.9 is still unclear. In this study, we examined the effects of protein kinases A and C (PKA and PKC, on the spontaneous augmentation of NaV1.9. The spontaneous augmentation of the NaV1.9 current was significantly suppressed by activation of PKA, whereas activation of PKA did not affect the voltage dependence of inactivation for the NaV1.9 current. On the contrary, the finding that activation of PKC can affect the voltage dependence of inactivation for NaV1.9 in the perforated patch recordings, where the augmentation does not occur, suggests that the effects of PMA are independent of the augmentation process. These results indicate that the spontaneous augmentation of NaV1.9 was regulated directly by PKA, and indirectly by PKC.

  8. Survey of research reactors

    International Nuclear Information System (INIS)

    A survey of reasearch reactors based on the IAEA Nuclear Research Reactor Data Base (RRDB) was done. This database includes information on 273 operating research reactors ranging in power from zero to several hundred MW. From these 273 operating research reactors 205 reactors have a power level below 5 MW, the remaining 68 reactors range from 5 MW up to several 100 MW thermal power. The major reactor types with common design are: Siemens Unterrichtsreaktors, 1.2 Argonaut reactors, Slowpoke reactors, the miniature neutron source reactors, TRIGA reactors, material testing reactors and high flux reactors. Technical data such as: power, fuel material, fuel type, enrichment, maximum neutron flux density and experimental facilities for each reactor type as well as a description of their utilization in physics and chemistry, medicine and biology, academic research and teaching, training purposes (students and physicists, operating personnel), industrial application (neutron radiography, silicon neutron transmutation doping facilities) are provided. The geographically distribution of these reactors is also shown. As conclusions the author discussed the advantages (low capital cost, low operating cost, low burn up, simple to operate, safe, less restrictive containment and sitting requirements, versatility) and disadvantages (lower sensitivity for NAA, limited radioisotope production, limited use of neutron beams, limited access to the core, licensing) of low power research reactors. 24 figs., refs. 15, Tab. 1 (nevyjel)

  9. Department of reactor technology

    International Nuclear Information System (INIS)

    The activities of the Department of Reactor Technology at Risoe during 1979 are described. The work is presented in five chapters: Reactor Engineering, Reactor Physics and Dynamics, Heat Transfer and Hydraulics, The DR 1 Reactor, and Non-Nuclear Activities. A list of the staff and of publications is included. (author)

  10. RB reactor noise analysis

    International Nuclear Information System (INIS)

    Statistical fluctuations of reactivity represent reactor noise. Analysis of reactor noise enables determining a series of reactor kinetic parameters. Fluctuations of power was measured by ionization chamber placed next to the tank of the RB reactor. The signal was digitized by an analog-digital converter. After calculation of the mean power, 3000 data obtained by sampling were analysed

  11. Stability of simple/complex classification with contrast and extraclassical receptive field modulation in macaque V1

    OpenAIRE

    Henry, Christopher A.; Hawken, Michael J.

    2013-01-01

    A key property of neurons in primary visual cortex (V1) is the distinction between simple and complex cells. Recent reports in cat visual cortex indicate the categorization of simple and complex can change depending on stimulus conditions. We investigated the stability of the simple/complex classification with changes in drive produced by either contrast or modulation by the extraclassical receptive field (eCRF). These two conditions were reported to increase the proportion of simple cells in...

  12. Analysis of Location of Laminar-Turbulent Transition on the FX 66-S-196 V1 Airfoil

    Directory of Open Access Journals (Sweden)

    Laurynas Naujokaitis

    2011-04-01

    Full Text Available The transition location on the FX 66‑S‑196 V1 wing section was analyzed with the using interactive program XFOIL of Mark Drela, MIT. Calculated results of transition location were compared with published measurement data from a wind tunnel at Delft University of Technology (Netherlands. The airfoil was analyzed at the Reynolds number Re = 0,5·106 and Re = 1,5·106. Article in Lithuanian

  13. Angular, velocity, rotational, and electronic distributions of vibrationally elastically scattered NO(v = 1) from LiF(100)

    Energy Technology Data Exchange (ETDEWEB)

    Misewich, J.; Zacharias, H.; Loy, M.M.T.

    1985-09-01

    Infrared laser excitation has been utilized to excite part of a molecular beam of NO to a single well-defined quantum state, NO(v = 1, J = 3/2, ..cap omega.. = 1/2), which is scattered from a cleaved LiF(100) surface. Laser spectroscopic detection techniques then allow the determination of rotational and electronic distributions as well as state-specific angular and velocity distributions for scattering from a single initial vibrational-rotational state.

  14. Dynamics of orientation tuning in cat V1 neurons depend on location within layers and orientation maps

    Directory of Open Access Journals (Sweden)

    Klaus Wimmer

    2007-10-01

    Full Text Available Analysis of the timecourse of the orientation tuning of responses in primary visual cortex (V1 can provide insight into the circuitry underlying tuning. Several studies have examined the temporal evolution of orientation selectivity in V1 neurons, but there is no consensus regarding the stability of orientation tuning properties over the timecourse of the response. We have used reverse-correlation analysis of the responses to dynamic grating stimuli to re-examine this issue in cat V1 neurons. We find that the preferred orientation and tuning curve shape are stable in the majority of neurons; however, more than forty percent of cells show a significant change in either preferred orientation or tuning width between early and late portions of the response. To examine the influence of the local cortical circuit connectivity, we analyzed the timecourse of responses as a function of receptive field type, laminar position, and orientation map position. Simple cells are more selective, and reach peak selectivity earlier, than complex cells. There are pronounced laminar differences in the timing of responses: middle layer cells respond faster, deep layer cells have prolonged response decay, and superficial cells are intermediate in timing. The average timing of neurons near and far from pinwheel centers is similar, but there is more variability in the timecourse of responses near pinwheel centers. This result was reproduced in an established network model of V1 operating in a regime of balanced excitatory and inhibitory recurrent connections, confirming previous results. Thus, response dynamics of cortical neurons reflect circuitry based on both vertical and horizontal location within cortical networks.

  15. The impact of nitration on the structure and immunogenicity of the major birch pollen allergen Bet v 1.0101.

    Directory of Open Access Journals (Sweden)

    Chloé Ackaert

    Full Text Available Allergy prevalence has increased in industrialized countries. One contributing factor could be pollution, which can cause nitration of allergens exogenously (in the air or endogenously (in inflamed lung tissue. We investigated the impact of nitration on both the structural and immunological behavior of the major birch pollen allergen Bet v 1.0101 to determine whether nitration might be a factor in the increased incidence of allergy. Bet v 1.0101 was nitrated with tetranitromethane. Immune effects were assessed by measuring the proliferation of specific T-cell lines (TCLs upon stimulation with different concentrations of nitrated and unmodified allergen, and by measurement of cytokine release of monocyte-derived dendritic cells (moDCs and primary DCs (primDCs stimulated with nitrated versus unmodified allergen. HPLC-MS, crystallography, gel electrophoresis, amino acid analysis, size exclusion chromatography and molecular dynamics simulation were performed to characterize structural changes after nitration of the allergen. The proliferation of specific TCLs was higher upon stimulation with the nitrated allergen in comparison to the unmodified allergen. An important structural consequence of nitration was oligomerization. Moreover, analysis of the crystal structure of nitrated Bet v 1.0101 showed that amino acid residue Y83, located in the hydrophobic cavity, was nitrated to 100%. Both moDCs and primDCs showed decreased production of TH1-priming cytokines, thus favoring a TH2 response. These results implicate that nitration of Bet v 1.0101 might be a contributing factor to the observed increase in birch pollen allergy, and emphasize the importance of protein modifications in understanding the molecular basis of allergenicity.

  16. CONTRIBUTION OF APICAL DENDRITES TO RECEPTIVE FIELD PROPERTIES IN LAYER 2/3 OF MOUSE V1

    Directory of Open Access Journals (Sweden)

    Jiyoung Park

    2014-03-01

    Full Text Available Although slice recordings and model studies provide a lot of information about how neurons integrate their inputs to overall responses, it is still not clear how neurons in the brain integrate their synaptic inputs to derive their functional properties in vivo. Pyramidal neurons in layer 2/3 of mouse V1 receive input from LGN via layer 4 and feedback from higher visual areas. Here, we focus on the function of apical dendrites, which play an important role in communicating with higher visual areas. We ablate apical dendrites of layer 2/3 pyramidal neurons in area V1, in vivo, and monitor their responses to visual stimuli by two photon microscopy. We compare orientation selectivity, contrast sensitivity and other receptive field properties of L2/3 pyramidal neurons before and after selective apical dendritic ablation. This approach provides information on how different dendritic inputs contribute to neuronal receptive field properties of L2/3 pyramidal neurons in mouse V1.

  17. MATISSE-v1.5 and MATISSE-v2.0: new developments and comparison with MIRAMER measurements

    Science.gov (United States)

    Simoneau, Pierre; Caillault, Karine; Fauqueux, Sandrine; Huet, Thierry; Labarre, Luc; Malherbe, Claire; Rosier, Bernard

    2009-05-01

    MATISSE is a background scene generator developed for the computation of natural background spectral radiance images and useful atmospheric radiatives quantities (radiance and transmission along a line of sight, local illumination, solar irradiance ...). The spectral bandwidth ranges from 0.4 to 14 μm. Natural backgrounds include atmosphere (taking into account spatial variability), low and high altitude clouds, sea and land. The current version MATISSE-v1.5 can be run on SUN and IBM workstations as well as on PC under Windows and Linux environment. An IHM developed under Java environment is also implemented. MATISSE-v2.0 recovers all the MATISSE-v1.5 functionalities, and includes a new sea surface radiance model depending on wind speed, wind direction and the fetch value. The release of this new version in planned for April 2009. This paper gives a description of MATISSE-v1.5 and MATISSE-v2.0 and shows preliminary comparison results between generated images and measured images during the MIRAMER campaign, which hold in May 2008 in the Mediterranean Sea.

  18. Prdm12 specifies V1 interneurons through cross-repressive interactions with Dbx1 and Nkx6 genes in Xenopus.

    Science.gov (United States)

    Thélie, Aurore; Desiderio, Simon; Hanotel, Julie; Quigley, Ian; Van Driessche, Benoit; Rodari, Anthony; Borromeo, Mark D; Kricha, Sadia; Lahaye, François; Croce, Jenifer; Cerda-Moya, Gustavo; Ordoño Fernandez, Jesús; Bolle, Barbara; Lewis, Katharine E; Sander, Maike; Pierani, Alessandra; Schubert, Michael; Johnson, Jane E; Kintner, Christopher R; Pieler, Tomas; Van Lint, Carine; Henningfeld, Kristine A; Bellefroid, Eric J; Van Campenhout, Claude

    2015-10-01

    V1 interneurons are inhibitory neurons that play an essential role in vertebrate locomotion. The molecular mechanisms underlying their genesis remain, however, largely undefined. Here, we show that the transcription factor Prdm12 is selectively expressed in p1 progenitors of the hindbrain and spinal cord in the frog embryo, and that a similar restricted expression profile is observed in the nerve cord of other vertebrates as well as of the cephalochordate amphioxus. Using frog, chick and mice, we analyzed the regulation of Prdm12 and found that its expression in the caudal neural tube is dependent on retinoic acid and Pax6, and that it is restricted to p1 progenitors, due to the repressive action of Dbx1 and Nkx6-1/2 expressed in the adjacent p0 and p2 domains. Functional studies in the frog, including genome-wide identification of its targets by RNA-seq and ChIP-Seq, reveal that vertebrate Prdm12 proteins act as a general determinant of V1 cell fate, at least in part, by directly repressing Dbx1 and Nkx6 genes. This probably occurs by recruiting the methyltransferase G9a, an activity that is not displayed by the amphioxus Prdm12 protein. Together, these findings indicate that Prdm12 promotes V1 interneurons through cross-repressive interactions with Dbx1 and Nkx6 genes, and suggest that this function might have only been acquired after the split of the vertebrate and cephalochordate lineages. PMID:26443638

  19. Early Posttransplant Isolated v1 Lesion Does Not Need to Be Treated and Does Not Lead to Increased Fibrosis

    Directory of Open Access Journals (Sweden)

    Irfan Moinuddin

    2016-01-01

    Full Text Available Acute vascular rejection (AVR is characterized by intimal arteritis in addition to tubulitis and interstitial inflammation. It is associated with a poorer prognosis compared to tubulointerstitial rejection (AIR and AVR is associated with a higher rate of graft loss than AIR. The prognosis and treatment of arteritis without tubulitis and interstitial inflammation (isolated v1 lesion are still controversial. We report a case of a patient who had a biopsy of the kidney allograft for evaluation of slow graft function. The biopsy revealed an isolated v1 lesion. However, we chose not to augment immunosuppression. The patient’s kidney allograft function improved over time with close monitoring. Repeat biopsy a year later showed no evidence of endothelialitis and relatively unchanged fibrosis and no other abnormalities. Although it is suggested that most cases of isolated v1 lesions will respond to corticosteroids or T cell depleting therapies, some cases will improve with conservative management. Further studies are needed to determine which cases could be managed conservatively.

  20. Biophysical characterization data of the artificial protein Octarellin V.1 and binding test with its X-ray helpers.

    Science.gov (United States)

    Figueroa, Maximiliano; Vandenameele, Julie; Goormaghtigh, Erik; Valerio-Lepiniec, Marie; Minard, Philippe; Matagne, André; Van de Weerdt, Cécile

    2016-09-01

    The artificial protein Octarellin V.1 (http://dx.doi.org/10.1016/j.jsb.2016.05.004[1]) was obtained through a direct evolution process over the de novo designed Octarellin V (http://dx.doi.org/10.1016/S0022-2836(02)01206-8[2]). The protein has been characterized by circular dichroism and fluorescence techniques, in order to obtain data related to its thermo and chemical stability. Moreover, the data for the secondary structure content studied by circular dichroism and infra red techniques is reported for the Octarellin V and V.1. Two crystallization helpers, nanobodies (http://dx.doi.org/10.1038/nprot.2014.039[3]) and αRep (http://dx.doi.org/10.1016/j.jmb.2010.09.048[4]), have been used to create stable complexes. Here we present the data obtained of the binding characterization of the Octarellin V.1 with the crystallization helpers by isothermal titration calorimetry. PMID:27547801

  1. The unexpected structure of the designed protein Octarellin V.1 forms a challenge for protein structure prediction tools.

    Science.gov (United States)

    Figueroa, Maximiliano; Sleutel, Mike; Vandevenne, Marylene; Parvizi, Gregory; Attout, Sophie; Jacquin, Olivier; Vandenameele, Julie; Fischer, Axel W; Damblon, Christian; Goormaghtigh, Erik; Valerio-Lepiniec, Marie; Urvoas, Agathe; Durand, Dominique; Pardon, Els; Steyaert, Jan; Minard, Philippe; Maes, Dominique; Meiler, Jens; Matagne, André; Martial, Joseph A; Van de Weerdt, Cécile

    2016-07-01

    Despite impressive successes in protein design, designing a well-folded protein of more 100 amino acids de novo remains a formidable challenge. Exploiting the promising biophysical features of the artificial protein Octarellin V, we improved this protein by directed evolution, thus creating a more stable and soluble protein: Octarellin V.1. Next, we obtained crystals of Octarellin V.1 in complex with crystallization chaperons and determined the tertiary structure. The experimental structure of Octarellin V.1 differs from its in silico design: the (αβα) sandwich architecture bears some resemblance to a Rossman-like fold instead of the intended TIM-barrel fold. This surprising result gave us a unique and attractive opportunity to test the state of the art in protein structure prediction, using this artificial protein free of any natural selection. We tested 13 automated webservers for protein structure prediction and found none of them to predict the actual structure. More than 50% of them predicted a TIM-barrel fold, i.e. the structure we set out to design more than 10years ago. In addition, local software runs that are human operated can sample a structure similar to the experimental one but fail in selecting it, suggesting that the scoring and ranking functions should be improved. We propose that artificial proteins could be used as tools to test the accuracy of protein structure prediction algorithms, because their lack of evolutionary pressure and unique sequences features. PMID:27181418

  2. Engineering potent and selective analogues of GpTx-1, a tarantula venom peptide antagonist of the Na(V)1.7 sodium channel.

    Science.gov (United States)

    Murray, Justin K; Ligutti, Joseph; Liu, Dong; Zou, Anruo; Poppe, Leszek; Li, Hongyan; Andrews, Kristin L; Moyer, Bryan D; McDonough, Stefan I; Favreau, Philippe; Stöcklin, Reto; Miranda, Les P

    2015-03-12

    NaV1.7 is a voltage-gated sodium ion channel implicated by human genetic evidence as a therapeutic target for the treatment of pain. Screening fractionated venom from the tarantula Grammostola porteri led to the identification of a 34-residue peptide, termed GpTx-1, with potent activity on NaV1.7 (IC50 = 10 nM) and promising selectivity against key NaV subtypes (20× and 1000× over NaV1.4 and NaV1.5, respectively). NMR structural analysis of the chemically synthesized three disulfide peptide was consistent with an inhibitory cystine knot motif. Alanine scanning of GpTx-1 revealed that residues Trp(29), Lys(31), and Phe(34) near the C-terminus are critical for potent NaV1.7 antagonist activity. Substitution of Ala for Phe at position 5 conferred 300-fold selectivity against NaV1.4. A structure-guided campaign afforded additive improvements in potency and NaV subtype selectivity, culminating in the design of [Ala5,Phe6,Leu26,Arg28]GpTx-1 with a NaV1.7 IC50 value of 1.6 nM and >1000× selectivity against NaV1.4 and NaV1.5. PMID:25658507

  3. Upgrading of existing NPPs with 440 and 1000 MW WWER type pressurized water reactors for severe external loading conditions. Proceedings. Working material. V. 1, 2

    International Nuclear Information System (INIS)

    The Seminar was intended to provide the opportunity for the exchange of updated information concerning the state-of-the-art related to structural safety of the WWER 440 and 1000 MW nuclear power plants operating or under construction in the Russian Federation and several Eastern European countries. Codes and standards, design assumptions, seismic upgrading and requalification activities, recent verification by experimental methods as well as the corresponding reanalysis and reevaluation procedures were included in the scope. Also presented and discussed were the results of recent studies of typical structures and components under seismic loading. The Seminar was divided into five working sessions. Each session consisted of several presentations by invited speakers and extensive discussions. The topic of discussions involved the following: standards used during design phase, input load definitions and criteria, evaluation of as-built conditions and walk down information, site-specific dynamic response of structures based on recent studies and evaluation of results, capacity evaluations of components and systems based on updated acceptance criteria and strengthening concepts, functional qualification of active mechanical and electrical components and systems

  4. MEGAHIT v1.0: A fast and scalable metagenome assembler driven by advanced methodologies and community practices.

    Science.gov (United States)

    Li, Dinghua; Luo, Ruibang; Liu, Chi-Man; Leung, Chi-Ming; Ting, Hing-Fung; Sadakane, Kunihiko; Yamashita, Hiroshi; Lam, Tak-Wah

    2016-06-01

    The study of metagenomics has been much benefited from low-cost and high-throughput sequencing technologies, yet the tremendous amount of data generated make analysis like de novo assembly to consume too much computational resources. In late 2014 we released MEGAHIT v0.1 (together with a brief note of Li et al. (2015) [1]), which is the first NGS metagenome assembler that can assemble genome sequences from metagenomic datasets of hundreds of Giga base-pairs (bp) in a time- and memory-efficient manner on a single server. The core of MEGAHIT is an efficient parallel algorithm for constructing succinct de Bruijn Graphs (SdBG), implemented on a graphical processing unit (GPU). The software has been well received by the assembly community, and there is interest in how to adapt the algorithms to integrate popular assembly practices so as to improve the assembly quality, as well as how to speed up the software using better CPU-based algorithms (instead of GPU). In this paper we first describe the details of the core algorithms in MEGAHIT v0.1, and then we show the new modules to upgrade MEGAHIT to version v1.0, which gives better assembly quality, runs faster and uses less memory. For the Iowa Prairie Soil dataset (252Gbp after quality trimming), the assembly quality of MEGAHIT v1.0, when compared with v0.1, has a significant improvement, namely, 36% increase in assembly size and 23% in N50. More interestingly, MEGAHIT v1.0 is no slower than before (even running with the extra modules). This is primarily due to a new CPU-based algorithm for SdBG construction that is faster and requires less memory. Using CPU only, MEGAHIT v1.0 can assemble the Iowa Prairie Soil sample in about 43h, reducing the running time of v0.1 by at least 25% and memory usage by up to 50%. MEGAHIT v1.0, exhibiting a smaller memory footprint, can process even larger datasets. The Kansas Prairie Soil sample (484Gbp), the largest publicly available dataset, can now be assembled using no more than 500GB

  5. Research Nuclear Reactors

    International Nuclear Information System (INIS)

    Published in English and in French, this large report first proposes an overview of the use and history of research nuclear reactors. It discusses their definition, and presents the various types of research reactors which can be either related to nuclear power (critical mock-ups, material test reactors, safety test reactors, training reactors, prototypes), or to research (basic research, industry, health), or to specific particle physics phenomena (neutron diffraction, isotope production, neutron activation, neutron radiography, semiconductor doping). It reports the history of the French research reactors by distinguishing the first atomic pile (ZOE), and the activities and achievements during the fifties, the sixties and the seventies. It also addresses the development of instrumentation for research reactors (neutron, thermal, mechanical and fission gas release measurements). The other parts of the report concern the validation of neutronics calculations for different reactors (the EOLE water critical mock-up, the MASURCA air critical mock-up dedicated to fast neutron reactor study, the MINERVE water critical mock-up, the CALIBAN pulsed research reactor), the testing of materials under irradiation (OSIRIS reactor, laboratories associated with research reactors, the Jules Horowitz reactor and its experimental programs and related devices, irradiation of materials with ion beams), the investigation of accident situations (on the CABRI, Phebus, Silene and Jules Horowitz reactors). The last part proposes a worldwide overview of research reactors

  6. Options for disposal of radioactive wastes arising from steam generator dismantling. Assessment from the external exposure aspect

    International Nuclear Information System (INIS)

    The paper focuses on steam generator dismantling at the Jaslovske Bohunice V1 nuclear power plant with VVER-440/230 reactors. The VISIPLAN 3D ALARA computer code was used to calculate external exposure arising from radiation existing on the waste package surface. The dependence of the external exposure on the internal configuration of the waste was investigated. The effect of the waste storage time (before packaging and disposal) and on personnel exposure was also examined and the suitability of the various decontamination techniques was assessed. (orig.)

