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Sample records for rs ophiuchi thermonuclear

  1. RS Ophiuchi: The Gift that Keeps on Giving

    Science.gov (United States)

    Starrfield, S.

    2008-12-01

    RS Oph experienced its sixth recorded outburst in 2006 and was observed in virtually every wavelength region from hard X-rays to the radio. Each observation, especially those with instruments that have come online since its last outburst in 1985, provided new and exciting information about the explosion. As a result, some of us organized a second workshop on the RS Oph outburst and it was held in June 2007 at Keele University. I gave the lead off talk in which I presented a number of questions to be discussed during the workshop, a brief summary of what had been discovered in previous outbursts concentrating on the ultraviolet studies with IUE, and a few observations of the 2006 outburst concentrating on the results from Swift and HST.

  2. Intense soft x-rays from RS Ophiuchi during the 1985 outburst

    International Nuclear Information System (INIS)

    Mason, K.O.; Cordova, F.A.; Bode, M.F.; Barr, P.

    1985-01-01

    Intense soft x-ray emission with a characteristic temperature of a few million degrees has been detected from the recurrent nova RS Oph approximately two months after its January 1985 optical outburst. This is the first detection of x-rays from such a system at outburst. The x-radiation is interpreted as emission from circumstellar gas that is shock heated by the passage of the blast wave from the nova explosion. The rapid decline of the x-ray flux between about 60 and 90 days after the outburst probably occurs because the blast wave has reached the edge of the volume filled, between outbursts, by the stellar wind of the red giant component of the binary system. Residual x-ray emission detected from RS Oph 250 days after the outburst is interpreted as coming from the surface of a white dwarf, at a temperature of approx.300,000K, where thermonuclear burning is persisting. 7 refs., 3 figs

  3. The Massive CO White Dwarf in the Symbiotic Recurrent Nova RS Ophiuchi

    Science.gov (United States)

    Mikołajewska, Joanna; Shara, Michael M.

    2017-10-01

    If accreting white dwarfs (WDs) in binary systems are to produce type Ia supernovae (SNe Ia), they must grow to nearly the Chandrasekhar mass and ignite carbon burning. Proving conclusively that a WD has grown substantially since its birth is a challenging task. Slow accretion of hydrogen inevitably leads to the erosion, rather than the growth of WDs. Rapid hydrogen accretion does lead to growth of a helium layer, due to both decreased degeneracy and the inhibition of mixing of the accreted hydrogen with the underlying WD. However, until recently, simulations of helium-accreting WDs all claimed to show the explosive ejection of a helium envelope once it exceeded ˜ {10}-1 {M}⊙ . Because CO WDs cannot be born with masses in excess of ˜ 1.1 {M}⊙ , any such object in excess of ˜ 1.2 {M}⊙ must have grown substantially. We demonstrate that the WD in the symbiotic nova RS Oph is in the mass range 1.2-1.4 M ⊙. We compare UV spectra of RS Oph with those of novae with ONe WDs and with novae erupting on CO WDs. The RS Oph WD is clearly made of CO, demonstrating that it has grown substantially since birth. It is a prime candidate to eventually produce an SN Ia.

  4. Theoretical light curve for the recurrent nova RS Ophiuchi - Determination of the white dwarf mass, composition, and distance

    International Nuclear Information System (INIS)

    Kato, M.

    1991-01-01

    Sequences of steady mass-loss solutions are constructed for the envelopes on a white dwarf with mass 1.33, 1.35, 1.36, 1.37, and 1.377 solar mass as models of the decay phase of novae. The envelopes are assumed to have a uniform chemical composition with X = 0.73, 0.6, 0.52, 0.44, 0.33, and 0.11 for hydrogen and Z = 0.02 for heavy elements by weight. An excellent agreement with the observed light curves of UV and optical is obtained in the models with a white dwarf mass of 1.36 solar mass with hydrogen content X = 0.52, and 1.37 solar mass with X = 0.6. The distance of RS Oph is obtained to be 1.6 kpc from the comparison between the theoretical and observed light curves. The success of this wind model is a strong indication from the theoretical point of view that RS Oph is a thermonuclear runaway event. 31 refs

  5. THE EXPANDING NEBULAR REMNANT OF THE RECURRENT NOVA RS OPHIUCHI (2006). II. MODELING OF COMBINED HUBBLE SPACE TELESCOPE IMAGING AND GROUND-BASED SPECTROSCOPY

    International Nuclear Information System (INIS)

    Ribeiro, V. A. R. M.; Bode, M. F.; Darnley, M. J.