  7. Considerations about the European Decommissioning Academy (EDA)

    International Nuclear Information System (INIS)

    The concept of the European Decommissioning Academy, to be launched in Slovakia in June 2015, is described. The main goal is to educate a new generation of experts in the decommissioning of nuclear facilities, with focus on VVER type reactors. This year the Academy activities will include lessons, practical exercises in laboratories, and 2 days on-site training at the Jaslovske Bohunice V-1 nuclear power plant. A 4-days' visit to major European decommissioning facilities in Switzerland and Italy is also planned. (orig.)

  8. Reactor Physics Training

    International Nuclear Information System (INIS)

    University courses in nuclear reactor physics at the universities consist of a theoretical description of the physics and technology of nuclear reactors. In order to demonstrate the basic concepts in reactor physics, training exercises in nuclear reactor installations are also desirable. Since the number of reactor facilities is however strongly decreasing in Europe, it becomes difficult to offer to students a means for demonstrating the basic concepts in reactor physics by performing training exercises in nuclear installations. Universities do not generally possess the capabilities for performing training exercises. Therefore, SCK-CEN offers universities the possibility to perform (on a commercial basis) training exercises at its infrastructure consisting of two research reactors (BR1 and VENUS). Besides the organisation of training exercises in the framework of university courses, SCK-CEN also organizes theoretical courses in reactor physics for the education and training of nuclear reactor operators. It is indeed a very important subject to guarantee the safe operation of present and future nuclear reactors. In this framework, an understanding of the fundamental principles of nuclear reactor physics is also necessary for reactor operators. Therefore, the organisation of a basic Nuclear reactor physics course at the level of reactor operators in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The objectives this activity are: (1) to provide training and education activities in reactor physics for university students and (2) to organise courses in nuclear reactor physics for reactor operators

  9. Introduction of Nuclear Reactor Engineering

    International Nuclear Information System (INIS)

    This book introduces development, status, supply and demand and resource of nuclear reactor. It deals with basic knowledge of nuclear reactor, which are reactor system, heat recovery in reactor core, structural feature in reactor, materials of structure in reactor, shielding of gamma ray, shielding of reactor, safety and environmental problem of nuclear power plant, nuclear fuel and economical efficiency of nuclear energy.

  10. Assessment of influence on the environment at closing down of nuclear facilities

    International Nuclear Information System (INIS)

    In this paper author presents the duties of the Nuclear Regulatory Authority of the Slovak Republic at the assessment of the influence on the environment at closing down of the nuclear facilities. Legislative aspect of decommissioning of the A-1 Jaslovske Bohunice NPP as well as closing down of the V-1 Jaslovske Bohunice NPP are discussed

  11. Simultaneous VLBA polarimetric observations of the v={1,2} J=1-0 and v=1, J=2-1 SiO maser emission toward VY CMa II: component-level polarization analysis.

    Science.gov (United States)

    Richter, L.; Kemball, A.; Jonas, J.

    2016-06-01

    This paper presents a component-level comparison of the polarized v=1 J =1-0, v=2 J=1-0 and v=1 J=2-1 SiO maser emission towards the supergiant star VY CMa at milliarcsecond-scale, as observed using the VLBA at λ = 7mm and λ = 3mm. An earlier paper considered overall maser morphology and constraints on SiO maser excitation and pumping derived from these data. The goal of the current paper is to use the measured polarization properties of individual co-spatial components detected across multiple transitions to provide constraints on several competing theories for the transport of polarized maser emission. This approach minimizes the significant effects of spatial blending. We present several diagnostic tests designed to distinguish key features of competing theoretical models for maser polarization. The number of coincident features is limited by sensitivity however, particularly in the v=1 J=2-1 transition at 86 GHz, and deeper observations are needed. Preliminary conclusions based on the current data provide some support for: i) spin-independent solutions for linear polarization; ii) the influence of geometry on the distribution of fractional linear polarization with intensity; and, iii) π/2 rotations in linear polarization position angle arising from transitions across the Van Vleck angle (sin 2θ = 2/3) between the maser line-of-sight and magnetic field. There is weaker evidence for several enumerated non-Zeeman explanations for circular polarization. The expected 2:1 ratio in circular polarization between J=1-0 and J=2-1 predicted by standard Zeeman theory cannot unfortunately be tested conclusively due to insufficient coincident components.

  12. Simultaneous VLBA polarimetric observations of the v = {1,2} J = 1-0 and v = 1, J = 2-1 SiO maser emission towards VY CMa II: component-level polarization analysis

    Science.gov (United States)

    Richter, L.; Kemball, A.; Jonas, J.

    2016-09-01

    This paper presents a component-level comparison of the polarized v = 1 J = 1-0, v = 2 J = 1-0 and v = 1 J = 2-1 SiO maser emission towards the supergiant star VY CMa at milliarcsecond-scale, as observed using the Very Long Baseline Array at λ = 7 and 3 mm. An earlier paper considered overall maser morphology and constraints on SiO maser excitation and pumping derived from these data. The goal of the current paper is to use the measured polarization properties of individual co-spatial components detected across multiple transitions to provide constraints on several competing theories for the transport of polarized maser emission. This approach minimizes the significant effects of spatial blending. We present several diagnostic tests designed to distinguish key features of competing theoretical models for maser polarization. The number of coincident features is limited by sensitivity however, particularly in the v = 1 J = 2-1 transition at 86 GHz, and deeper observations are needed. Preliminary conclusions based on the current data provide some support for: (i) spin-independent solutions for linear polarization; (ii) the influence of geometry on the distribution of fractional linear polarization with intensity; and, (iii) π/2 rotations in linear polarization position angle arising from transitions across the Van Vleck angle (sin 2θ = 2/3) between the maser line of sight and magnetic field. There is weaker evidence for several enumerated non-Zeeman explanations for circular polarization. The expected 2:1 ratio in circular polarization between J = 1-0 and J = 2-1 predicted by standard Zeeman theory cannot unfortunately be tested conclusively due to insufficient coincident components.

  13. Effects of Amyloid-β Peptides on Voltage-Gated L-Type CaV1.2 and CaV1.3 Ca2+ Channels

    OpenAIRE

    Kim, Sunoh; Rhim, Hyewhon

    2011-01-01

    Overload of intracellular Ca2+ has been implicated in the pathogenesis of neuronal disorders, such as Alzheimer’s disease. Various mechanisms produce abnormalities in intracellular Ca2+ homeostasis systems. L-type Ca2+ channels have been known to be closely involved in the mechanisms underlying the neurodegenerative properties of amyloid-β (Aβ) peptides. However, most studies of L-type Ca2+ channels in Aβ-related mechanisms have been limited to CaV1.2, and surprisingly little is known about t...

  14. Safeguarding research reactors

    International Nuclear Information System (INIS)

    The report is organized in four sections, including the introduction. The second section contains a discussion of the characteristics and attributes of research reactors important to safeguards. In this section, research reactors are described according to their power level, if greater than 25 thermal megawatts, or according to each fuel type. This descriptive discussion includes both reactor and reactor fuel information of a generic nature, according to the following categories. 1. Research reactors with more than 25 megawatts thermal power, 2. Plate fuelled reactors, 3. Assembly fuelled reactors. 4. Research reactors fuelled with individual rods. 5. Disk fuelled reactors, and 6. Research reactors fuelled with aqueous homogeneous fuel. The third section consists of a brief discussion of general IAEA safeguards as they apply to research reactors. This section is based on IAEA safeguards implementation documents and technical reports that are used to establish Agency-State agreements and facility attachments. The fourth and last section describes inspection activities at research reactors necessary to meet Agency objectives. The scope of the activities extends to both pre and post inspection as well as the on-site inspection and includes the examination of records and reports relative to reactor operation and to receipts, shipments and certain internal transfers, periodic verification of fresh fuel, spent fuel and core fuel, activities related to containment and surveillance, and other selected activities, depending on the reactor

  15. Research nuclear reactors

    International Nuclear Information System (INIS)

    Since the divergence of the first nuclear reactor in 1942, about 600 research or test reactors have been built throughout the world. Today 255 research reactors are operating in 57 countries and about 70% are over 25 years old. Whereas there are very few reactor types for power plants because of rationalization and standardisation, there is a great diversity of research reactors. We can divide them into 2 groups: heavy water cooled reactors and light water moderated reactors. Heavy water cooled reactors are dedicated to the production of high flux of thermal neutrons which are extracted from the core by means of neutronic channels. Light water moderated reactors involved pool reactors and slightly pressurized closed reactors, they are polyvalent but their main purposes are material testing, technological irradiations, radionuclide production and neutron radiography. At the moment 8 research reactors are being built in Canada, Germany, Iran, Japan, Kazakhstan, Morocco, Russia and Slovakia and 8 others are planned in 7 countries (France, Indonesia, Nigeria, Russia, Slovakia, Thailand and Tunisia. Different research reactors are described: Phebus, Masurca, Phenix and Petten HFR. The general principles of nuclear safety applied to test reactors are presented. (A.C.)

  16. Dominating IgE-binding epitope of Bet v 1, the major allergen of birch pollen, characterized by X-ray crystallography and site-directed mutagenesis

    DEFF Research Database (Denmark)

    Spangfort, Michael D; Mirza, Osman; Ipsen, Henrik;

    2003-01-01

    surface area of Bet v 1 and is clearly conformational. A synthetic peptide representing a sequential motif in the epitope (11 of 16 residues) did not inhibit the binding of mAb BV16 to Bet v 1, illustrating limitations in the use of peptides for B cell epitope characterization. The single amino acid...

  17. Nuclear reactor building

    International Nuclear Information System (INIS)

    Purpose: To prevent seismic vibrations of external buildings from transmitting to the side walls of a reactor container in a tank type FBR reactor building. Constitution: The reactor building is structured such that the base mat for a reactor container chamber and a reactor container is separated from the base mat for the walls of building, and gas-tight material such as silicon rubber is filled in the gap therebetween. With such a constitution, even if the crane-supporting wall vibrates violently upon occurrence of earthqualkes, the seismic vibrations do not transmit toward the reactor container chamber. (Horiuchi, T.)

  18. Animation of natural scene by virtual eye-movements evokes high precision and low noise in V1 neurons.

    Science.gov (United States)

    Baudot, Pierre; Levy, Manuel; Marre, Olivier; Monier, Cyril; Pananceau, Marc; Frégnac, Yves

    2013-01-01

    Synaptic noise is thought to be a limiting factor for computational efficiency in the brain. In visual cortex (V1), ongoing activity is present in vivo, and spiking responses to simple stimuli are highly unreliable across trials. Stimulus statistics used to plot receptive fields, however, are quite different from those experienced during natural visuomotor exploration. We recorded V1 neurons intracellularly in the anaesthetized and paralyzed cat and compared their spiking and synaptic responses to full field natural images animated by simulated eye-movements to those evoked by simpler (grating) or higher dimensionality statistics (dense noise). In most cells, natural scene animation was the only condition where high temporal precision (in the 10-20 ms range) was maintained during sparse and reliable activity. At the subthreshold level, irregular but highly reproducible membrane potential dynamics were observed, even during long (several 100 ms) "spike-less" periods. We showed that both the spatial structure of natural scenes and the temporal dynamics of eye-movements increase the signal-to-noise ratio by a non-linear amplification of the signal combined with a reduction of the subthreshold contextual noise. These data support the view that the sparsening and the time precision of the neural code in V1 may depend primarily on three factors: (1) broadband input spectrum: the bandwidth must be rich enough for recruiting optimally the diversity of spatial and time constants during recurrent processing; (2) tight temporal interplay of excitation and inhibition: conductance measurements demonstrate that natural scene statistics narrow selectively the duration of the spiking opportunity window during which the balance between excitation and inhibition changes transiently and reversibly; (3) signal energy in the lower frequency band: a minimal level of power is needed below 10 Hz to reach consistently the spiking threshold, a situation rarely reached with visual dense

  19. Defect structure of epitaxial CrxV1−x thin films on MgO(001)

    International Nuclear Information System (INIS)

    Epitaxial thin films of CrxV1−x over the entire composition range were deposited on MgO(001) by molecular beam epitaxy. The films exhibited the expected 45° in-plane rotation with no evidence of phase segregation or spinodal decomposition. Pure Cr, with the largest lattice mismatch to MgO, exhibited full relaxation and cubic lattice parameters. As the lattice mismatch decreased with alloy composition, residual epitaxial strain was observed. For 0.2 ≤ x ≤ 0.4 the films were coherently strained to the substrate with associated tetragonal distortion; near the lattice-matched composition of x = 0.33, the films exhibited strain-free pseudomorphic matching to MgO. Unusually, films on the Cr-rich side of the lattice-matched composition exhibited more in-plane compression than expected from the bulk lattice parameters; this result was confirmed with both x-ray diffraction and Rutherford backscattering spectrometry channeling measurements. The effect of thermal expansion mismatch on strain in the heterostructure was estimated. High resolution transmission electron microscopy was utilized to characterize the misfit dislocation network present at the film/MgO interface. Dislocations were found to be present with a non-uniform distribution, which is attributed to the Volmer–Weber growth mode of the films. The CrxV1−x/MgO(001) system can serve as a model system to study the fundamentals of defect formation in bcc films. - Highlights: • Epitaxial CrxV1−x thin films were deposited on MgO(001) by molecular beam epitaxy. • Unusually large in-plane lattice compression observed for Cr-rich films • Non-uniform misfit dislocation network attributed to Volmer–Weber growth mode • Serves as model system to study interplay between defects and radiation damage

  20. Animation of natural scene by virtual eye-movements evokes high precision and low noise in V1 neurons

    Directory of Open Access Journals (Sweden)

    Yves Frégnac

    2013-12-01

    Full Text Available Synaptic Noise is thought to be a limiting factor for computational efficiency in the Brain. In visual cortex (V1, ongoing activity is present in vivo, and spiking responses to simple stimuli are highly unreliable across trials. Stimulus statistics used to plot receptive fields, however, are quite different from those experienced during natural visuomotor exploration. We recorded V1 neurons intracellularly in the anaesthetized and paralyzed cat and compared their spiking and synaptic responses to full field natural images animated by simulated eye-movements to those evoked by simpler (grating or higher dimensionality statistics (dense noise. In most cells, natural scene animation was the only condition where high temporal precision (in the 10-20 ms range was maintained during sparse and reliable activity. At the subthreshold level, irregular but highly reproducible membrane potential dynamics were observed, even during long (several 100 ms “spike-less” periods. We showed that both the spatial structure of natural scenes and the temporal dynamics of eye-movements increase the signal-to-noise ratio by a non linear amplification of the signal combined with a reduction of the subthreshold contextual noise. These data support the view that the sparsening and the time precision of the neural code in V1 may depend primarily on three factors: 1 broadband input spectrum: the bandwidth must be rich enough for recruiting optimally the diversity of spatial and time constants during recurrent processing; 2 tight temporal interplay of excitation and inhibition: conductance measurements demonstrate that natural scene statistics narrow selectively the duration of the spiking opportunity window during which the balance between excitation and inhibition changes transiently and reversibly; 3 signal energy in the lower frequency band: a minimal level of power is needed below 10 Hz to reach consistently the spiking threshold, a situation rarely reached with

  1. Expression of calcium channel CaV1.3 in cat spinal cord: light and electron microscopic immunohistochemical study

    DEFF Research Database (Denmark)

    Zhang, Mengliang; Møller, Morten; Broman, Jonas;

    2008-01-01

    in the cat spinal cord by light and electron microscopic immunohistochemistry. The results show that Ca(V)1.3-like immunoreactivity is widely distributed in all segments of the spinal cord but that the distribution in the different laminae of the spinal gray matter varies, with the highest density of labeled...... associated with the rough endoplasmic reticulum but some also with the plasma membrane. In dendrites, they were associated with both intracellular organelles, including microtubules and microchondria, and the plasma membrane. These results indicate that significant proportions of the neurons in cat spinal...

  2. Projections to early visual areas V1 and V2 in the calcarine fissure from parietal association areas in the macaque.

    Directory of Open Access Journals (Sweden)

    Elena Borra

    2011-06-01

    Full Text Available Non-extrastriate projections to area V1 in monkeys, now demonstrated by several anatomical studies, are potential substrates of physiologically documented multisensory effects in primary sensory areas. The full network of projections among association and primary areas, however, is likely to be complex and is still only partially understood. In the present report, we used the anterograde tracer biotinylated dextran amine to investigate projections to areas V1 and V2 from subdivisions of the parietal association cortex in macaque. Parietal cortex was chosen to allow comparisons between projections from this higher association area and from other previously reported areas. In addition, we were interested in further elucidating pathways to areas V1 and V2 from parietal areas, as potentially contributing to attention and active vision. Of eight cases, three brains had projections only to area V2, and the five others projected to both areas V1 and V2. Terminations in area V1 were sparse. These were located in supragranular layers I, II, upper III; occasionally in IVB; and in layer VI. Terminations in V2 were denser, and slightly more prevalent in the supragranular layers. For both areas, terminations were in the calcarine region, corresponding to the representation of the peripheral visual field. By reconstructions of single axons, we demonstrated that four of nine axons had collaterals, either to V1 and V2 (n=1 or to area V1 and a ventral area likely to be TEO (n=3. In area V1, axons extended divergently in layer VI as well as layer I. Overall, these and previous results suggest a nested connectivity architecture, consisting of multiple direct and indirect recurrent projections from association areas to area V1. Terminations in area V1 are not abundant, but could be potentiated by the network of indirect connections.

  3. Reactor Physics Programme

    International Nuclear Information System (INIS)

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies

  4. Ship propulsion reactors technology

    International Nuclear Information System (INIS)

    This paper takes the state of the art on ship propulsion reactors technology. The french research programs with the corresponding technological stakes, the reactors specifications and advantages are detailed. (A.L.B.)

  5. Undergraduate reactor control experiment

    International Nuclear Information System (INIS)

    A sequence of reactor and related experiments has been a central element of a senior-level laboratory course at Pennsylvania State University (Penn State) for more than 20 yr. A new experiment has been developed where the students program and operate a computer controller that manipulates the speed of a secondary control rod to regulate TRIGA reactor power. Elementary feedback control theory is introduced to explain the experiment, which emphasizes the nonlinear aspect of reactor control where power level changes are equivalent to a change in control loop gain. Digital control of nuclear reactors has become more visible at Penn State with the replacement of the original analog-based TRIGA reactor control console with a modern computer-based digital control console. Several TRIGA reactor dynamics experiments, which comprise half of the three-credit laboratory course, lead to the control experiment finale: (a) digital simulation, (b) control rod calibration, (c) reactor pulsing, (d) reactivity oscillator, and (e) reactor noise

  6. Process heat reactors

    International Nuclear Information System (INIS)

    The consumption of heat, for industrial and domestic needs, takes up half of the national energy supply; direct utilization of the heat produced by nuclear reactors could therefore contribute to reduce the deficit in the energetic results. The restraints proper to heat consumption (dispersal and variety of consumers, irregular demand) involve the development of the heat transport system structures and adequate nuclear reactors. With this in view, the Commissariat a l'Energie Atomique and Technicatome are developing the CAS reactor series, pressurized water reactors (PWR), (CAS 3G reactor with a power of 420 MW.th.), and the Thermos reactor (100 MW.th.), directly conceived to produce heat at 1200C and whose technology derives from the experimental pool reactors type. In order to prove the value of the Thermos design, an experimental reactor should soon be constructed in the Saclay nuclear research centre

  7. Reactor System Design

    International Nuclear Information System (INIS)

    SMART NPP(Nuclear Power Plant) has been developed for duel purpose, electricity generation and energy supply for seawater desalination. The objective of this project IS to design the reactor system of SMART pilot plant(SMART-P) which will be built and operated for the integrated technology verification of SMART. SMART-P is an integral reactor in which primary components of reactor coolant system are enclosed in single pressure vessel without connecting pipes. The major components installed within a vessel includes a core, twelve steam generator cassettes, a low-temperature self pressurizer, twelve control rod drives, and two main coolant pumps. SMART-P reactor system design was categorized to the reactor coe design, fluid system design, reactor mechanical design, major component design and MMIS design. Reactor safety -analysis and performance analysis were performed for developed SMART=P reactor system. Also, the preparation of safety analysis report, and the technical support for licensing acquisition are performed

  8. Nuclear Reactor RA Safety Report, Vol. 11, Reactor operation

    International Nuclear Information System (INIS)

    This volume includes the following chapters describing: Organisation of reactor operation (including operational safety, fuel management, and regulatory rules for RA reactor operation); Control and maintenance of reactor components (reactor core, nuclear fuel, heavy water and cover gas systems, mechanical structures, electric power supply system, reactor instrumentation); Quality assurance and Training of the reactor personnel

  9. Corrosion at Nuclear Power Plant from Mössbauer Spectroscopy Point of View

    Science.gov (United States)

    Slugeň, V.; Lipka, J.; Dekan, J.; Tóth, I.; Smieško, I.

    2010-07-01

    Steam generators of four VVER-440 units at nuclear power plants V-1 and V-2 in Jaslovske Bohunice (Slovakia) were gradually changed by new original "Bohunice" design in the 1994-1998 period. Corrosion processes before and after these design and material changes in Bohunice secondary circuit were studied using Mössbauer spectroscopy during the last 25 years. Innovations in the feed water pipeline design as well as material composition improvements were evaluated positively. Mössbauer spectroscopy studies of phase composition of corrosion products were performed on real specimens scrapped from water pipelines or in the form of filters deposits. The corrosion of new feed water pipelines system (from austenitic steel) in combination to innovated operation regimes goes dominantly to magnetite. The hematite presence is mostly on the internal surface of steam generator body and its concentration increases towards the top of the body. In the results interpretation it is necessary to consider also erosion as well as scope and type of maintenance activities. The long-term study of phase composition of corrosion products at VVER reactors is one of precondition for the safe operation over the projected NPP lifetime. Keywords: Enter Keywords here. Text should remain 10-pt.

  10. The Chernobylsk reactor accident

    International Nuclear Information System (INIS)

    The construction, the safety philosophy, the major reactor physical parameters of RBMK-1000 type reactor units and the detailed description of the Chernobylsk-4 reactor accident, its causes and conclusions, the efforts to reduce the consequences on the reactor site and in the surroundings are discussed based on different types of Soviet documents including the report presented to the IAEA by the Soviet Atomic Energy Agency in August 1986. (V.N.)

  11. Zero energy reactor 'RB'

    International Nuclear Information System (INIS)

    In 1958 the zero energy reactor RB was built with the purpose of enabling critical experiments with various reactor systems to be carried out. The first core assembly built in this reactor consists of heavy water as moderator and natural uranium metal as fuel. In order to be able to obtain very accurate results when measuring the main characteristics of the assembly the reactor was built as a completely bare system. (author)

  12. Characterization of the honeybee AmNaV1 channel and tools to assess the toxicity of insecticides.

    Science.gov (United States)

    Gosselin-Badaroudine, Pascal; Moreau, Adrien; Delemotte, Lucie; Cens, Thierry; Collet, Claude; Rousset, Matthieu; Charnet, Pierre; Klein, Michael L; Chahine, Mohamed

    2015-01-01

    Pollination is important for both agriculture and biodiversity. For a significant number of plants, this process is highly, and sometimes exclusively, dependent on the pollination activity of honeybees. The large numbers of honeybee colony losses reported in recent years have been attributed to colony collapse disorder. Various hypotheses, including pesticide overuse, have been suggested to explain the disorder. Using the Xenopus oocytes expression system and two microelectrode voltage-clamp, we report the functional expression and the molecular, biophysical, and pharmacological characterization of the western honeybee's sodium channel (Apis Mellifera NaV1). The NaV1 channel is the primary target for pyrethroid insecticides in insect pests. We further report that the honeybee's channel is also sensitive to permethrin and fenvalerate, respectively type I and type II pyrethroid insecticides. Molecular docking of these insecticides revealed a binding site that is similar to sites previously identified in other insects. We describe in vitro and in silico tools that can be used to test chemical compounds. Our findings could be used to assess the risks that current and next generation pesticides pose to honeybee populations. PMID:26202396

  13. Structural basis for diverse N-glycan recognition by HIV-1-neutralizing V1-V2-directed antibody PG16

    Energy Technology Data Exchange (ETDEWEB)

    Pancera, Marie; Shahzad-ul-Hussan, Syed; Doria-Rose, Nicole A.; McLellan, Jason S.; Bailer, Robert T.; Dai, Kaifan; Loesgen, Sandra; Louder, Mark K.; Staupe, Ryan P.; Yang, Yongping; Zhang, Baoshan; Parks, Robert; Eudailey, Joshua; Lloyd, Krissey E.; Blinn, Julie; Alam, S. Munir; Haynes, Barton F.; Amin, Mohammed N.; Wang, Lai-Xi; Burton, Dennis R.; Koff, Wayne C.; Nabel, Gary J.; Mascola, John R.; Bewley, Carole A; Kwong, Peter D. [NIH; (Scripps); (Duke); (Maryland-MED); (IAVI)

    2013-08-05

    HIV-1 uses a diverse N-linked-glycan shield to evade recognition by antibody. Select human antibodies, such as the clonally related PG9 and PG16, recognize glycopeptide epitopes in the HIV-1 V1–V2 region and penetrate this shield, but their ability to accommodate diverse glycans is unclear. Here we report the structure of antibody PG16 bound to a scaffolded V1–V2, showing an epitope comprising both high mannose–type and complex-type N-linked glycans. We combined structure, NMR and mutagenesis analyses to characterize glycan recognition by PG9 and PG16. Three PG16-specific residues, arginine, serine and histidine (RSH), were critical for binding sialic acid on complex-type glycans, and introduction of these residues into PG9 produced a chimeric antibody with enhanced HIV-1 neutralization. Although HIV-1–glycan diversity facilitates evasion, antibody somatic diversity can overcome this and can provide clues to guide the design of modified antibodies with enhanced neutralization.

  14. Informational constraints on interceptive actions of elite football goalkeepers in 1v1 dyads during competitive performance.

    Science.gov (United States)

    Shafizadeh, Mohsen; Davids, Keith; Correia, Vanda; Wheat, Jonathan; Hizan, Hazuan

    2016-09-01

    The aim of this study was to examine whether perceptual variables can provide informational constraints for the goalkeepers to intercept the ball successfully in 1v1 dyads. Video images of 42 actions (1v1 in direct shots) were selected randomly from different matches and divided into conceded goals (n = 20) and saved actions (n = 22) to investigate interceptive actions of 20 goalkeepers in the English Premier League in season 2013-2014. Time to Contact (TTC) of the closing distance gap between shooter and goalkeeper was obtained by digitising actions in the 18-yard penalty box. Statistical analyses revealed that, in sequences of play resulting in an intercepted shot at goal, goalkeepers closed down outfield players in the X axis, whereas when a goal was conceded, there was a significantly delayed movement by goalkeepers toward the shooters in this plane. The results of canonical correlations showed that a decreasing distance between a shooter and goalkeeper, and accompanied reduction in relative interpersonal velocity followed a temporal pattern. Findings of this study showed how perception of key informational constraints on dyadic system relations, such as TTC, interpersonal distance and relative velocity, constrain elite goalkeepers' interceptive actions, playing an important role in successful performance. PMID:26652039

  15. Dependence of chromatic responses in V1 on visual field eccentricity and spatial frequency: an fMRI study.

    Science.gov (United States)

    D'Souza, Dany V; Auer, Tibor; Frahm, Jens; Strasburger, Hans; Lee, Barry B

    2016-03-01

    Psychophysical sensitivity to red-green chromatic modulation decreases with visual eccentricity, compared to sensitivity to luminance modulation, even after appropriate stimulus scaling. This is likely to occur at a central, rather than a retinal, site. Blood-oxygenation-level-dependent (BOLD) functional magnetic resonance imaging (fMRI) responses to stimuli designed to separately stimulate different afferent channels' [red-green, luminance, and short-wavelength (S)-cone] circular gratings were recorded as a function of visual eccentricity (±10  deg) and spatial frequency (SF) in human primary visual cortex (V1) and further visual areas (V2v, V3v). In V1, the SF tuning of BOLD fMRI responses became coarser with eccentricity. For red-green and luminance gratings, similar SF tuning curves were found at all eccentricities. The pattern for S-cone modulation differed, with SF tuning changing more slowly with eccentricity than for the other two modalities. This may be due to the different retinal distribution with eccentricity of this receptor type. A similar pattern held in V2v and V3v. This would suggest that transformation or spatial filtering of the chromatic (red-green) signal occurs beyond these areas. PMID:26974942

  16. High solids fermentation reactor

    Science.gov (United States)

    Wyman, Charles E.; Grohmann, Karel; Himmel, Michael E.; Richard, Christopher J.

    1993-01-01

    A fermentation reactor and method for fermentation of materials having greater than about 10% solids. The reactor includes a rotatable shaft along the central axis, the shaft including rods extending outwardly to mix the materials. The reactor and method are useful for anaerobic digestion of municipal solid wastes to produce methane, for production of commodity chemicals from organic materials, and for microbial fermentation processes.

  17. Fossil nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Maurette, M.

    1976-01-01

    The discussion of fossil nuclear reactors (the Oklo phenomenon) covers the earth science background, neutron-induced isotopes and reactor operating conditions, radiation-damage studies, and reactor modeling. In conclusion possible future studies are suggested and the significance of the data obtained in past studies is summarized. (JSR)

  18. Fusion reactor studies

    International Nuclear Information System (INIS)

    A review is given of fusion reactor systems studies, the objectives of these studies are outlined and some recent conceptual reactor designs are described. The need for further studies in greater depth is indicated so that progress towards a commercial fusion reactor may be consolidated. (U.K.)

  19. Reactor power measuring device

    International Nuclear Information System (INIS)

    The present invention provides a self-powered long detector having a sensitivity over the entire length of a reactor core as an entire control rod withdrawal range of a BWR type reactor, and a reactor power measuring device using a gamma ray thermometer which scarcely causes sensitivity degradation. That is, a hollow protection pipe is disposed passing through the reactor core from the outside of a reactor pressure vessel. The self-powered long detectors and the gamma ray thermometers are inserted and installed in the protection pipe. An average reactor power in an axial direction of the reactor relative to a certain position in the horizontal cross section of the reactor core is determined based on the power of the self-powered long detector over the entire length of the reactor core. Since the response of the self-powered detector relative to a local power change is rapid, the output is used as an input signal to a safety protection device of the reactor core. Further, a gamma ray thermometer secured in the reactor and having scarce sensitivity degradation is used instead of an incore travelling neutron monitor used for relative calibration of an existent neutron monitor secured in the reactor. (I.S.)

  20. Molecular characterization of recombinant T1, a non-allergenic periwinkle (Catharanthus roseus) protein, with sequence similarity to the Bet v 1 plant allergen family.

    Science.gov (United States)

    Laffer, Sylvia; Hamdi, Said; Lupinek, Christian; Sperr, Wolfgang R; Valent, Peter; Verdino, Petra; Keller, Walter; Grote, Monika; Hoffmann-Sommergruber, Karin; Scheiner, Otto; Kraft, Dietrich; Rideau, Marc; Valenta, Rudolf

    2003-01-01

    More than 25% of the population suffer from Type I allergy, an IgE-mediated hypersensitivity disease. Allergens with homology to the major birch ( Betula verrucosa ) pollen allergen, Bet v 1, belong to the most potent elicitors of IgE-mediated allergies. T1, a cytokinin-inducible cytoplasmic periwinkle ( Catharanthus roseus ) protein, with significant sequence similarity to members of the Bet v 1 plant allergen family, was expressed in Escherichia coli. Recombinant T1 (rT1) did not react with IgE antibodies from allergic patients, and failed to induce basophil histamine release and immediate-type skin reactions in Bet v 1-allergic patients. Antibodies raised against purified rT1 could be used for in situ localization of natural T1 by immunogold electron microscopy, but did not cross-react with most of the Bet v 1-related allergens. CD analysis showed significant differences regarding secondary structure and thermal denaturation behaviour between rT1 and recombinant Bet v 1, suggesting that these structural differences are responsible for the different allergenicity of the proteins. T1 represents a non-allergenic member of the Bet v 1 family that may be used to study structural requirements of allergenicity and to engineer hypo-allergenic plants by replacing Bet v 1-related allergens for primary prevention of allergy. PMID:12656672

  1. Analysis of epitope-specific immune responses induced by vaccination with structurally folded and unfolded recombinant Bet v 1 allergen derivatives in man.

    Science.gov (United States)

    Pree, Ines; Reisinger, Jürgen; Focke, Margit; Vrtala, Susanne; Pauli, Gabrielle; van Hage, Marianne; Cromwell, Oliver; Gadermaier, Elisabeth; Egger, Cornelia; Reider, Norbert; Horak, Friedrich; Valenta, Rudolf; Niederberger, Verena

    2007-10-15

    Previously, we have constructed recombinant derivatives of the major birch pollen allergen, Bet v 1, with a more than 100-fold reduced ability to induce IgE-mediated allergic reactions. These derivatives differed from each other because the two recombinant Bet v 1 fragments represented unfolded molecules whereas the recombinant trimer resembled most of the structural fold of the Bet v 1 allergen. In this study, we analyzed the Ab (IgE, IgG subclass, IgA, IgM) response to Bet v 1, recombinant and synthetic Bet v 1-derived peptides in birch pollen allergic patients who had been vaccinated with the derivatives or adjuvant alone. Furthermore, we studied the induction of IgE-mediated skin responses in these patients using Bet v 1 and Bet v 1 fragments. Both types of vaccines induced a comparable IgG1 and IgG4 response against new sequential epitopes which overlap with the conformational IgE epitopes of Bet v 1. This response was 4- to 5-fold higher than that induced by immunotherapy with birch pollen extract. Trimer more than fragments induced also IgE responses against new epitopes and a transient increase in skin sensitivity to the fragments at the beginning of therapy. However, skin reactions to Bet v 1 tended to decrease one year after treatment in both actively treated groups. We demonstrate that vaccination with folded and unfolded recombinant allergen derivatives induces IgG Abs against new epitopes. These data may be important for the development of therapeutic as well as prophylactic vaccines based on recombinant allergens. PMID:17911617

  2. Mapping the conformational epitope of a neutralizing antibody (AcV1) directed against the AcMNPV GP64 protein

    International Nuclear Information System (INIS)

    The envelope glycoprotein GP64 of Autographa californica nucleopolyhedrovirus (AcMNPV) is necessary and sufficient for the acid-induced membrane fusion activity that is required for fusion of the budded virus (BV) envelope and the endosome membrane during virus entry. Infectivity of the budded virus (BV) is neutralized by AcV1, a monoclonal antibody (MAb) directed against GP64. Prior studies indicated that AcV1 recognizes a conformational epitope and does not inhibit virus attachment to the cell, but instead inhibits entry at a step following virus attachment. We found that AcV1 recognition of GP64 was lost upon exposure of GP64 to low pH (pH 4.5) and restored by returning GP64 to pH 6.2. In addition, the AcV1 epitope was lost upon denaturation of GP64 in SDS, but the AcV1 epitope was restored by refolding the protein in the absence of SDS. Using truncated GP64 proteins expressed in insect cells, we mapped the AcV1 epitope to a 24 amino acid region in the central variable domain of GP64. When sequences within the mapped AcV1 epitope were substituted with a c-Myc epitope and the resulting construct was used to replace wt GP64 in recombinant AcMNPV viruses, the modified GP64 protein appeared to function normally. However, an anti-c-Myc monoclonal antibody did not neutralize infectivity of those viruses. Because binding of the c-Myc MAb to the same site in the GP64 sequence did not result in neutralization, these studies suggest that AcV1 neutralization may result from a specific structural constraint caused by AcV1 binding and not simply by steric hindrance caused by antibody binding at this position in GP64

  3. SCORPIO-VVER Core Monitoring and Surveillance System for VVER-440 Reactors

    International Nuclear Information System (INIS)

    The SCORPIO-VVER core monitoring system has proved since the first installation at Dukovany NPP in 1999 to be a valuable tool for the reactor operators and reactor physicists. It is now installed on four units of Dukovany NPP (EDU, Czech Republic) and two units of Bohunice NPP (EBO, Slovak Republic) replacing the original Russian VK3 system. By both Czech and Slovak nuclear regulatory bodies it was licensed as a Technical Specification Surveillance tool. The monitoring system operates in two modes: in core follow mode and in predictive mode. In the core follow mode, the present core state is evaluated by a method combining the instrumentation signals and the theoretical calculation of the power distribution done by the core simulator. This procedure is followed by an automatic limit checking, where characteristics of the current state are compared to the Technical Specifications. The operator obtains relevant information on core status through the dedicated Man-Machine Interfaces. In the predictive mode, the operator can visualize the core characteristics during the transients forecasted for coming hours or days. Quick forecasts realized by the strategy generator are deeply analyzed by the predictive simulator. Similarly as in the core follow mode, characteristics of the evaluated states can be compared against Technical Specifications. Since it's first installation, the development of SCORPIO-VVER system continues along with the changes in WWER reactors operation. The system is being adapted according the utility needs and several notable improvements in physical modules of the system were introduced. The latest most significant changes were done in connection with implementation of a new digital I and C system, loading of the optimized Gd2 fuel assemblies, improvements in the area of core design (neutron physics, core thermal hydraulics and fuel thermal mechanics) and improvements in the predictive part of the system (Strategy Generator). The currently finished

  4. Alcohol Withdrawal-Induced Seizure Susceptibility is Associated with an Upregulation of CaV1.3 Channels in the Rat Inferior Colliculus

    Science.gov (United States)

    Akinfiresoye, Luli R.; Allard, Joanne S.; Lovinger, David M.