    2009-01-01

    We report Hubble Space Telescope (HST) imaging, obtained 155 and 449 days after the 2006 outburst of the recurrent nova RS Ophiuchi, together with ground-based spectroscopic observations, obtained from the Observatorio Astronomico Nacional en San Pedro Martir, Baja California, Mexico and at the Observatorio AstrofIsico Guillermo Haro, at Cananea, Sonora, Mexico. The observations at the first epoch were used as inputs to model the geometry and kinematic structure of the evolving RS Oph nebular remnant. We find that the modeled remnant comprises two distinct co-aligned bipolar components; a low-velocity, high-density innermost (hour glass) region and a more extended, high-velocity (dumbbell) structure. This overall structure is in agreement with that deduced from radio observations and optical interferometry at earlier epochs. We find that the asymmetry observed in the west lobe is an instrumental effect caused by the profile of the HST filter and hence demonstrate that this lobe is approaching the observer. We then conclude that the system has an inclination to the line of sight of 39 +10 -10 . This is in agreement with the inclination of the binary orbit and lends support to the proposal that this morphology is due to the interaction of the outburst ejecta with either an accretion disk around the central white dwarf and/or a pre-existing red giant wind that is significantly denser in the equatorial regions of the binary than at the poles. The second epoch HST observation was also modeled. However, as no spectra were taken at this epoch, it is more difficult to constrain any model. Nevertheless, we demonstrate that between the two HST epochs the outer dumbbell structure seems to have expanded linearly. For the central (hour glass) region, there may be evidence of deceleration, but it is harder to draw firm conclusions in this case.

  6. Thermonuclear detonation

    International Nuclear Information System (INIS)

    Feoktistov, L.P.

    1998-01-01

    The characteristics of, and energy transfer mechanisms involved in, thermonuclear detonation are discussed. What makes the fundamental difference between thermonuclear and chemical detonation is that the former has a high specific energy release and can therefore be employed for preliminary compressing the thermonuclear mixture ahead of the burning wave. Consequently, with moderate (mega joule) initiation energies, a steady-state detonation laboratory experiment with unlimited energy multiplication becomes a possibility

  7. Thermonuclear detonation

    International Nuclear Information System (INIS)

    Feoktistov, L P

    1998-01-01

    The characteristics of, and energy transfer mechanisms involved in, thermonuclear detonation are discussed. What makes the fundamental difference between thermonuclear and chemical detonation is that the former has a high specific energy release and can therefore be employed for preliminarily compressing the thermonuclear mixture ahead of the burning wave. Consequently, with moderate (megajoule) initiation energies, a steady-state detonation laboratory experiment with unlimited energy multiplication becomes a possibility. (from the history of physics)

  8. Thermonuclear device

    International Nuclear Information System (INIS)

    Yagi, Yasuomi; Takahashi, Ken; Hashimoto, Hiroshi.

    1984-01-01

    Purpose: To improve the plasma confining performances by bringing the irregular magnetic fields nearly to zero and decreasing the absolute value of the irregular magnetic fields at every positions. Constitution: The winding direction of a plurality of coil elements, for instance, double pan cake coils of toroidal coils in a torus type or mirror type thermonuclear device are reversed to each other in their laminating direction, whereby the irregular magnetic fields due to the coil-stepped portions in each toroidal coils are brought nearly to zero. This enables to bring the average irregular magnetic fields as a whole in the thermonuclear device nearly to zero, as well as, decrease the absolute value of the irregular magnetic fields in each positions. Thus, the plasma confining performances can be improved. (Moriyama, K.)

  9. Thermonuclear astrophysics

    International Nuclear Information System (INIS)

    Clayton, D.D.; Woosley, S.E.

    1974-01-01

    We discuss the types of thermonuclear reactions that are of importance to stellar evolution and nucleosynthesis, with particular attention to the explosive ejection of shells of He, C, O, and Si. We present tables of the reactions important in the various burning phases, including the reason for their importance and an estimate of the value of a carefully measured rate. This format is chosen for dual purpose: (1) to clarify the nuclear needs by evaluating the importance of specific reactions within the astronomical settings and (2) by assigning a value scale for cross-section measurements

  10. Thermonuclear device

    International Nuclear Information System (INIS)

    Inoue, Toyokazu; Murata, Toru.