    2015-01-01

    Background: We previously reported increased current density through L-type voltage-gated Ca2+ (CaV1) channels in inferior colliculus (IC) neurons during alcohol withdrawal. However, the molecular correlate of this increased CaV1 current is currently unknown. Methods: Rats received three daily doses of ethanol every 8 hours for 4 consecutive days; control rats received vehicle. The IC was dissected at various time intervals following alcohol withdrawal, and the mRNA and protein levels of the CaV1.3 and CaV1.2 α1 subunits were measured. In separate experiments, rats were tested for their susceptibility to alcohol withdrawal–induced seizures (AWS) 3, 24, and 48 hours after alcohol withdrawal. Results: In the alcohol-treated group, AWS were observed 24 hours after withdrawal; no seizures were observed at 3 or 48 hours. No seizures were observed at any time in the control-treated rats. Compared to control-treated rats, the mRNA level of the CaV1.3 α1 subunit was increased 1.4-fold, 1.9-fold, and 1.3-fold at 3, 24, and 48 hours, respectively. In contrast, the mRNA level of the CaV1.2 α1 subunit increased 1.5-fold and 1.4-fold at 24 and 48 hours, respectively. At 24 hours, Western blot analyses revealed that the levels of the CaV1.3 and CaV1.2 α1 subunits increased by 52% and 32%, respectively, 24 hours after alcohol withdrawal. In contrast, the CaV1.2 and CaV1.3 α1 subunits were not altered at either 3 or 48 hours during alcohol withdrawal. Conclusions: Expression of the CaV1.3 α1 subunit increased in parallel with AWS development, suggesting that altered L-type CaV1.3 channel expression is an important feature of AWS pathogenesis. PMID:25556199

  5. Light water reactor safety

    CERN Document Server

    Pershagen, B

    2013-01-01

    This book describes the principles and practices of reactor safety as applied to the design, regulation and operation of light water reactors, combining a historical approach with an up-to-date account of the safety, technology and operating experience of both pressurized water reactors and boiling water reactors. The introductory chapters set out the basic facts upon which the safety of light water reactors depend. The central section is devoted to the methods and results of safety analysis. The accidents at Three Mile Island and Chernobyl are reviewed and their implications for light wate

  6. Nuclear reactor repairing device

    International Nuclear Information System (INIS)

    Purpose: To enable free repairing of an arbitrary position in an LMFBR reactor. Constitution: A laser light emitted from a laser oscillator installed out of a nuclear reactor is guided into a portion to be repaired in the reactor by using a reflecting mirror, thereby welding or cutting it. The guidance of the laser out of the reactor into the reactor is performed by an extension tube depending into a through hole of a rotary plug, and the guidance of the laser light into a portion to be repaired is performed by the transmitting and condensing action of the reflecting mirror. (Kamimura, M.)

  7. Fundamentals of reactor chemistry

    International Nuclear Information System (INIS)

    In the Nuclear Engineering School of JAERI, many courses are presented for the people working in and around the nuclear reactors. The curricula of the courses contain also the subject material of chemistry. With reference to the foreign curricula, a plan of educational subject material of chemistry in the Nuclear Engineering School of JAERI was considered, and the fundamental part of reactor chemistry was reviewed in this report. Since the students of the Nuclear Engineering School are not chemists, the knowledge necessary in and around the nuclear reactors was emphasized in order to familiarize the students with the reactor chemistry. The teaching experience of the fundamentals of reactor chemistry is also given. (author)

  8. Nuclear reactor physics

    CERN Document Server

    Stacey, Weston M

    2010-01-01

    Nuclear reactor physics is the core discipline of nuclear engineering. Nuclear reactors now account for a significant portion of the electrical power generated worldwide, and new power reactors with improved fuel cycles are being developed. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. The second edition of this successful comprehensive textbook and reference on basic and advanced nuclear reactor physics has been completely updated, revised and enlarged to include the latest developme

  9. Generation III+ Reactor Portfolio

    International Nuclear Information System (INIS)

    While the power generation needs of utilities are unique and diverse, they are all faced with the double challenge of meeting growing electricity needs while curbing CO2 emissions. To answer these diverse needs and help tackle this challenge, AREVA has developed several reactor models which are briefly described in this document: The EPRTM Reactor: designed on the basis of the Konvoi (Germany) and N4 (France) reactors, the EPRTM reactor is an evolutionary model designed to achieve best-in-class safety and operational performance levels. The ATMEA1TM reactor: jointly designed by Mitsubishi Heavy Industries and AREVA through ATMEA, their common company. This reactor design benefits from the competencies and expertise of the two mother companies, which have commissioned close to 130 reactor units. The KERENATM reactor: Designed on the basis of the most recent German BWR reactors (Gundremmingen) the KERENATM reactor relies on proven technology while also including innovative, yet thoroughly tested, features. The optimal combination of active and passive safety systems for a boiling water reactor achieves a very low probability of severe accident

  10. The Maple reactor project

    International Nuclear Information System (INIS)

    MDS Nordion supplies the majority of the world's reactor-produced medical isotopes. These isotopes are currently produced in the NRU reactor at AECL's Chalk River Laboratories (CRL). Medical isotopes and related technology are relied upon around the world to prevent, diagnose and treat disease. The NRU reactor, which has played a key role in supplying medical isotopes to date, has been in operation for over 40 years. Replacing this aging reactor has been a priority for MDS Nordion to assure the global nuclear medicine community that Canada will continue to be a dependable supplier of medical isotopes. MDS Nordion contracted AECL to construct two MAPLE reactors dedicated to the production of medical isotopes. The MDS Nordion Medical Isotope Reactor (MMIR) project started in September 1996. This paper describes the MAPLE reactors that AECL has built at its CRL site, and will operate for MDS Nordion. (author)

  11. High temperature reactors

    International Nuclear Information System (INIS)

    With the advent of high temperature reactors, nuclear energy, in addition to producing electricity, has shown enormous potential for the production of alternate transport energy carrier such as hydrogen. High efficiency hydrogen production processes need process heat at temperatures around 1173-1223 K. Bhabha Atomic Research Centre (BARC), is currently developing concepts of high temperature reactors capable of supplying process heat around 1273 K. These reactors would provide energy to facilitate combined production of hydrogen, electricity, and drinking water. Compact high temperature reactor is being developed as a technology demonstrator for associated technologies. Design has been also initiated for a 600 MWth innovative high temperature reactor. High temperature reactor development programme has opened new avenues for research in areas like advanced nuclear fuels, high temperature and corrosion resistant materials and protective coatings, heavy liquid metal coolant technologies, etc. The paper highlights design of these reactors and their material related requirements

  12. Spinning fluids reactor

    Science.gov (United States)

    Miller, Jan D; Hupka, Jan; Aranowski, Robert

    2012-11-20

    A spinning fluids reactor, includes a reactor body (24) having a circular cross-section and a fluid contactor screen (26) within the reactor body (24). The fluid contactor screen (26) having a plurality of apertures and a circular cross-section concentric with the reactor body (24) for a length thus forming an inner volume (28) bound by the fluid contactor screen (26) and an outer volume (30) bound by the reactor body (24) and the fluid contactor screen (26). A primary inlet (20) can be operatively connected to the reactor body (24) and can be configured to produce flow-through first spinning flow of a first fluid within the inner volume (28). A secondary inlet (22) can similarly be operatively connected to the reactor body (24) and can be configured to produce a second flow of a second fluid within the outer volume (30) which is optionally spinning.

  13. Green syntheses, v.1

    CERN Document Server

    Tundo, Pietro

    2014-01-01

    Introduction to the Green Syntheses SeriesPietro Tundo and John AndraosApplication of Material Efficiency Metrics to Assess Reaction Greenness-Illustrative Case Studies from Organic SynthesesJohn AndraosReaction 1: Synthesis of 3-Benzyl-5-Methyleneoxazolidin-2-one from N-Benzylprop-2-yn-1-Amine and CO2Qing-Wen Song and Liang-Nian HeReaction 2: Synthesis of the 5-Membered Cyclic Carbonates from Epoxides and CO2Qing-Wen Song, Liang-Nian HePart I: Green Methods for the Epoxidation of

  14. Singularity v1.x

    Energy Technology Data Exchange (ETDEWEB)

    2016-04-12

    Singularity is a container solution designed to facilitate mobility of compute across systems and HPC infrastructures. It does this by creating minimal containers that are defined by a specfile and files from the host system are used to build the container. The resulting container can then be launched by any Linux computer with Singularity installed regardless if the programs inside the container are present on the target system, or if they are a different version, or even incompatible versions. Singularity achieves extreme portability without sacrificing usability thus solving the need of mobility of compute. Singularity containers can be executed within a normal/standard command line process flow.

  15. AFA's annals. V. 1

    International Nuclear Information System (INIS)

    The meeting of the Argentine Physics Association (AFA) held in 1989 is intended to expose the scientific works of its associates as well as of specially invited scientists. It also aims to diffuse the advances of physical science and its applications in the Argentine scientific community. The papers included in this work are representative of physical research in the country. The subjects of research were: mathematical methods in physics; classical and quantum physics, mechanics and fields; statistical physics and thermodynamics; nuclear physics; atomic physics, elementary particles and fields; optics and optical spectroscopy; fluid dynamics; plasma physics and electric discharges; condensed matter; applied physics: instruments, physical chemistry, biophysics, medical physics and biomedical engineering

  16. Reactor Safety: Introduction

    International Nuclear Information System (INIS)

    The programme of the Reactor Safety Division focuses on the development of expertise on materials behaviour under irradiation for fission and fusion oriented applications. Furthermore, as nuclear energy needs international public acceptance with respect to safety and efficient management of natural resources and wants to reduce the burden of nuclear waste, the Reactor Safety Division enhanced its efforts to develop the MYRRHA project. MYRRHA, an accelerator driven sub-critical system, might have the potential to cope in Europe with the above mentioned constraints on acceptability and might serve as a technological platform for GEN IV reactor development, in particular the Liquid Metal Fast Reactor.The Reactor Safety Division gathers three research entities that are internationally recognised: the Reactor Materials Research department, the Reactor Physics and MYRRHA department and the Instrumentation department.The objectives of Reactor Materials Research are: to evaluate the integrity and behaviour of structural materials and nuclear fuels used in present and future nuclear power industry; to perform research to unravel and understand the parameters that determine the material and fuel behaviour under or after irradiation; to contribute to the interpretation and modelling of the materials and fuels behaviour in order to develop and assess strategies for optimum life management of nuclear power plant components. The programmes within the Reactor Materials Research department concentrate on four distinct disciplines: Reactor Pressure Vessel Steel embrittlement Stress corrosion cracking in reactor coolant environment, including Irradiation Assisted Stress Corrosion Cracking; Nuclear Fuel characterisation and development of new fuel types for commercial and test reactors. Development of materials for Fusion and advanced nuclear fission reactors. The safe operation of present nuclear power plants relies primarily on the integrity of the reactor pressure vessel

  17. Nondispersive hole transport in a polyfluorene copolymer with a mobility of 0.01 cm2 V-1 s-1

    Science.gov (United States)

    Fong, H. H.; Papadimitratos, Alexios; Malliaras, George G.

    2006-10-01

    The hole mobility in the fluorene copolymer poly[(9,9-dioctylfluorenyl-2,7-diyl)-co-(4,4'-(N-(4-sec-butylphenyl)) diphenylamine)] (TFB) was measured using the time-of-flight technique. Transport was found to be nondispersive throughout the temperature range between 220 and 350K, indicating the absence of intrinsic traps in this material. At room temperature, TFB shows a hole mobility of 0.01cm2V-1s-1, with a weak field dependence. The hole mobility is independent of sample thickness in the range between 0.9 and 6.4μm. These results are in agreement with a narrow transport manifold, with a width of 65.9±0.5meV.

  18. Electrical and magnetic properties of (BiNa)1/2(FeV)1/2O3

    Indian Academy of Sciences (India)

    S K Bera; Subrat K Barik; R N P Choudhary; P K Bajpai

    2012-02-01

    Potential multiferroic material, (BiNa)1/2(FeV)1/2O3, synthesized using solid-state route is investigated. The phase formation was confirmed by X-ray diffraction and surface morphology by scanning electron microscopy (SEM). Structural data reveal the single phase formation corroborated by SEM. The grain distribution is uniform with an average grain size of 3.6 m. Electrical properties were investigated in a frequency range (1 kHz–1 MHz) by complex impedance spectroscopy (CIS) technique. The material showed negative temperature coefficient of resistance (NTCR) reflecting semiconductor behaviour. A.C. conductivity was found to obey Johnscher’s law. Conductivity mechanism is discussed and activation energy estimated (1.17 eV) for the conduction process is associated with Fe3+ → Fe2+ variable state. The M–H curve showed the presence of ferromagnetism in the studied material.

  19. Contribution of the experimental validation of the French criticality-safety package 'CRISTAL V1' : APOLLO2 SN route

    International Nuclear Information System (INIS)

    Since 1995, the Commissariat a l'Energie Atomique (CEA) and the Institut de Radioprotection et de Surete Nucleaire (IRSN) in collaboration with the AREVA/COGEMA Company have been developing a criticality-safety package called CRISTAL''. The CRISTAL system involves the newest accurate French codes, APOLLO2, MORET4 and TRIPOLI4 and uses the JEF2.2 European File. The experimental validation of the V0 version of CRISTAL has revealed some insufficiencies and some parts need to be added. For version V1, the existing calculation schemes were improved and new ones were conceived. These recommended design calculation routes were checked by reference code calculations. Then, they were validated against specific criticality experiments. (author)

  20. Cross-correlation trajectory study of vibrational relaxation of HF (v=1--7) by HF (v=0)

    International Nuclear Information System (INIS)

    Results are presented for a three-dimensional quasiclassical trajectory study of the vibrational deactivation of vibrationally excited HF (v=1--7) by ground vibrational HF. A cross-correlation method of analysis is used to calculate probabilities and rate constants for V--V and V--RT transitions using trajectory results. Comparisons are made of calculated total deactivation rate constants (V--V plus V--RT) with experimental values. The V--RT dominates the relaxation for higher v states, and increases particularly rapidly with increasing v. Comparisons are made with recent classical-path calculations for this system, and in the use of Morse versus equivalent harmonic oscillator potentials

  1. Evaluation of control rod motion simulator research reactors

    International Nuclear Information System (INIS)

    Motion simulator has been carried out testing of the reactor control rod using a servomotor. Reactor control rod motion at any point should be in the right position, one of the motors that can move in a precise and correct the servo motor. To ensure that the servo motor to move in accordance with the desired program, then the servomotor function test for motor work to ensure the performance of the appliance. Tests carried out on meshes stress disorder, the load is stable within a certain period and travel time safety control rod up and down, travel time regulating control rods up and down and travel time compensation control rods up and down. In testing the breakdown voltage Vout nets at 24 V, 6.5 A with 12 Ω load deviation obtained V0 = V1 = 0.1% and 0.65% and for the stability of the load in a certain time deviation V = 0.7125%, next to the breakdown voltage Vout nets at 12V, 4.2 A with a 6 Ω load deviation obtained V0 = V1 = 0.275% and 1.158% for the stability of the load in a certain time deviation V = 1.463% and the net-voltage noise nets on Vout 24 V, 4.5 A with 12 Ω load deviation obtained V0 = V1 = 0.196% and 0.496% and for the stability of the load in a certain time deviation V = 0.3625%. While the travel time of a safety control rod up and down, up and down the regulator and compensation rise and fall showed a steady linear graph. The results show that the performance of the servo motor is very stable with the working area below the tolerance limit, it is 5% - 10%. (author)

  2. An evaluation of control rod motion simulator of research reactor

    International Nuclear Information System (INIS)

    Motion simulator for rod control research reactor has been carried out using a servo motor. Reactor rod motion control at any point should be in the right position, one of the motors that can move in a precise and correct is the servo motor. To ensure that the servo motor to move in accordance with the desired program, then the servo motor function test should be carried out to ensure having good performance. Tests carried out on meshes stress disorder, the load is stable within a certain period and travel time safety control rod up and down, travel time regulating control rods up and down and travel time compensation control rods up and down. In testing the breakdown voltage V out nets at 24 V, 6.5 A with 12 Q load deviation obtained V0= V1 = 0.1% and 0.65% and for the stability of the load in a certain time deviation V = 0.7125% , next to the breakdown voltage V out nets at 12 V, 4.2 A with a 6 Q load deviation obtained V0= V1 = 0.275% and 1.158% for the stability of the load in a certain time deviation V = 1.463% and the net-voltage noise nets on V out 24 V, 4.5 A with 12 Q load deviation obtained V0 = V1 = 0.196% and 0.496% and for the stability of the load in a certain time deviation V = 0.3625%. While the travel time of a safety control rod up and down, up and down the regulator and compensation rise and fall showed a steady linear graph. The results show that the performance of the servo motor is very stable with the working area below the tolerance limit, it is 5% - 10%.(author)

  3. Dynamic causal modelling of eye movements during pursuit: Confirming precision-encoding in V1 using MEG.

    Science.gov (United States)

    Adams, Rick A; Bauer, Markus; Pinotsis, Dimitris; Friston, Karl J

    2016-05-15

    This paper shows that it is possible to estimate the subjective precision (inverse variance) of Bayesian beliefs during oculomotor pursuit. Subjects viewed a sinusoidal target, with or without random fluctuations in its motion. Eye trajectories and magnetoencephalographic (MEG) data were recorded concurrently. The target was periodically occluded, such that its reappearance caused a visual evoked response field (ERF). Dynamic causal modelling (DCM) was used to fit models of eye trajectories and the ERFs. The DCM for pursuit was based on predictive coding and active inference, and predicts subjects' eye movements based on their (subjective) Bayesian beliefs about target (and eye) motion. The precisions of these hierarchical beliefs can be inferred from behavioural (pursuit) data. The DCM for MEG data used an established biophysical model of neuronal activity that includes parameters for the gain of superficial pyramidal cells, which is thought to encode precision at the neuronal level. Previous studies (using DCM of pursuit data) suggest that noisy target motion increases subjective precision at the sensory level: i.e., subjects attend more to the target's sensory attributes. We compared (noisy motion-induced) changes in the synaptic gain based on the modelling of MEG data to changes in subjective precision estimated using the pursuit data. We demonstrate that imprecise target motion increases the gain of superficial pyramidal cells in V1 (across subjects). Furthermore, increases in sensory precision - inferred by our behavioural DCM - correlate with the increase in gain in V1, across subjects. This is a step towards a fully integrated model of brain computations, cortical responses and behaviour that may provide a useful clinical tool in conditions like schizophrenia. PMID:26921713

  4. A User's Manual for MASH V1.5 - A Monte Carlo Adjoint Shielding Code System

    Energy Technology Data Exchange (ETDEWEB)

    C. O. Slater; J. M. Barnes; J. O. Johnson; J.D. Drischler

    1998-10-01

    The Monte Carlo ~djoint ~ielding Code System, MASH, calculates neutron and gamma- ray environments and radiation protection factors for armored military vehicles, structures, trenches, and other shielding configurations by coupling a forward discrete ordinates air- over-ground transport calculation with an adjoint Monte Carlo treatment of the shielding geometry. Efficiency and optimum use of computer time are emphasized. The code system includes the GRTUNCL and DORT codes for air-over-ground transport calculations, the MORSE code with the GIFT5 combinatorial geometry package for adjoint shielding calculations, and several peripheral codes that perform the required data preparations, transformations, and coupling functions. The current version, MASH v 1.5, is the successor to the original MASH v 1.0 code system initially developed at Oak Ridge National Laboratory (ORNL). The discrete ordinates calculation determines the fluence on a coupling surface surrounding the shielding geometry due to an external neutron/gamma-ray source. The Monte Carlo calculation determines the effectiveness of the fluence at that surface in causing a response in a detector within the shielding geometry, i.e., the "dose importance" of the coupling surface fluence. A coupling code folds the fluence together with the dose importance, giving the desired dose response. The coupling code can determine the dose response as a function of the shielding geometry orientation relative to the source, distance from the source, and energy response of the detector. This user's manual includes a short description of each code, the input required to execute the code along with some helpful input data notes, and a representative sample problem.

  5. An Internally Consistent Dataset of δ13C-DIC in the North Atlantic Ocean - NAC13v1

    Science.gov (United States)

    Becker, Meike; Andersen, Nils; Erlenkeuser, Helmut; Humphreys, Matthew. P.; Tanhua, Toste; Körtzinger, Arne

    2016-03-01

    The stable carbon isotope composition of dissolved inorganic carbon (δ13C-DIC) can be used to quantify fluxes within the carbon system. For example, knowing the δ13C-DIC signature of the inorganic carbon pool can help to describe the exchange between ocean and atmosphere as well as the amount of anthropogenic carbon in the water column. The measurements can also be used for evaluating modeled carbon fluxes, for making basin wide estimates, studying seasonal and interannual variability or decadal trends in interior ocean biogeochemistry. For all these purposes, it is not only important to have a sufficient amount of data, but these data must also be internally consistent and of high quality. In this study, we present a δ13C-DIC dataset for the North Atlantic, which has undergone secondary quality control. The data originate from oceanographic research cruises between 1981 and 2012. During a primary quality control step based on simple range tests obviously bad data were flagged. In a second quality control step, biases between measurements from different cruises were quantified through a crossover analysis using nearby data of the respective cruises and absolute values of biased cruises were adjusted in the data product. the crossover analysis was possible for 22 of the 29 cruises in our dataset and adjustments were applied to 10 of these. The internal accuracy of this dataset is 0.017 ‰. The dataset is available via CDIAC at http://cdiac.ornl.gov/oceans/ndp_096/NAC13v1.html, doi: 10.3334/CDIAC/OTG.NAC13v1.

  6. Dynamic causal modelling of eye movements during pursuit: Confirming precision-encoding in V1 using MEG

    Science.gov (United States)

    Adams, Rick A.; Bauer, Markus; Pinotsis, Dimitris; Friston, Karl J.

    2016-01-01

    This paper shows that it is possible to estimate the subjective precision (inverse variance) of Bayesian beliefs during oculomotor pursuit. Subjects viewed a sinusoidal target, with or without random fluctuations in its motion. Eye trajectories and magnetoencephalographic (MEG) data were recorded concurrently. The target was periodically occluded, such that its reappearance caused a visual evoked response field (ERF). Dynamic causal modelling (DCM) was used to fit models of eye trajectories and the ERFs. The DCM for pursuit was based on predictive coding and active inference, and predicts subjects' eye movements based on their (subjective) Bayesian beliefs about target (and eye) motion. The precisions of these hierarchical beliefs can be inferred from behavioural (pursuit) data. The DCM for MEG data used an established biophysical model of neuronal activity that includes parameters for the gain of superficial pyramidal cells, which is thought to encode precision at the neuronal level. Previous studies (using DCM of pursuit data) suggest that noisy target motion increases subjective precision at the sensory level: i.e., subjects attend more to the target's sensory attributes. We compared (noisy motion-induced) changes in the synaptic gain based on the modelling of MEG data to changes in subjective precision estimated using the pursuit data. We demonstrate that imprecise target motion increases the gain of superficial pyramidal cells in V1 (across subjects). Furthermore, increases in sensory precision – inferred by our behavioural DCM – correlate with the increase in gain in V1, across subjects. This is a step towards a fully integrated model of brain computations, cortical responses and behaviour that may provide a useful clinical tool in conditions like schizophrenia. PMID:26921713

  7. Cardiac sodium channel Na(v)1.5 interacts with and is regulated by the protein tyrosine phosphatase PTPH1.

    Science.gov (United States)

    Jespersen, Thomas; Gavillet, Bruno; van Bemmelen, Miguel X; Cordonier, Sophie; Thomas, Marc A; Staub, Olivier; Abriel, Hugues

    2006-10-01

    In order to identify proteins interacting with the cardiac voltage-gated sodium channel Na(v)1.5, we used the last 66 amino acids of the C-terminus of the channel as bait to screen a human cardiac cDNA library. We identified the protein tyrosine phosphatase PTPH1 as an interacting protein. Pull-down experiments confirmed the interaction, and indicated that it depends on the PDZ-domain binding motif of Na(v)1.5. Co-expression experiments in HEK293 cells showed that PTPH1 shifts the Na(v)1.5 availability relationship toward hyperpolarized potentials, whereas an inactive PTPH1 or the tyrosine kinase Fyn does the opposite. The results of this study suggest that tyrosine phosphorylation destabilizes the inactivated state of Na(v)1.5. PMID:16930557

  8. Mechanisms of a human skeletal myotonia produced by mutation in the C-terminus of NaV1.4: is Ca2+ regulation defective?

    Directory of Open Access Journals (Sweden)

    Subrata Biswas

    Full Text Available Mutations in the cytoplasmic tail (CT of voltage gated sodium channels cause a spectrum of inherited diseases of cellular excitability, yet to date only one mutation in the CT of the human skeletal muscle voltage gated sodium channel (hNaV1.4F1705I has been linked to cold aggravated myotonia. The functional effects of altered regulation of hNaV1.4F1705I are incompletely understood. The location of the hNaV1.4F1705I in the CT prompted us to examine the role of Ca(2+ and calmodulin (CaM regulation in the manifestations of myotonia. To study Na channel related mechanisms of myotonia we exploited the differences in rat and human NaV1.4 channel regulation by Ca(2+ and CaM. hNaV1.4F1705I inactivation gating is Ca(2+-sensitive compared to wild type hNaV1.4 which is Ca(2+ insensitive and the mutant channel exhibits a depolarizing shift of the V1/2 of inactivation with CaM over expression. In contrast the same mutation in the rNaV1.4 channel background (rNaV1.4F1698I eliminates Ca(2+ sensitivity of gating without affecting the CaM over expression induced hyperpolarizing shift in steady-state inactivation. The differences in the Ca(2+ sensitivity of gating between wild type and mutant human and rat NaV1.4 channels are in part mediated by a divergence in the amino acid sequence in the EF hand like (EFL region of the CT. Thus the composition of the EFL region contributes to the species differences in Ca(2+/CaM regulation of the mutant channels that produce myotonia. The myotonia mutation F1705I slows INa decay in a Ca(2+-sensitive fashion. The combination of the altered voltage dependence and kinetics of INa decay contribute to the myotonic phenotype and may involve the Ca(2+-sensing apparatus in the CT of NaV1.4.

  9. Research reactors in Argentina

    International Nuclear Information System (INIS)

    Argentine Nuclear Development started in early fifties. In 1957, it was decided to built the first a research reactor. RA-1 reactor (120 kw, today licensed to work at 40 kW) started operation in January 1958. Originally RA-1 was an Argonaut (American design) reactor. In early sixties, the RA-1 core was changed. Fuel rods (20% enrichment) was introduced instead the old Argonaut core design. For that reason, a critical facility named RA-0 was built. After that, the RA-3 project started, to build a multipurpose 5 MW nuclear reactor MTR pool type, to produce radioisotopes and research. For that reason and to define the characteristics of the RA-3 core, another critical facility was built, RA-2. Initially RA-3 was a 90 % enriched fuel reactor, and started operation in 1967. When Atucha I NPP project started, a German design Power Reactor, a small homogeneous reactor was donated by the German Government to Argentina (1969). This was RA-4 reactor (20% enrichment, 1W). In 1982, RA-6 pool reactor achieved criticality. This is a 500 kW reactor with 90% enriched MTR fuel elements. In 1990, RA-3 started to operate fueled by 20% enriched fuel. In 1997, the RA-8 (multipurpose critical facility located at Pilcaniyeu) started to operate. RA-3 reactor is the most important CNEA reactor for Argentine Research Reactors development. It is the first in a succession of Argentine MTR reactors built by CNEA (and INVAP SE ) in Argentina and other countries: RA-6 (500 kW, Bariloche-Argentina), RP-10 (10MW, Peru), NUR (500 kW, Algeria), MPR (22 MW, Egypt). The experience of Argentinian industry permits to compete with foreign developed countries as supplier of research reactors. Today, CNEA has six research reactors whose activities have a range from education and promotion of nuclear activity, to radioisotope production. For more than forty years, Argentine Research Reactors are working. The experience of Argentine is important, and argentine firms are able to compete in the design and

  10. Thai research reactor

    International Nuclear Information System (INIS)

    The Office of Atomic Energy for Peace (OAEP) was established in 1962, as a reactor center, by the virtue of the Atomic Energy for Peace Act, under operational policy and authority of the Thai Atomic Energy for Peace Commission (TAEPC); and under administration of Ministry of Science, Technology and Energy. It owns and operates the only Thai Research Reactor (TRR-1/M1). The TRR-1/M1 is a mixed reactor system constituting of the old MTR type swimming pool, irradiation facilities and cooling system; and TRIGA Mark III core and control instrumentation. The general performance of TRR-1/M1 is summarized in Table I. The safe operation of TRR-1/M1 is regulated by Reactor Safety Committee (RSC), established under TAEPC, and Health Physics Group of OAEP. The RCS has responsibility and duty to review of and make recommendations on Reactor Standing Orders, Reactor Operation Procedures, Reactor Core Loading and Requests for Reactor Experiments. In addition,there also exist of Emergency Procedures which is administered by OAEP. The Reactor Operation Procedures constitute of reactor operating procedures, system operating procedures and reactor maintenance procedures. At the level of reactor routine operating procedures, there is a set of Specifications on Safety and Operation Limits and Code of Practice from which reactor shift supervisor and operators must follow in order to assure the safe operation of TRR-1/M1. Table II is the summary of such specifications. The OAEP is now upgrading certain major components of the TRR-1/M1 such as the cooling system, the ventilation system and monitoring equipment to ensure their adequately safe and reliable performance under normal and emergency conditions. Furthermore, the International Atomic Energy Agency has been providing assistance in areas of operation and maintenance and safety analysis. (author)

  11. Nuclear Reactor Physics

    Science.gov (United States)

    Stacey, Weston M.

    2001-02-01

    An authoritative textbook and up-to-date professional's guide to basic and advanced principles and practices Nuclear reactors now account for a significant portion of the electrical power generated worldwide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. Nuclear reactor physics is the core discipline of nuclear engineering, and as the first comprehensive textbook and reference on basic and advanced nuclear reactor physics to appear in a quarter century, this book fills a large gap in the professional literature. Nuclear Reactor Physics is a textbook for students new to the subject, for others who need a basic understanding of how nuclear reactors work, as well as for those who are, or wish to become, specialists in nuclear reactor physics and reactor physics computations. It is also a valuable resource for engineers responsible for the operation of nuclear reactors. Dr. Weston Stacey begins with clear presentations of the basic physical principles, nuclear data, and computational methodology needed to understand both the static and dynamic behaviors of nuclear reactors. This is followed by in-depth discussions of advanced concepts, including extensive treatment of neutron transport computational methods. As an aid to comprehension and quick mastery of computational skills, he provides numerous examples illustrating step-by-step procedures for performing the calculations described and chapter-end problems. Nuclear Reactor Physics is a useful textbook and working reference. It is an excellent self-teaching guide for research scientists, engineers, and technicians involved in industrial, research, and military applications of nuclear reactors, as well as government regulators who wish to increase their understanding of nuclear reactors.

  12. Gemini: A hybrid plasma modelling capability for low pressure systems. User`s manual - V.1.7

    Energy Technology Data Exchange (ETDEWEB)

    Johannes, J.; Bartel, T.; Sears, D.; Payne, J.

    1996-10-01

    Gemini is the coupling of Icarus, the Sandia National Laboratories (SNL) 2-D Direct Simulation Monte Carlo (DMSC) code, to MPRES, the University of Houston 2-D finite element plasma reactor code. Thus, Gemini is not a stand alone code. The primary application of Gemini is the simulation of inductively coupled plasma reactors that operate at low pressures (< 10mtorr) where continuum formulations of the transport equations begin to break down. Plasma parameters (electron density (ne), electron temperature (Te) and electrostatic fields (Er and Ez)) are computed in MPRES and interpolated onto the DSMC grid. This allows transport of the neutrals and ions to be performed using the DSMC method while including electron impact reactions and field transport effects. A sample calculation including appropriate input files is given.

  13. The chain reaction: a golden jubilee commemorative volume on research in basic sciences at DAE Institutions. V. 1

    International Nuclear Information System (INIS)

    This book has been chosen to metaphorically reflect how research in basic sciences in various institutions of the Department of Atomic Energy (DAE) has evolved over the years, closely mimicking what goes on in a nuclear chain reactor. Since, for harnessing atomic energy for peaceful uses, nuclear physics and atomic physics are the two core activities, work was undertaken in these areas during initial days at the Tata Institute of Fundamental Research. These activities then promoted the growth of major programmes in a number of areas, such as, reactor physics, accelerator physics, condensed matter physics and materials science, theoretical physics and mathematical physics, astronomy and astrophysics, laser and plasma physics, radiation chemistry, photochemistry, chemical dynamics, nuclear chemistry, radiation biology and health sciences, molecular and cellular biology, structural biology and biophysics, agriculture and food sciences etc. In turn, all these programmes have been fostering the growth in several other domains of science, engineering and technology

  14. Sustained inhibition of the NaV1.7 sodium channel by engineered dimers of the domain II binding peptide GpTx-1.

    Science.gov (United States)

    Murray, Justin K; Biswas, Kaustav; Holder, J Ryan; Zou, Anruo; Ligutti, Joseph; Liu, Dong; Poppe, Leszek; Andrews, Kristin L; Lin, Fen-Fen; Meng, Shi-Yuan; Moyer, Bryan D; McDonough, Stefan I; Miranda, Les P

    2015-11-01

    Many efforts are underway to develop selective inhibitors of the voltage-gated sodium channel NaV1.7 as new analgesics. Thus far, however, in vitro selectivity has proved difficult for small molecules, and peptides generally lack appropriate pharmacokinetic properties. We previously identified the NaV1.7 inhibitory peptide GpTx-1 from tarantula venom and optimized its potency and selectivity via structure-guided analoging. To further understand GpTx-1 binding to NaV1.7, we have mapped the binding site to transmembrane segments 1-4 of the second pseudosubunit internal repeat (commonly referred to as Site 4) using NaV1.5/NaV1.7 chimeric protein constructs. We also report that select GpTx-1 amino acid residues apparently not contacting NaV1.7 can be derivatized with a hydrophilic polymer without adversely affecting peptide potency. Homodimerization of GpTx-1 with a bifunctional polyethylene glycol (PEG) linker resulted in a compound with increased potency and a significantly reduced off-rate, demonstrating the ability to modulate the function and properties of GpTx-1 by linking to additional molecules. PMID:26112439

  15. International Working Group on Life Management of Nuclear Power Plants. (IWG-LMNPP). Regular meeting. Working material. V. 1

    International Nuclear Information System (INIS)

    National programs of Argentina, Brazil, Belgium, Czech Republic, Canada, France and Germany related to nuclear power plants life management presented at the Technical Committee Meeting are published in this volume. Finnish report VTT-TIED-1843 included in this volume was already included separately in the INIS Database. The main features of the reports are oriented towards extension of NPP lifetime and conditions indispensable to achieve in order to fulfil the safety requirements including testing the mechanical properties of relevant reactor components

  16. Reactor containment and reactor safety in the United States

    International Nuclear Information System (INIS)

    The reactor safety systems of two reactors are studied aiming at the reactor containment integrity. The first is a BWR type reactor and is called Peachbottom 2, and the second is a PWR type reactor, and is called surry. (E.G.)

  17. Reconstruction of the Emergency Core Cooling System (ECCS), Confinement Spray System (SSK) and Pressurizer Safety Valves and Relief Line (PVKO)

    International Nuclear Information System (INIS)

    The paper deals with the results of reconstruction of the ECCS, SSK, and PVKO systems as implemented during the Gradual Upgrading with safety upgrading of the Bohunice V1 nuclear power plant 1997 to 2000. (author)

  18. Build-up the new essential service water system (TVD)

    International Nuclear Information System (INIS)

    n this paper there is description of the service water system reconstruction goals, description of the service water system before reconstruction, and description of the essential service water system in NPP V-1 Jaslovske Bohunice after reconstruction. (author)

  19. TRIGA reactor main systems

    International Nuclear Information System (INIS)

    This module describes the main systems of low power (<2 MW) and higher power (≥2 MW) TRIGA reactors. The most significant difference between the two is that forced reactor cooling and an emergency core cooling system are generally required for the higher power TRIGA reactors. However, those TRIGA reactors that are designed to be operated above 3 MW also use a TRIGA fuel that is specifically designed for those higher power outputs (3 to 14 MW). Typical values are given for the respective systems although each TRIGA facility will have unique characteristics that may only be determined by the experienced facility operators. Due to the inherent wide scope of these research reactor facilities construction and missions, this training module covers those systems found at most operating TRIGA reactor facilities but may also discuss non-standard equipment that was found to be operationally useful although not necessarily required. (author)

  20. Evaluation of research reactors

    International Nuclear Information System (INIS)

    The present status of research reactors with highly enriched (93%) uranium fuel at JAERI, JRR-2 and JMTR is described. JRR-2 is a heterogeneous type of reactor, using heavy water as moderator and coolant. It uses both MTR type and cylindrical type of fuel elements. The maximum thermal power and the thermal neutron flux are 10 MW and 2x1014 n/cm2 see respectively. The reactor has been used for various experiments such as solid state physics, material irradiation, reactor fuel irradiation and radioisotope production. The JMTR is a multi-purpose tank type material testing reactor, and light water moderator and coolant, operated at 50 MW. The evaluation of lower enriched fuel and its consequences for both reactors is considered more especially

  1. Multipurpose research reactors

    International Nuclear Information System (INIS)

    The international symposium on the utilization of multipurpose research reactors and related international co-operation was organized by the IAEA to provide for information exchange on current uses of research reactors and international co-operative projects. The symposium was attended by about 140 participants from 36 countries and two international organizations. There were 49 oral presentations of papers and 24 poster presentations. The presentations were divided into 7 sessions devoted to the following topics: neutron beam research and applications of neutron scattering (6 papers and 1 poster), reactor engineering (6 papers and 5 posters), irradiation testing of fuel and material for fission and fusion reactors (6 papers and 10 posters), research reactor utilization programmes (13 papers and 4 posters), neutron capture therapy (4 papers), neutron activation analysis (3 papers and 4 posters), application of small reactors in research and training (11 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

  2. The nuclear soliton reactor

    International Nuclear Information System (INIS)

    The basic reactor physics of a completely novel nuclear fission reactor design - the soliton-reactor - is presented on the basis of a simple model. In such a reactor, the neutrons in the critical region convert either fertile material in the adjacent layers into fissile material or reduce the poisoning of fissile material in such a manner that successively new critical regions emerge. The result is an autocatalytically driven burn-up wave which propagates throughout the reactor. Thereby, the relevant characteristic spatial distributions (neutron flux, specific power density and the associated particle densities) are solitons - wave phenomena resulting from non-linear partial differential equations which do not change their shape during propagation. A qualitativley new kind of harnessing nuclear fission energy may become possible with fuel residence times comparable with the useful lifetime of the reactor system. In the long run, fast breeder systems which exploit the natural uranium and thorium resources, without any reprocessing capacity are imaginable. (orig.)

  3. Fast Spectrum Reactors

    CERN Document Server

    Todd, Donald; Tsvetkov, Pavel

    2012-01-01

    Fast Spectrum Reactors presents a detailed overview of world-wide technology contributing to the development of fast spectrum reactors. With a unique focus on the capabilities of fast spectrum reactors to address nuclear waste transmutation issues, in addition to the well-known capabilities of breeding new fuel, this volume describes how fast spectrum reactors contribute to the wide application of nuclear power systems to serve the global nuclear renaissance while minimizing nuclear proliferation concerns. Readers will find an introduction to the sustainable development of nuclear energy and the role of fast reactors, in addition to an economic analysis of nuclear reactors. A section devoted to neutronics offers the current trends in nuclear design, such as performance parameters and the optimization of advanced power systems. The latest findings on fuel management, partitioning and transmutation include the physics, efficiency and strategies of transmutation, homogeneous and heterogeneous recycling, in addit...

  4. Fusion reactor research

    International Nuclear Information System (INIS)

    This work covers four separate areas: (1) development of technology for processing liquid lithium from blankets, (2) investigation of hydrogen isotope permeation in candidate structural metals and alloys for near-term fusion reactors, (3) analytical studies encompassing fusion reactor thermal hydraulics, tritium facility design, and fusion reactor safety, and (4) studies involving dosimetry and damage analysis. Recent accomplishments in each of these areas are summarized

  5. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    The Integral Fast Reactor (IFR) is an innovative liquid metal reactor concept being developed at Argonne National Laboratory. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system. This paper describes the key features and potential advantages of the IFR concept, with emphasis on its safety characteristics. 3 refs., 4 figs., 1 tab

  6. The replacement research reactor

    International Nuclear Information System (INIS)

    As a consequences of the government decision in September 1997. ANSTO established a replacement research reactor project to manage the procurement of the replacement reactor through the necessary approval, tendering and contract management stages This paper provides an update of the status of the project including the completion of the Environmental Impact Statement. Prequalification and Public Works Committee processes. The aims of the project, management organisation, reactor type and expected capabilities are also described

  7. PFBR reactor protection

    International Nuclear Information System (INIS)

    Design philosophy adopted for Prototype Fast breeder Reactor (PFBR) is a classical one and has the following features: triplicated sensors for measuring important safety parameters; two independent reactor protection Logic Systems based on solid state devices; reactivity control achieved by control rods; gas equipped modules at the core blanket interface providing negative reactivity. Design verification of these features showed that safety of the reactor can be achieved by a traditional approach since the inherent features of LMFBR make this easy

  8. Reactor BR2

    International Nuclear Information System (INIS)

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported

  9. TRIGA reactor characteristics

    International Nuclear Information System (INIS)

    This module describes the general design, characteristics and parameters of TRIGA reactors and fuels. It is recommended that most of this information should be incorporated into any reactor operator training program and, in many cases, the facility Safety Analysis Report. It is oriented to teach the basics of the physics and mechanical design of the TRIGA fuel as well as its unique operational characteristics and the differences between TRIGA fuels and others more traditional reactor fuels. (nevyjel)

  10. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of four main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents, the development of an expert system for the aid to diagnosis; the development and application of a probabilistic reactor dynamics method. Main achievements in 1999 are reported

  11. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    Research and development activities in the Department of Reactor Engineering in fiscal 1984 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, reactor physics experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, safeguards technology, and activities of the Committee on Reactor Physics. (author)

  12. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research and development activities in the Division of Reactor Engineering in fiscal 1981 are described. The work of the Division is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committee on Reactor Physics. (author)

  13. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research activities in the Division of Reactor Engineering in fiscal 1979 are described. The work of the Division is closely related to development of multi-purpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committees on Reactor Physics and on Decomissioning of Nuclear Facilities. (author)

  14. New reactor concepts

    International Nuclear Information System (INIS)

    The document gives a summary of new nuclear reactor concepts from a technological point of view. Belgium supports the development of the European Pressurized-Water Reactor, which is an evolutionary concept based on the European experience in Pressurized-Water Reactors. A reorientation of the Belgian choice for this evolutionary concept may be required in case that a decision is taken to burn plutonium, when the need for flexible nuclear power plants arises or when new reactor concepts can demonstrate proved benefits in terms of safety and cost

  15. Reactor construction steels

    International Nuclear Information System (INIS)

    The basic functions of light water reactor components are shown on the example of a pressurized water reactor and the requirements resulting therefrom for steel, the basic structural material, are derived. A detailed analysis of three main groups of reactor steels is presented and the applications are indicated of low-alloyed steels, high-alloyed austenitic steels, and steels with a high content of Ni and of alloying additions for steam generator pipes. An outline is given of prospective fast breeder reactor steels. (J.K.)

  16. Commercialization of fast reactors

    International Nuclear Information System (INIS)

    Comparative analysis has been performed of capital and fuel cycle costs for fast BN-type and pressurized light water VVER-type reactors. As a result of materials demand and components costs comparison of NPPs with VVER-1000 and BN-600 reactors, respectively, conclusion was made, that under equal conditions of the comparison, NPP with fast reactor had surpassed the specific capital cost of NPP with VVER by about 30 - 40 %. Ways were determined for further decrease of this difference, as well as for the fuel cycle cost reduction, because at present it is higher than that of VVER-type reactors. (author)

  17. Mirror fusion reactors

    International Nuclear Information System (INIS)

    Conceptual design studies were made of fusion reactors based on the three current mirror-confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fuel for fission reactors. We have designed a large commercial hybrid and a small pilot-plant hybrid based on standard mirror confinement. Tandem mirror designs include a commercial 1000-MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single-cell pilot plant

  18. Natural convection type reactor

    International Nuclear Information System (INIS)

    In a natural convection type nuclear reactor, a reactor core is disposed such that the top of the reactor core is always situated in a flooded position even if pipelines connected to the pressure vessel are ruptured and the level at the inside of the reactor vessel is reduced due to flashing. Further, a lower dry well situated below the pressure vessel is disposed such that it is in communication with a through hole to a pressure suppression chamber situated therearound and the reactor core is situated at the level lower than that of the through hole. If pipelines connected to the pressure vessel are ruptured to cause loss of water, although the water level is lowered after the end of the flashing, the reactor core is always flooded till the operation of a pressure accummulation water injection system to prevent the top of the reactor core even from temporary exposure. Further, injected water is discharged to the outside of the pressure vessel, transferred to the lower dry well, and flows through the through hole to the pressure control chamber and cools the surface of the reactor pressure vessel from the outside. Accordingly, the reactor core is cooled to surely and efficiently remove the after-heat. (N.H.)

  19. INVAP's Research Reactor Designs

    International Nuclear Information System (INIS)

    INVAP, an Argentine company founded more than three decades ago, is today recognized as one of the leaders within the research reactor industry. INVAP has participated in several projects covering a wide range of facilities, designed in accordance with the requirements of our different clients. For complying with these requirements, INVAP developed special skills and capabilities to deal with different fuel assemblies, different core cooling systems, and different reactor layouts. This paper summarizes the general features and utilization of several INVAP research reactor designs, from subcritical and critical assemblies to high-power reactors IAEA safety

  20. Reactor power control device

    International Nuclear Information System (INIS)

    The present invention provides a control device which can conduct scram and avoid lowering of the power of a nuclear power plant upon occurrence of earthquakes. Namely, the device of the present invention comprises, in addition to an existent power control device, (1) an earthquake detector for detecting occurrence and annihilation of earthquakes and (2) a reactor control device for outputting control rod operation signals and reactor core flow rate control signals depending on the earthquake detection signals from the detector, and reactor and plant information. With such a constitution, although the reactor is vibrated by earthquakes, the detector detects slight oscillations of the reactor by initial fine vibration waves as premonitory symptoms of serious earthquakes. The earthquake occurrence signals are outputted to the reactor control device. The reactor control device, receiving the signals, changes the position of control rods by way of control rod driving mechanisms to make the axial power distribution in the reactor core to a top peak type. As a result, even if the void amount in the reactor core is reduced by the subsequent actual earthquakes, since the void amount is moved, effects on the increase of neutron fluxes by the actual earthquakes is small. (I.S.)

  1. Nuclear reactor internals arrangement

    International Nuclear Information System (INIS)

    A nuclear reactor internals arrangement is disclosed which facilitates reactor refueling. A reactor vessel and a nuclear core is utilized in conjunction with an upper core support arrangement having means for storing withdrawn control rods therein. The upper core support is mounted to the underside of the reactor vessel closure head so that upon withdrawal of the control rods into the upper core support, the closure head, the upper core support and the control rods are removed as a single unit thereby directly exposing the core for purposes of refueling

  2. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed

  3. On the Effects on Cortical Spontaneous Activity of the Symmetries of the Network of Pinwheels in Visual Area V1.

    Science.gov (United States)

    Veltz, Romain; Chossat, Pascal; Faugeras, Olivier

    2015-12-01

    This paper challenges and extends earlier seminal work. We consider the problem of describing mathematically the spontaneous activity of V1 by combining several important experimental observations including (1) the organization of the visual cortex into a spatially periodic network of hypercolumns structured around pinwheels, (2) the difference between short-range and long-range intracortical connections, the first ones being rather isotropic and producing naturally doubly periodic patterns by Turing mechanisms, the second one being patchy, and (3) the fact that the Turing patterns spontaneously produced by the short-range connections and the network of pinwheels have similar periods. By analyzing the PO maps, we are able to classify all possible singular points (the pinwheels) as having symmetries described by a small subset of the wallpaper groups. We then propose a description of the spontaneous activity of V1 using a classical voltage-based neural field model that features isotropic short-range connectivities modulated by non-isotropic long-range connectivities. A key observation is that, with only short-range connections and because the problem has full translational invariance in this case, a spontaneous doubly periodic pattern generates a 2-torus in a suitable functional space which persists as a flow-invariant manifold under small perturbations, for example when turning on the long-range connections. Through a complete analysis of the symmetries of the resulting neural field equation and motivated by a numerical investigation of the bifurcations of their solutions, we conclude that the branches of solutions which are stable over an extended range of parameters are those that correspond to patterns with an hexagonal (or nearly hexagonal) symmetry. The question of which patterns persist when turning on the long-range connections is answered by (1) analyzing the remaining symmetries on the perturbed torus and (2) combining this information with the Poincar

  4. Alternative splicing at C terminus of Ca(V)1.4 calcium channel modulates calcium-dependent inactivation, activation potential, and current density.

    Science.gov (United States)

    Tan, Gregory Ming Yeong; Yu, Dejie; Wang, Juejin; Soong, Tuck Wah

    2012-01-01

    The Ca(V)1.4 voltage-gated calcium channel is predominantly expressed in the retina, and mutations to this channel have been associated with human congenital stationary night blindness type-2. The L-type Ca(V)1.4 channel displays distinct properties such as absence of calcium-dependent inactivation (CDI) and slow voltage-dependent inactivation (VDI) due to the presence of an autoinhibitory domain (inhibitor of CDI) in the distal C terminus. We hypothesized that native Ca(V)1.4 is subjected to extensive alternative splicing, much like the other voltage-gated calcium channels, and employed the transcript scanning method to identify alternatively spliced exons within the Ca(V)1.4 transcripts isolated from the human retina. In total, we identified 19 alternative splice variations, of which 16 variations have not been previously reported. Characterization of the C terminus alternatively spliced exons using whole-cell patch clamp electrophysiology revealed a splice variant that exhibits robust CDI. This splice variant arose from the splicing of a novel alternate exon (43*) that can be found in 13.6% of the full-length transcripts screened. Inclusion of exon 43* inserts a stop codon that truncates half the C terminus. The Ca(V)1.4 43* channel exhibited robust CDI, a larger current density, a hyperpolarized shift in activation potential by ∼10 mV, and a slower VDI. Through deletional experiments, we showed that the inhibitor of CDI was responsible for modulating channel activation and VDI, in addition to CDI. Calcium currents in the photoreceptors were observed to exhibit CDI and are more negatively activated as compared with currents elicited from heterologously expressed full-length Ca(V)1.4. Naturally occurring alternative splice variants may in part contribute to the properties of the native Ca(V)1.4 channels. PMID:22069316

  5. Nuclear safety in Slovak Republic. Status of safety improvements

    International Nuclear Information System (INIS)

    Status of the safety improvements at Bohunice V-1 units concerning WWER-440/V-230 design upgrading were as follows: supplementing of steam generator super-emergency feed water system; higher capacity of emergency core cooling system; supplementing of automatic links between primary and secondary circuit systems; higher level of secondary system automation. The goal of the modernization program for Bohunice V-1 units WWER-440/V-230 was to increase nuclear safety to the level of the proposals and IAEA recommendations and to reach probability goals of the reactor concerning active zone damage, leak of radioactive materials, failures of safety systems and damage shields. Upgrading program for Mochovce NPP - WWER-440/V-213 is concerned with improving the integrity of the reactor pressure vessel, steam generators 'leak before break' methods applied for the NPP, instrumentation and control of safety systems, diagnostic systems, replacement of in-core monitoring system, emergency analyses, pressurizers safety relief valves, hydrogen removal system, seismic evaluations, non-destructive testing, fire protection. Implementation of quality assurance has a special role in improvement of operational safety activities as well as safety management and safety culture, radiation protection, decommissioning and waste management and training. The Year 2000 problem is mentioned as well

  6. The research reactors their contribution to the reactors physics

    International Nuclear Information System (INIS)

    The 19 october 2000, the french society of nuclear energy organized a day on the research reactors. This associated report of the technical session, reactors physics, is presented in two parts. The first part deals with the annual meeting and groups general papers on the pressurized water reactors, the fast neutrons reactors and the fusion reactors industry. The second part presents more technical papers about the research programs, critical models, irradiation reactors (OSIRIS and Jules Horowitz) and computing tools. (A.L.B.)

  7. Kinematics and subpopulations' structure definition of blue fox (Alopex lagopus) sperm motility using the ISAS® V1 CASA system.

    Science.gov (United States)

    Soler, C; García, A; Contell, J; Segervall, J; Sancho, M

    2014-08-01

    Over recent years, technological advances have brought innovation in assisted reproduction to the agriculture. Fox species are of great economical interest in some countries, but their semen characteristics have not been studied enough. To advance the knowledge of function of fox spermatozoa, five samples were obtained by masturbation, in the breeding season. Kinetic analysis was performed using ISAS® v1 system. Usual kinematic parameters (VCL, VSL, VAP, LIN, STR, WOB, ALH and BCF) were considered. To establish the standardization for the analysis of samples, the minimum number of cells to analyse and the minimum number of fields to capture were defined. In the second step, the presence of subpopulations in blue fox semen was analysed. The minimum number of cells to test was 30, because kinematic parameters remained constant along the groups of analysis. Also, the effectiveness of ISAS® D4C20 counting chamber was studied, showing that the first five squares presented equivalent results, while in the squares six and seven, the kinematic parameters showed a reduction in all of them, but not in the concentration or motility percentage. Kinematic variables were grouped into two principal components (PC). A linear movement characterized PC1, while PC2 showed an oscillatory movement. Three subpopulations were found, varying in structure among different animals. PMID:24890953

  8. Modeling of 10 GeV-1 TeV laser-plasma accelerators using Lorentz booster simulations

    Energy Technology Data Exchange (ETDEWEB)

    Vay, J.-L.; Geddes, C.G.R.; Esarey, E.; Esarey, E.; Leemans, W.P.; Cormier-Michel, E.; Grote, D.P.

    2011-12-01

    Modeling of laser-plasma wakefield accelerators in an optimal frame of reference [J.-L. Vay, Phys. Rev. Lett. 98 130405 (2007)] allows direct and efficient full-scale modeling of deeply depleted and beam loaded laser-plasma stages of 10 GeV-1 TeV (parameters not computationally accessible otherwise). This verifies the scaling of plasma accelerators to very high energies and accurately models the laser evolution and the accelerated electron beam transverse dynamics and energy spread. Over 4, 5 and 6 orders of magnitude speedup is achieved for the modeling of 10 GeV, 100 GeV and 1 TeV class stages, respectively. Agreement at the percentage level is demonstrated between simulations using different frames of reference for a 0.1 GeV class stage. Obtaining these speedups and levels of accuracy was permitted by solutions for handling data input (in particular particle and laser beams injection) and output in a relativistically boosted frame of reference, as well as mitigation of a high-frequency instability that otherwise limits effectiveness.

  9. Optimization of radioactive clothes washing with respect to processing of laundry waters from V-1 nuclear power plant

    International Nuclear Information System (INIS)

    An analysis was made of the current technology of washing and decontamination of laundry and protective clothing as well as of the operating regime of the special laundry in the V-1 nuclear power plant. The laundry is provided with two automatic washing machines PAC-91 D, the quality of washing is controlled visually, the quality of decontamination with a RUP-1 dosemeter. The processing and disposal of water from the laundry has some problems which differ from the problems of other liquid radioactive wastes. The water contains considerable amounts of surfactants and phosphates and must therefore be treated both radiochemically and chemically. In a number of experiments washing procedures were optimized for laundry with various levels of contamination. For laundry contaminated to 148 kBq/m2 only the first wash is used at 60 degC with gradual heating to 90 degC and the amount of detergent is increased, thereby reducing the volume of waste water by more than 8%. In order to reduce the amount of surfactants on the washed laundry a special preparation based on a weak organic acid is added to the demineralized water used for the last rinse. Increased decontamination efficiency is expected with the introduction of a new special detergent for washing radioactive laundry in Czechoslovak nuclear power plants, whose development based on domestic raw materials has been started. (Z.M.)

  10. Acupuncture Alleviates Colorectal Hypersensitivity and Correlates with the Regulatory Mechanism of TrpV1 and p-ERK

    Directory of Open Access Journals (Sweden)

    Shao-Jun Wang

    2012-01-01

    Full Text Available Here we used a mouse model of zymosan-induced colorectal hypersensitivity, a similar model of IBS in our previous work, to evaluate the effectiveness of the different number of times of acupuncture and elucidate its potential mechanism of EA treatment. Colorectal distension (CRD tests show that intracolonic zymosan injection does, while saline injection does not, induce a typical colorectal hypersensitivity. EA treatment at classical acupoints Zusanli (ST36 and Shangjuxu (ST37 in both hind limbs for 15 min slightly attenuated and significantly blunted the hypersensitive responses after first and fifth acupunctures, respectively, to colorectal distention in zymosan treatment mice, but not in saline treatment mice. Western blot results indicated that ion channel and TrpV1 expression in colorectum as well as ERK1/2 MAPK pathway activation in peripheral and central nerve system might be involved in this process. Hence, we conclude that EA is a potential therapeutic tool in the treatment and alleviation of chronic abdominal pain, and the effectiveness of acupuncture analgesia is accumulative with increased number of times of acupuncture when compared to that of a single time of acupuncture.

  11. High-throughput measurements of thermochromic behavior in V(1-x)Nb(x)O(2) combinatorial thin film libraries.

    Science.gov (United States)

    Barron, S C; Gorham, J M; Patel, M P; Green, M L

    2014-10-13

    We describe a high-throughput characterization of near-infrared thermochromism in V1-xNbxO2 combinatorial thin film libraries. The oxide thin film library was prepared with a VO2 crystal structure and a continuous gradient in composition with Nb concentrations in the range of less than 1% to 45%. The thermochromic phase transition from monoclinic to tetragonal was characterized by the accompanying change in near-infrared reflectance. With increasing Nb substitution, the transition temperature was depressed from 65 to 35 °C, as desirable for smart window applications. However, the magnitude of the reflectance change across the thermochromic transition was also reduced with increasing Nb film content. Data collection, handling, and analysis supporting thermochromic characterization were fully automated to achieve high throughput. Using this system, in 14 h, temperature-dependent infrared reflectances were measured at 165 arbitrary locations on a thin film combinatorial library; these measurements were analyzed for thermochromic transitions in minutes. PMID:25180465

  12. Push-Pull Receptive Field Organization and Synaptic Depression: Mechanisms for Reliably Encoding Naturalistic Stimuli in V1

    Science.gov (United States)

    Kremkow, Jens; Perrinet, Laurent U.; Monier, Cyril; Alonso, Jose-Manuel; Aertsen, Ad; Frégnac, Yves; Masson, Guillaume S.

    2016-01-01

    Neurons in the primary visual cortex are known for responding vigorously but with high variability to classical stimuli such as drifting bars or gratings. By contrast, natural scenes are encoded more efficiently by sparse and temporal precise spiking responses. We used a conductance-based model of the visual system in higher mammals to investigate how two specific features of the thalamo-cortical pathway, namely push-pull receptive field organization and fast synaptic depression, can contribute to this contextual reshaping of V1 responses. By comparing cortical dynamics evoked respectively by natural vs. artificial stimuli in a comprehensive parametric space analysis, we demonstrate that the reliability and sparseness of the spiking responses during natural vision is not a mere consequence of the increased bandwidth in the sensory input spectrum. Rather, it results from the combined impacts of fast synaptic depression and push-pull inhibition, the later acting for natural scenes as a form of “effective” feed-forward inhibition as demonstrated in other sensory systems. Thus, the combination of feedforward-like inhibition with fast thalamo-cortical synaptic depression by simple cells receiving a direct structured input from thalamus composes a generic computational mechanism for generating a sparse and reliable encoding of natural sensory events.

  13. Wear mechanism and microstructures of Mo-implanted 4Cr5MoV1Si steel

    Institute of Scientific and Technical Information of China (English)

    YANG Jian-Hua; ZHANG Tong-He

    2004-01-01

    Mo ions extracted from a metal vapor vacuum arc ion source (MEVVA) were implanted into 4Cr5MoV1Si(H13) steel samples with a high implantation dose of 5×1017cm2 and a pulsed ion beam flux of about friction characteristics of the steel. The results from Rutherford backscattering spectroscopy (RBS) and the collision theory demonstrated that the radiation enhanced diffusion gave great influence on the Mo profile. It was observed by X-ray photoelectron spectroscopy (XPS) and grazing-angle X-ray diffraction (GXRD) that carbide of Mo appeared in the doped region for the implantation at 48 kV. The results showed that improvement in the wear resistance of the Mo-implanted steel were mainly due to the formation of Mo2C in the doped zone and the implantation affected zone underneath. Oxidation resistance of the surface iron and the surface with small crystal grains gave influences on the wear resistance in a way.

  14. A Practical Approach to the Investigation of an rSr' Pattern in Leads V1-V2.

    Science.gov (United States)

    Koppikar, Sahil; Barbosa-Barros, Raimundo; Baranchuk, Adrian

    2015-12-01

    The differential diagnosis of an rSr' pattern in leads V1-V2 on electrocardiogram is a frequently encountered entity in clinical cardiology. This finding often presents itself in asymptomatic and healthy individuals. The causes might vary from benign and nonpathological, to severe and life-threatening diseases, such as Brugada syndrome or arrhythmogenic right ventricular dysplasia. Workup of these patients involves a history and physical examination to screen for underlying cardiac disease and potential triggers. Routine investigation involves blood work and a thorough electrocardiographic examination. Echocardiography has a role in evaluating patients in whom structural heart disease is suspected. Pulmonary testing using computed tomography can be conducted if right ventricular enlargement is identified. More advanced testing is not warranted if these initial investigations are reassuring. Referral to an arrhythmia specialist should be considered for patients in whom this finding is due to Brugada syndrome, arrhythmogenic right ventricular dysplasia, or Wolf-Parkinson-White syndrome. We propose a clinical and electrocardiographic algorithm that will assist clinicians in narrowing their differential diagnosis. PMID:26143139

  15. ALMA observations of the vibrationally-excited rotational CO transition $v=1, J=3-2$ towards five AGB stars

    CERN Document Server

    Khouri, T; Ramstedt, S; Lombaert, R; Maercker, M; De Beck, E

    2016-01-01

    We report the serendipitous detection with ALMA of the vibrationally-excited pure-rotational CO transition $v=1, J=3-2$ towards five asymptotic giant branch (AGB) stars, $o$ Cet, R Aqr, R Scl, W Aql, and $\\pi^1$ Gru. The observed lines are formed in the poorly-understood region located between the stellar surface and the region where the wind starts, the so-called warm molecular layer. We successfully reproduce the observed lines profiles using a simple model. We constrain the extents, densities, and kinematics of the region where the lines are produced. R Aqr and R Scl show inverse P-Cygni line profiles which indicate infall of material onto the stars. The line profiles of $o$ Cet and R Scl show variability. The serendipitous detection towards these five sources shows that vibrationally-excited rotational lines can be observed towards a large number of nearby AGB stars using ALMA. This opens a new possibility for the study of the innermost regions of AGB circumstellar envelopes.

  16. Feasibility Study of a 6.6kV, 1MW Transformerless BTB-Based Loop Controller

    Science.gov (United States)

    Yonetani, Shinsuke; Fujita, Hideaki; Akagi, Hirofumi; Okada, Naotaka

    This paper achieves a feasibility study of a 6.6kV, 1MW loop controller that consists of a transformerless back-to-back configuration using two 5-level diode-clamped converters. However, the loop controller requires reducing the zero-sequence current circulating between the two distribution lines below than 0.2 A in rms, in order to avoid malfunction of line-to-ground fault protection relays. Moreover, all the dc voltages across four capacitors in the dc link have to be controlled equally. This paper presents a solution to these problems. Two common-mode chokes are installed at the ac side of each converter to suppress high-frequency zero-sequence currents, while feedback control is applied to eliminate low-frequency zero-sequence currents. Two bidirectional buck-boost dc-dc converters are employed to keep the four capacitor voltages equal. Simulation results verify viability and effectiveness of the loop controller, along with the developed theoretical analysis.

  17. One piece reactor removal

    International Nuclear Information System (INIS)

    Japan Research Reactor No.3 (JRR-3) was the first reactor consisting of 'Japanese-made' components alone except for fuel and heavy water. After reaching its initial critical state in September 1962, JRR-3 had been in operation for 21 years until March 1983. It was decided that the reactor be removed en-bloc in view of the work schedule, cost and management of the reactor following the removal. In the special method developed jointly by the Japanese Atomic Energy Research Institute and Shimizu Construction Co., Ltd., the reactor main unit was cut off from the building by continuous core boring, with its major components bound in the block with biological shield material (heavy concrete), and then conveyed and stored in a large waste store building constructed near the reactor building. Major work processes described in this report include the cutting off, lifting, horizontal conveyance and lowering of the reactor main unit. The removal of the JRR-3 reactor main unit was successfully carried out safely and quickly by the en-block removal method with radiation exposure dose of the workers being kept at a minimum. Thus the high performance of the en-bloc removal method was demonstrated and, in addition, valuable knowhow and other data were obtained from the work. (Nogami, K.)

  18. Reactor Materials Research

    International Nuclear Information System (INIS)

    The activities of the Reactor Materials Research Department of the Belgian Nuclear Research Centre SCK-CEN in 2000 are summarised. The programmes within the department are focussed on studies concerning (1) fusion, in particular mechanical testing; (2) Irradiation Assisted Stress Corrosion Cracking (IASCC); (3) nuclear fuel; and (4) Reactor Pressure Vessel Steel (RPVS)

  19. The fusion reactor

    International Nuclear Information System (INIS)

    Basic principles of the fusion reactor are outlined. Plasma heating and confinement schemes are described. These confinement systems include the linear Z pinch, magnetic mirrors and Tokamaks. A fusion reactor is described and a discussion is given of its environmental impact and its fuel situation. (R.L.)

  20. Polymerization Reactor Engineering.

    Science.gov (United States)

    Skaates, J. Michael

    1987-01-01

    Describes a polymerization reactor engineering course offered at Michigan Technological University which focuses on the design and operation of industrial polymerization reactors to achieve a desired degree of polymerization and molecular weight distribution. Provides a list of the course topics and assigned readings. (TW)

  1. Reactor Materials Research

    Energy Technology Data Exchange (ETDEWEB)

    Van Walle, E

    2001-04-01

    The activities of the Reactor Materials Research Department of the Belgian Nuclear Research Centre SCK-CEN in 2000 are summarised. The programmes within the department are focussed on studies concerning (1) fusion, in particular mechanical testing; (2) Irradiation Assisted Stress Corrosion Cracking (IASCC); (3) nuclear fuel; and (4) Reactor Pressure Vessel Steel (RPVS)

  2. Gas-cooled reactors

    International Nuclear Information System (INIS)

    The present study is the second part of a general survey of Gas Cooled Reactors (GCRs). In this part, the course of development, overall performance and present development status of High Temperature Gas Cooled Reactors (HTCRs) and advances of HTGR systems are reviewed. (author)

  3. Light water reactor program

    Energy Technology Data Exchange (ETDEWEB)

    Franks, S.M.

    1994-12-31

    The US Department of Energy`s Light Water Reactor Program is outlined. The scope of the program consists of: design certification of evolutionary plants; design, development, and design certification of simplified passive plants; first-of-a-kind engineering to achieve commercial standardization; plant lifetime improvement; and advanced reactor severe accident program. These program activities of the Office of Nuclear Energy are discussed.

  4. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of two main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents. Main achievements in 1999 are reported

  5. Light water type reactor

    International Nuclear Information System (INIS)

    The nuclear reactor of the present invention prevents disruption of a reactor core even in a case of occurrence of entire AC power loss event, and even if a reactor core disruption should occur, it prevents a rupture of the reactor container due to excess heating. That is, a high pressure water injection system and a low pressure water injection system operated by a diesel engine are disposed in the reactor building in addition to an emergency core cooling system. With such a constitution, even if an entire AC power loss event should occur, water can surely be injected to the reactor thereby enabling to prevent the rupture of the reactor core. Even if it should be ruptured, water can be sprayed to the reactor container by the low pressure water injection system. Further, if each of water injection pumps of the high pressure water injection system and the low pressure water injection system can be driven also by motors in addition to the diesel engine, the pump operation can be conducted more certainly and integrally. (I.S.)

  6. A C-terminal segment of the V1R vasopressin receptor is unstructured in the crystal structure of its chimera with the maltose-binding protein

    International Nuclear Information System (INIS)

    The 1.8 Å crystal structure of an MBP-fusion protein with the C-terminal cytoplasmic segment of the V1 vasopressin receptor reveals that the receptor segment is unstructured. The V1 vascular vasopressin receptor (V1R) is a G-protein-coupled receptor (GPCR) involved in the regulation of body-fluid osmolality, blood volume and blood pressure. Signal transduction is mediated by the third intracellular loop of this seven-transmembrane protein as well as by the C-terminal cytoplasmic segment. A chimera of the maltose-binding protein (MBP) and the C-terminal segment of V1R has been cloned, expressed, purified and crystallized. The crystals belong to space group P21, with unit-cell parameters a = 51.10, b = 66.56, c = 115.72 Å, β = 95.99°. The 1.8 Å crystal structure reveals the conformation of MBP and part of the linker region of this chimera, with the C-terminal segment being unstructured. This may reflect a conformational plasticity in the C-terminal segment that may be necessary for proper function of V1R

  7. Mice with an NaV1.4 sodium channel null allele have latent myasthenia, without susceptibility to periodic paralysis.

    Science.gov (United States)

    Wu, Fenfen; Mi, Wentao; Fu, Yu; Struyk, Arie; Cannon, Stephen C

    2016-06-01

    Over 60 mutations of SCN4A encoding the NaV1.4 sodium channel of skeletal muscle have been identified in patients with myotonia, periodic paralysis, myasthenia, or congenital myopathy. Most mutations are missense with gain-of-function defects that cause susceptibility to myotonia or periodic paralysis. Loss-of-function from enhanced inactivation or null alleles is rare and has been associated with myasthenia and congenital myopathy, while a mix of loss and gain of function changes has an uncertain relation to hypokalaemic periodic paralysis. To better define the functional consequences for a loss-of-function, we generated NaV1.4 null mice by deletion of exon 12. Heterozygous null mice have latent myasthenia and a right shift of the force-stimulus relation, without evidence of periodic paralysis. Sodium current density was half that of wild-type muscle and no compensation by retained expression of the foetal NaV1.5 isoform was detected. Mice null for NaV1.4 did not survive beyond the second postnatal day. This mouse model shows remarkable preservation of muscle function and viability for haploinsufficiency of NaV1.4, as has been reported in humans, with a propensity for pseudo-myasthenia caused by a marginal Na(+) current density to support sustained high-frequency action potentials in muscle. PMID:27048647

  8. Naval propulsion reactors

    International Nuclear Information System (INIS)

    This article deals with the design and exploitation of naval propulsion reactors, mainly of PWR-type. The other existing or conceivable types of reactors are also presented: 1 - specificities of nuclear propulsion (integration in the ship, marine environment, maneuverability, instantaneous availability, conditions of exploitation-isolation, nuclear safety, safety authority); 2 - PWR-type reactor (stable operation, mastered technology, general design, radiation protection); 3 - other reactor types; 4 - compact or integrated loops architecture; 5 - radiation protection; 6 - reactor core; 7 - reactivity control (core lifetime, control means and mechanisms); 8 - core cooling (natural circulation, forced circulation, primary flow-rate program); 9 - primary loop; 10 - pressurizer; 11 - steam generators and water-steam secondary loop; 12 - auxiliary and safety loops; 13 - control instrumentation; 14 - operation; 15 - nuclear wastes and dismantling. (J.S.)

  9. Iris reactor conceptual design

    International Nuclear Information System (INIS)

    IRIS (International Reactor Innovative and Secure) is a modular, integral, light water cooled, low-to-medium power (100-350 MWe) reactor which addresses the requirements defined by the US DOE for Generation IV reactors, i.e., proliferation resistance, enhanced safety, improved economics and fuel cycle sustainability. It relies on the proven technology of light water reactors and features innovative engineering, but it does not require new technology development. This paper discusses the current reference IRIS design, which features a 1000 MWt thermal core with proven 5%-enriched uranium oxide fuel and five-year long straight burn fuel cycle, integral reactor vessel housing helical tube steam generators and immersed spool pumps. Other major contributors to the high level of safety and economic attractiveness are the safety by design and optimized maintenance approaches, which allow elimination of some classes of accidents, lower capital cost, long operating cycle, and high capacity factors. (author)

  10. Research reactor DHRUVA

    International Nuclear Information System (INIS)

    DHRUVA, a 100 MWt research reactor located at the Bhabha Atomic Research Centre, Bombay, attained first criticality during August, 1985. The reactor is fuelled with natural uranium and is cooled, moderated and reflected by heavy water. Maximum thermal neutron flux obtained in the reactor is 1.8 X 1014 n/cm2/sec. Some of the salient design features of the reactor are discussed in this paper. Some important features of the reactor coolant system, regulation and protection systems and experimental facilities are presented. A short account of the engineered safety features is provided. Some of the problems that were faced during commissioning and the initial phase of power operation are also dealt upon

  11. Reactor core monitoring method

    Energy Technology Data Exchange (ETDEWEB)

    Mori, Michitsugu [Tokyo Electric Power Co., Inc. (Japan); Kanemoto, Shigeru; Enomoto, Mitsuhiro; Ebata, Shigeo

    1998-05-06

    The present invention provides a method of monitoring the state of coolant flow in a reactor of a BWR power plant. Namely, a plurality of local power region monitors (LPRM) are disposed to the inside of the reactor core for monitoring a power distribution. Signals of at least two optional LPRM detectors situated at positions different in axial or radial positions of the reactor core are obtained. General fluctuation components which nuclear hydrothermally fluctuate in overall reactor core are removed from the components of the signals. Then, correlational functions between these signals are determined. The state of coolant flow in the reactor is monitored based on the correlational function. When the axial flowing rate and radial flow interference are monitored, the accuracy upon monitoring axial and radial local behaviors of coolants can be improved by thus previously removing the general fluctuation components from signals of LPRM detectors and extracting local void information near to LPRM detectors at high accuracy. (I.S.)

  12. Physics of nuclear reactors

    International Nuclear Information System (INIS)

    This manual covers all the aspects of the science of neutron transport in nuclear reactors and can be used with great advantage by students, engineers or even reactor experts. It is composed of 18 chapters: 1) basis of nuclear physics, 2) the interactions of neutrons with matter, 3) the interactions of electromagnetic radiations and charged-particles with matter, 4) neutron slowing-down, 5) resonant absorption, 6) Doppler effect, 7) neutron thermalization, 8) Boltzmann equation, 9) calculation methods in neutron transport theory, 10) neutron scattering, 11) reactor reactivity, 12) theory of the critical homogenous pile, 13) the neutron reflector, 14) the heterogeneous reactor, 15) the equations of the fuel cycle, 16) neutron counter-reactions, 17) reactor kinetics, and 18) calculation methods in neutron scattering

  13. Mirror reactor surface study

    International Nuclear Information System (INIS)

    A general survey is presented of surface-related phenomena associated with the following mirror reactor elements: plasma first wall, ion sources, neutral beams, director converters, vacuum systems, and plasma diagnostics. A discussion of surface phenomena in possible abnormal reactor operation is included. Several studies which appear to merit immediate attention and which are essential to the development of mirror reactors are abstracted from the list of recommended areas for surface work. The appendix contains a discussion of the fundamentals of particle/surface interactions. The interactions surveyed are backscattering, thermal desorption, sputtering, diffusion, particle ranges in solids, and surface spectroscopic methods. A bibliography lists references in a number of categories pertinent to mirror reactors. Several complete published and unpublished reports on surface aspects of current mirror plasma experiments and reactor developments are also included

  14. FBR type reactor

    International Nuclear Information System (INIS)

    A circular neutron reflector is disposed vertically movably so as to surround the outer circumference of a reactor core barrel. A reflector driving device comprises a driving device main body attracted to the outer wall surface of the reactor barrel by electromagnetic attraction force and an inertia body disposed above the driving device main body vertically movably. A reflector is connected below the reactor driving device. At the initial stage, a spontaneous large current is supplied to upper electromagnetic repulsion coils of the reflector driving device, impact electromagnetic repulsion force is caused between the inertia body and the reflector driving device, so that the driving device main body moves downwardly by a predetermined distance and stopped. The reflector driving device can be lowered in a step-like manner to an appropriate position suitable to restart the reactor during stoppage of the reactor core by conducting spontaneous supply of current repeatedly to the upper electromagnetic repulsion coils. (I.N.)

  15. TRIGA research reactors

    International Nuclear Information System (INIS)

    TRIGA (Training, Research, Isotope production, General-Atomic) has become the most used research reactor in the world with 65 units operating in 24 countries. The original patent for TRIGA reactors was registered in 1958. The success of this reactor is due to its inherent level of safety that results from a prompt negative temperature coefficient. Most of the neutron moderation occurs in the nuclear fuel (UZrH) because of the presence of hydrogen atoms, so in case of an increase of fuel temperature, the neutron spectrum becomes harder and neutrons are less likely to fission uranium nuclei and as a consequence the power released decreases. This inherent level of safety has made this reactor fit for training tool in university laboratories. Some recent versions of TRIGA reactors have been designed for medicine and industrial isotope production, for neutron therapy of cancers and for providing a neutron source. (A.C.)

  16. Status of French reactors

    Energy Technology Data Exchange (ETDEWEB)

    Ballagny, A. [Commissariat a l`Energie Atomique, Saclay (France)

    1997-08-01

    The status of French reactors is reviewed. The ORPHEE and RHF reactors can not be operated with a LEU fuel which would be limited to 4.8 g U/cm{sup 3}. The OSIRIS reactor has already been converted to LEU. It will use U{sub 3}Si{sub 2} as soon as its present stock of UO{sub 2} fuel is used up, at the end of 1994. The decision to close down the SILOE reactor in the near future is not propitious for the start of a conversion process. The REX 2000 reactor, which is expected to be commissioned in 2005, will use LEU (except if the fast neutrons core option is selected). Concerning the end of the HEU fuel cycle, the best option is reprocessing followed by conversion of the reprocessed uranium to LEU.

  17. Nuclear reactor design

    CERN Document Server

    2014-01-01

    This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.

  18. Compact torsatron reactors

    International Nuclear Information System (INIS)

    Low-aspect-ratio torsatron configurations could lead to compact stellarator reactors with R0 = 8--11m, roughly one-half to one-third the size of more conventional stellarator reactor designs. Minimum-size torsatron reactors are found using various assumptions. Their size is relatively insensitive to the choice of the conductor parameters and depends mostly on geometrical constraints. The smallest size is obtained by eliminating the tritium breeding blanket under the helical winding on the inboard side and by reducing the radial depth of the superconducting coil. Engineering design issues and reactor performance are examined for three examples to illustrate the feasibility of this approach for compact reactors and for a medium-size (R0 ≅ 4 m,/bar a/ /approx lt/ 1 m) copper-coil ignition experiment. 26 refs., 11 figs., 7 tabs

  19. Multi-purpose reactor

    International Nuclear Information System (INIS)

    The Multi-Purpose-Reactor (MPR), is a pool-type reactor with an open water surface and variable core arrangement. Its main feature is plant safety and reliability. Its power is 22MWth, cooled by light water and moderated by beryllium. It has platetype fuel elements (MTR type, approx. 20%. enriched uranium) clad in aluminium. Its cobalt (Co60) production capacity is 50000 Ci/yr, 200Ci/gr. The distribution of the reactor core and associated control and safety systems is essentially based on the following design criteria: - upwards cooling flow, to waive the need for cooling flow inversion in case the reactor is cooled by natural convection if confronted with a loss of pumping power, and in order to establish a superior heat transfer potential (a higher coolant saturation temperature); - easy access to the reactor core from top of pool level with the reactor operating at full power, in order to facilitate actual implementation of experiments. Consequently, mechanisms associated to control and safety rods s,re located underneath the reactor tank; - free access of reactor personnel to top of pool level with the reactor operating at full power. This aids in the training of personnel and the actual carrying out of experiments, hence: - a vast water column was placed over the core to act as radiation shielding; - the core's external area is cooled by a downwards flow which leads to a decay tank beyond the pool (for N16 to decay); - a small downwards flow was directed to stream downwards from above the reactor core in order to drag along any possibly active element; and - a stagnant hot layer system was placed at top of pool level so as to minimize the upwards coolant flow rising towards pool level

  20. The CAREM reactor and present currents in reactor design

    International Nuclear Information System (INIS)

    INVAP has been working on the CAREM project since 1983. It concerns a very low power reactor for electrical energy generation. The design of the reactor and the basic criteria used were described in 1984. Since then, a series of designs have been presented for reactors which are similar to CAREM regarding the solutions presented to reduce the chance of major nuclear accidents. These designs have been grouped under different names: Advanced Reactors, Second Generation Reactors, Inherently Safe Reactors, or even, Revolutionary Reactors. Every reactor fabrication firm has, at least, one project which can be placed in this category. Presently, there are two main currents of Reactor Design; Evolutionary and Revolutionary. The present work discusses characteristics of these two types of reactors, some revolutionary designs and common criteria to both types. After, these criteria are compared with CAREM reactor design. (Author)

  1. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research activities in the Division of Reactor Engineering in fiscal 1977 are described. Works of the Division are development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and development of Liquid Metal Fast Breeder Reactor for Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology, and Committee on Reactor Physics. (Author)

  2. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    Research and development activities in the Department of Reactor Engineering in fiscal 1983 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and safeguards technology, and activities of the Committee on Reactor Physics. (author)

  3. Reactor Engineering Division annual report

    International Nuclear Information System (INIS)

    Research activities conducted in Reactor Engineering Division in fiscal 1975 are summarized in this report. Works in the division are closely related to the development of multi-purpose High-temperature Gas Cooled Reactor, the development of Liquid Metal Fast Breeder Reactor by Power Reactor and Nuclear Fuel Development Corporation, and engineering research of thermonuclear fusion reactor. Many achievements are described concerning nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology and activities of the Committee on Reactor Physics. (auth.)

  4. Reactor performance calculations for water reactors

    International Nuclear Information System (INIS)

    The principles of nuclear, thermal and hydraulic performance calculations for water cooled reactors are discussed. The principles are illustrated by describing their implementation in the UKAEA PATRIARCH scheme of computer codes. This material was originally delivered as a course of lectures at the Technical University of Helsinki in Summer of 1969.

  5. Epitope grafting, re-creating a conformational Bet v 1 antibody epitope on the surface of the homologous apple allergen Mal d 1

    DEFF Research Database (Denmark)

    Holm, Jens; Ferreras, Mercedes; Ipsen, Henrik; Würtzen, Peter A; Gajhede, Michael; Larsen, Jørgen N; Lund, Kaare; Spangfort, Michael D

    2011-01-01

    Birch-allergic patients often experience oral allergy syndrome upon ingestion of vegetables and fruits, most prominently apple, that is caused by antibody cross-reactivity of the IgE antibodies in patients to proteins sharing molecular surface structures with the major birch pollen group 1 allergen...... from Betula verrucosa (Bet v 1). Still, to what extent two molecular surfaces need to be similar for clinically relevant antibody cross-reactivity to occur is unknown. Here, we describe the grafting of a defined conformational antibody epitope from Bet v 1 onto the surface of the homologous apple...... allergen Malus domestica group 1 (Mal d 1). Engineering of the epitope was accomplished by genetic engineering substituting amino acid residues in Mal d 1 differing between Bet v 1 and Mal d 1 within the epitope defined by the mAb BV16. The kinetic parameters characterizing the antibody binding interaction...

  6. An IgE epitope of Bet v 1 and fagales PR10 proteins as defined by a human monoclonal IgE

    DEFF Research Database (Denmark)

    Hecker, J.; Diethers, A.; Schulz, D.;

    2012-01-01

    formats including IgE. Using variants of Bet v 1, the epitope of the antibody was mapped and extrapolated to other PR10 proteins. RESULTS: The obtained antibodies exhibited pronounced reactivity with Bet v 1, but were not reactive with the homologous PR10 protein Mal d 1. The epitope as defined by the Ig......-reactivities predicted by primary structure analyses of different isoforms and PR10 proteins were verified by allergen chip-based analyses. CONCLUSIONS: The obtained results demonstrate that hybrid IgE repertoires represent a source for human antibodies with genuine paratopes. The IgE-derived information about the Ig......E epitope nature of Bet v 1 and homologues allows for detailed insights into molecular aspects of allergenicity and cross-reactivity within the PR10 protein family....

  7. Fourth Generation Reactor Concepts

    International Nuclear Information System (INIS)

    Concerns over energy resources availability, climate changes and energy supply security suggest an important role for nuclear energy in future energy supplies. So far nuclear energy evolved through three generations and is still evolving into new generation that is now being extensively studied. Nuclear Power Plants are producing 16% of the world's electricity. Today the world is moving towards hydrogen economy. Nuclear technologies can provide energy to dissociate water into oxygen and hydrogen and to production of synthetic fuel from coal gasification. The introduction of breeder reactors would turn nuclear energy from depletable energy supply into an unlimited supply. From the early beginnings of nuclear energy in the 1940s to the present, three generations of nuclear power reactors have been developed: First generation reactors: introduced during the period 1950-1970. Second generation: includes commercial power reactors built during 1970-1990 (PWR, BWR, Candu, Russian RBMK and VVER). Third generation: started being deployed in the 1990s and is composed of Advanced LWR (ALWR), Advanced BWR (ABWR) and Passive AP600 to be deployed in 2010-2030. Future advances of the nuclear technology designs can broaden opportunities for use of nuclear energy. The fourth generation reactors are expected to be deployed by 2030 in time to replace ageing reactors built in the 1970s and 1980s. The new reactors are to be designed with a view of the following objectives: economic competitiveness, enhanced safety, minimal radioactive waste production, proliferation resistance. The Generation IV International Forum (GIF) was established in January 2000 to investigate innovative nuclear energy system concepts. GIF members include Argentina, Brazil, Canada, Euratom, France Japan, South Africa, South Korea, Switzerland, United Kingdom and United States with the IAEA and OECD's NEA as permanent observers. China and Russia are expected to join the GIF initiative. The following six systems

  8. Safety of research reactors

    International Nuclear Information System (INIS)

    The number of research reactors that have been constructed worldwide for civilian applications is about 651. Of the reactors constructed, 284 are currently in operation, 258 are shut down and 109 have been decommissioned. More than half of all operating research reactors worldwide are over thirty years old. During this long period of time national priorities have changed. Facility ageing, if not properly managed, has a natural degrading effect. Many research reactors face concerns with the obsolescence of equipment, lack of experimental programmes, lack of funding for operation and maintenance and loss of expertise through ageing and retirement of the staff. Other reactors of the same vintage maintain effective ageing management programmes, conduct active research programmes, develop and retain high calibre personnel and make important contributions to society. Many countries that operate research reactors neither operate nor plan to operate power reactors. In most of these countries there is a tendency not to create a formal regulatory body. A safety committee, not always independent of the operating organization, may be responsible for regulatory oversight. Even in countries with nuclear power plants, a regulatory regime differing from the one used for the power plants may exist. Concern is therefore focused on one tail of a continuous spectrum of operational performance. The IAEA has been sending missions to review the safety of research reactors in Member States since 1972. Some of the reviews have been conducted pursuant to the IAEA' functions and responsibilities regarding research reactors that are operated within the framework of Project and Supply Agreements between Member States and the IAEA. Other reviews have been conducted upon request. All these reviews are conducted following procedures for Integrated Safety Assessment of Research Reactors (INSARR) missions. The prime objective of these missions has been to conduct a comprehensive operational safety

  9. Electrophysiological and autoradiographical evidence of V1 vasopressin receptors in the lateral septum of the rat brain

    Energy Technology Data Exchange (ETDEWEB)

    Raggenbass, M.; Tribollet, E.; Dreifuss, J.J.

    1987-11-01

    Extracellular recordings were obtained from single neurons located in the lateral septum, an area known to receive a vasopressinergic innervation in the rat brain. Approximately half of the neurons tested responded to 8-L-arginine vasopressin (AVP) by a marked increase in firing rate at concentrations greater than 1 nM. The effect of vasopressin was blocked by synthetic structural analogues possessing antagonistic properties on peripheral vasopressin and oxytocin receptors. Oxytocin was much less potent than vasopressin in firing septal neurons, and a selective oxytocic agonist was totally ineffective. The action of vasopressin on neuronal firing was mimicked by the vasopressor agonist (2-phenylalanine,8-ornithine)vasotocin but not by the selective antidiuretic agonist 1-deamino(8-D-arginine)vasopressin. In a parallel study, sites that bind (/sup 3/H)AVP at low concentration (1.5 nM) were found by in vitro autoradiography in the lateral septum. Adjacent sections were also incubated with 1.5 mM (/sup 3/H)AVP and, in addition, with 100 nM (2-phenylalanine,8-ornithine)vasotocin or 1-deamino(8-D-arginine)vasopressin--i.e., the same compounds as those used for the electrophysiological study. Results showed that the vasopressor agonist, but not the antidiuretic agonist, displaced (/sup 3/H)AVP, thus indicating that the vasopressin binding sites detected by autoradiography in the septum were V1 (vasopressor type) rather than V2 (antidiuretic type) receptors. Based on the electrophysiological evidence, we conclude that these receptors, when occupied, lead to increased firing of lateral septal neurons.

  10. MISTRAL V1.1.1: assessing doses from atmospheric releases in normal and off-normal conditions

    International Nuclear Information System (INIS)

    Protecting the environment and the public from radioactive and chemical hazards has always been a top priority for all companies operating in the nuclear domain. In this scope, SGN provides all the services the nuclear industry needs in environmental studies especially in relation to the impact assessment in normal operating conditions and risk assessment in off-normal conditions. In order to quantify dose impact on members of the public due to atmospheric releases, COGEMA and SGN developed MISTRAL V1.1.1 code. Dose impact depends strongly on dispersion of radionuclides in atmosphere. The main parameters involved in dispersion characterization are wind velocity and direction, rain, diffusion conditions, coordinates of the point of observation and stack elevation. MISTRAL code implements DOURY and PASQUILL Gaussian plume models which are widely used in the scientific community. These models, applicable for distances of transfer ranging from 100 m up to 30 km, are used to calculate atmospheric concentration and deposit at different distances from the point of release. MISTRAL allows the use of different dose regulations or dose coefficient databases such as: - ICRP30 and ICPR71 for internal doses (inhalation, ingestion) - Despres/Kocher database or US-EPA Federal Guidance no.12 (ICPR72 for noble gases) for external exposure (from plume or ground). The initial instant of the release can be considered as the origin of time or a date format can be specified (could be useful in a crisis context). While the context is specified, the user define the meteorological conditions of the release. In normal operating mode (routine releases), the user gives the annual meteorological scheme. The data can be recorded in the MISTRAL meteorological database. In off-normal conditions mode, MISTRAL V1.1 allows the use of successive release stages for which the user gives the duration, the meteorological conditions, that is to say stability class, wind speed and direction and rainfall

  11. MISTRAL V1.1.1: assessing doses from atmospheric releases in normal and off-normal conditions

    Energy Technology Data Exchange (ETDEWEB)

    David Kerouanton [AREVA/SGN/DMI/ECR (France); Patrick Devin [AREVA/COGEMA/D3S/IG (France); Malvina Rennesson [AREVA/COGEMA/BUT/DQSSE (France)

    2006-07-01

    Protecting the environment and the public from radioactive and chemical hazards has always been a top priority for all companies operating in the nuclear domain. In this scope, SGN provides all the services the nuclear industry needs in environmental studies especially in relation to the impact assessment in normal operating conditions and risk assessment in off-normal conditions. In order to quantify dose impact on members of the public due to atmospheric releases, COGEMA and SGN developed MISTRAL V1.1.1 code. Dose impact depends strongly on dispersion of radionuclides in atmosphere. The main parameters involved in dispersion characterization are wind velocity and direction, rain, diffusion conditions, coordinates of the point of observation and stack elevation. MISTRAL code implements DOURY and PASQUILL Gaussian plume models which are widely used in the scientific community. These models, applicable for distances of transfer ranging from 100 m up to 30 km, are used to calculate atmospheric concentration and deposit at different distances from the point of release. MISTRAL allows the use of different dose regulations or dose coefficient databases such as: - ICRP30 and ICPR71 for internal doses (inhalation, ingestion) - Despres/Kocher database or US-EPA Federal Guidance no.12 (ICPR72 for noble gases) for external exposure (from plume or ground). The initial instant of the release can be considered as the origin of time or a date format can be specified (could be useful in a crisis context). While the context is specified, the user define the meteorological conditions of the release. In normal operating mode (routine releases), the user gives the annual meteorological scheme. The data can be recorded in the MISTRAL meteorological database. In off-normal conditions mode, MISTRAL V1.1 allows the use of successive release stages for which the user gives the duration, the meteorological conditions, that is to say stability class, wind speed and direction and rainfall

  12. Reactor Engineering Department annual report

    International Nuclear Information System (INIS)

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1992 (April 1, 1992-March 31, 1993). The major Department's programs promoted in the year are the assessment of the high conversion light water reactor, the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project were also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

  13. Reactor engineering department annual report

    International Nuclear Information System (INIS)

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1989 (April 1, 1989 - March 31, 1990). One of major Department's programs is the assessment of the high conversion light water reactor and the design activities of advanced reactor system. Development of a high energy proton linear accelerator for the nuclear engineering including is also TRU incineration promoted. Other major tasks of the Department are various basic researches on nuclear data and group constants, theoretical methods and code development, on reactor physics experiments and analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics, technology assessment of nuclear energy and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

  14. Intra- and interfamily phenotypic diversity in pain syndromes associated with a gain-of-function variant of NaV1.7

    Directory of Open Access Journals (Sweden)

    Estacion Mark

    2011-12-01

    Full Text Available Abstract Background Sodium channel NaV1.7 is preferentially expressed within dorsal root ganglia (DRG, trigeminal ganglia and sympathetic ganglion neurons and their fine-diamter axons, where it acts as a threshold channel, amplifying stimuli such as generator potentials in nociceptors. Gain-of-function mutations and variants (single amino acid substitutions of NaV1.7 have been linked to three pain syndromes: Inherited Erythromelalgia (IEM, Paroxysmal Extreme Pain Disorder (PEPD, and Small Fiber Neuropathy (SFN. IEM is characterized clinically by burning pain and redness that is usually focused on the distal extremities, precipitated by mild warmth and relieved by cooling, and is caused by mutations that hyperpolarize activation, slow deactivation, and enhance the channel ramp response. PEPD is characterized by perirectal, periocular or perimandibular pain, often triggered by defecation or lower body stimulation, and is caused by mutations that severely impair fast-inactivation. SFN presents a clinical picture dominated by neuropathic pain and autonomic symptoms; gain-of-function variants have been reported to be present in approximately 30% of patients with biopsy-confirmed idiopathic SFN, and functional testing has shown altered fast-inactivation, slow-inactivation or resurgent current. In this paper we describe three patients who house the NaV1.7/I228M variant. Methods We have used clinical assessment of patients, quantitative sensory testing and skin biopsy to study these patients, including two siblings in one family, in whom genomic screening demonstrated the I228M NaV1.7 variant. Electrophysiology (voltage-clamp and current-clamp was used to test functional effects of the variant channel. Results We report three different clinical presentations of the I228M NaV1.7 variant: presentation with severe facial pain, presentation with distal (feet, hands pain, and presentation with scalp discomfort in three patients housing this NaV1.7 variant

  15. Frequent occurrence of T cell–mediated late reactions revealed by atopy patch testing with hypoallergenic rBet v 1 fragments

    OpenAIRE

    Campana, Raffaela; Moritz, Katharina; Marth, Katharina; Neubauer, Angela; Huber, Hans; Henning, Rainer; Blatt, Katharina; Hoermann, Gregor; Brodie, Tess M.; Kaider, Alexandra; Valent, Peter; Sallusto, Federica; Wöhrl, Stefan; Valenta, Rudolf

    2015-01-01

    Background Late allergic reactions are common in the course of allergen-specific immunotherapy and even occur with allergy vaccines with reduced IgE reactivity. Objective We sought to study atopy patch test (APT) reactions and T-cell responses to the recombinant birch pollen allergen Bet v 1 and recombinant hypoallergenic T-cell epitope–containing Bet v 1 fragments in patients with birch pollen allergy with and without atopic dermatitis (AD). Methods A clinical study was conducted in 15 patie...

  16. Slurry reactor design studies

    Energy Technology Data Exchange (ETDEWEB)

    Fox, J.M.; Degen, B.D.; Cady, G.; Deslate, F.D.; Summers, R.L. (Bechtel Group, Inc., San Francisco, CA (USA)); Akgerman, A. (Texas A and M Univ., College Station, TX (USA)); Smith, J.M. (California Univ., Davis, CA (USA))

    1990-06-01

    The objective of these studies was to perform a realistic evaluation of the relative costs of tublar-fixed-bed and slurry reactors for methanol, mixed alcohols and Fischer-Tropsch syntheses under conditions where they would realistically be expected to operate. The slurry Fischer-Tropsch reactor was, therefore, operated at low H{sub 2}/CO ratio on gas directly from a Shell gasifier. The fixed-bed reactor was operated on 2.0 H{sub 2}/CO ratio gas after adjustment by shift and CO{sub 2} removal. Every attempt was made to give each reactor the benefit of its optimum design condition and correlations were developed to extend the models beyond the range of the experimental pilot plant data. For the methanol design, comparisons were made for a recycle plant with high methanol yield, this being the standard design condition. It is recognized that this is not necessarily the optimum application for the slurry reactor, which is being proposed for a once-through operation, coproducing methanol and power. Consideration is also given to the applicability of the slurry reactor to mixed alcohols, based on conditions provided by Lurgi for an Octamix{trademark} plant using their standard tubular-fixed reactor technology. 7 figs., 26 tabs.

  17. FBR type reactor

    International Nuclear Information System (INIS)

    The present invention provides an FBR type reactor in which the combustion of reactor core fuels is controlled by reflectors, and the position of a reflector driving device can be controlled even during shut down of the reactor. Namely, the reflector driving device is attracted to the outer wall surface of a reactor core barrel by electromagnetic attraction force. An inertia body is disposed vertically movably to the upper portion of the reflector driving device. Magnetic repulsive coils generate instantaneous magnetic repulsive force between the inertia body and the reflector driving device. With such a constitution, the reflector driving device can be driven by using magnetic repulsion of the electromagnetic repulsive coils and inertia of the inertia body. As a result, not only the reflectors can be elevated at an ultraslow speed during normal reactor operation, but also fine position adjustment for the reflector driving device, as well as fine position adjustment of the reflectors required upon restart of the reactor can be conducted by lowering the reflector driving device during shut down of the reactor. (I.S.)

  18. Reactor water sampling device

    International Nuclear Information System (INIS)

    The present invention concerns a reactor water sampling device for sampling reactor water in an in-core monitor (neutron measuring tube) housing in a BWR type reactor. The upper end portion of a drain pipe of the reactor water sampling device is attached detachably to an in-core monitor flange. A push-up rod is inserted in the drain pipe vertically movably. A sampling vessel and a vacuum pump are connected to the lower end of the drain pipe. A vacuum pump is operated to depressurize the inside of the device and move the push-up rod upwardly. Reactor water in the in-core monitor housing flows between the drain pipe and the push-up rod and flows into the sampling vessel. With such a constitution, reactor water in the in-core monitor housing can be sampled rapidly with neither opening the lid of the reactor pressure vessel nor being in contact with air. Accordingly, operator's exposure dose can be reduced. (I.N.)

  19. Test reactor technology

    International Nuclear Information System (INIS)

    The Reactor Development Program created a need for engineering testing of fuels and materials. The Engineering Test Reactors were developed around the world in response to this demand. The design of the test reactors proved to be different from that of power reactors, carrying the fuel elements closer to the threshold of failure, requiring more responsive instrumentation, more rapid control element action, and inherent self-limiting behavior under accident conditions. The design of the experimental facilities to exploit these reactors evolved a new, specialized, branch of engineering, requiring a very high-lvel scientific and engineering team, established a meticulous concern with reliability, the provision for recovery from their own failures, and detailed attention to possible interactions with the test reactors. This paper presents this technology commencing with the Materials Testing Reactor (MTR) through the Fast Flux Test Facility, some of the unique experimental facilities developed to exploit them, but discusses only cursorily the experiments performed, since sample preparation and sample analyses were, and to some extent still are, either classified or proprietary. The Nuclear Engineering literature is filled with this information

  20. Advanced reactor licensing issues

    International Nuclear Information System (INIS)

    In July 1986 the US Nuclear Regulatory Commission issued a Policy Statement on the Regulation of Advanced Nuclear Power Plants. As part of this policy advanced reactor designers were encouraged to interact with NRC early in the design process to obtain feedback regarding licensing requirements for advanced reactors. Accordingly, the staff has been interacting with the Department of Energy (DOE) and its contractors on the review of three advanced reactor conceptual designs: one modular High Temperature Gas-Cooled Reactor (MHTGR) and two Liquid Metal Reactors (LMRs). As a result of these interactions certain safety issues associated with these advanced reactor designs have been identified as key to the licensability of the designs as proposed by DOE. The major issues in this regard are: (1) selection and treatment of accident scenarios; (2) selection of siting source term; (3) performance and reliability of reactor shutdown and decay heat removal systems; (4) need for conventional containment; (5) need for conventional emergency evacuation; (6) role of the operator; (7) treatment of balance of plant; and (8) modular approach. This paper provides a status of the NRC review effort, describes the above issues in more detail and provides the current status and approach to the development of licensing guidance on each