    1983-01-01

    Purpose: To shield superconducting coils for use in the generation of magnetic field against neutron irradiation thereby preventing tritium contamination. Constitution: The thermonuclear device comprises, in its inside, a vacuum container for containing plasmas, superconducting coils disposed to the outside of the vacuum container and neutron absorbers disposed between the super-conducting coils and the vacuum container. since neutrons issued from the plasma are absorbed by neutron absorbers and not irradiated to the superconducting coils, generation of tritium due to the reaction between 3 He in the liquid helium as the coolants for the super-conducting coils and the neutrons is prevented. (Aizawa, K.)

  11. Rho Ophiuchi Cloud Core Extinction Map

    Science.gov (United States)

    Gibson, D. J.; Rudolph, A.; Barsony, M.

    1997-12-01

    We present an extinction map of a one square degree region ( ~ 2.2pc square) of the core of the star-forming region rho Ophiuchi derived by the method of star counts. Photometry from the near-infrared J, H, and K band images of Barsony et al. (1997) provided the stellar catalog for this study. From this map an estimate of the mass of the region is made and compared with previous estimates from other methods. Reference Barsony, M., Kenyon, S.J., Lada, E.A., & Teuben, P.J. 1997, ApJS, 112, 109

  12. Thermonuclear fusion

    International Nuclear Information System (INIS)

    Weisse, J.

    2000-01-01

    This document takes stock of the two ways of thermonuclear fusion research explored today: magnetic confinement fusion and inertial confinement fusion. The basic physical principles are recalled first: fundamental nuclear reactions, high temperatures, elementary properties of plasmas, ignition criterion, magnetic confinement (charged particle in a uniform magnetic field, confinement and Tokamak principle, heating of magnetized plasmas (ohmic, neutral particles, high frequency waves, other heating means), results obtained so far (scale laws and extrapolation of performances, tritium experiments, ITER project), inertial fusion (hot spot ignition, instabilities, results (Centurion-Halite program, laser experiments). The second part presents the fusion reactor and its associated technologies: principle (tritium production, heat source, neutron protection, tritium generation, materials), magnetic fusion (superconducting magnets, divertor (role, principle, realization), inertial fusion (energy vector, laser adaptation, particle beams, reaction chamber, stresses, chamber concepts (dry and wet walls, liquid walls), targets (fabrication, injection and pointing)). The third chapter concerns the socio-economic aspects of thermonuclear fusion: safety (normal operation and accidents, wastes), costs (costs structure and elementary comparison, ecological impact and external costs). (J.S.)

  13. Thermonuclear device

    International Nuclear Information System (INIS)

    Tezuka, Masaru.

    1993-01-01

    Protrusions and recesses are formed to a vacuum vessel and toroidal magnetic coils, and they are engaged. Since the vacuum vessel is generally supported firmly by a rack or the like by support legs, the toroidal magnetic field coils can be certainly supported against tumbling force. Then, there can be attained strong supports for the toroidal magnetic field coils, in addition to support by wedges on the side of inboard and support by share panels on the side of outboard, capable of withstanding great electromagnetic forces which may occur in large-scaled next-generation devices. That is, toroidal magnetic field coils excellent from a view point of deformation and stress can be obtained, to provide a thermonuclear device of higher reliability. (N.H.)

  14. Thermonuclear device

    International Nuclear Information System (INIS)

    Kajiura, Soji.

    1984-01-01

    Purpose: To suppress the generation of electromagnetic forces and improve the strength of a vacuum container for sealing plasmas and of a support frame for covering the coils disposed around the periphery of the vacuum container. Constitution: Either one of the vacuum container or the support frame is made of a composite material, whose first material has low radioactivatability and the second has low radioactivatability and stronger electrical resistance than that of the first; therein, with the first material being disposed on the surface. The damage caused by neutrons resulted from thermonuclear reaction can be extremely small since the constituent is made of the material having the low radioactivatability. Further, eddy current does not occurs in the second material, but in the first material only in case magnetic fields change rapidly, whereby the electromagnetic force resulted in this portion is decreased as a whole. (Moriyama, K.)

  15. Thermonuclear device

    International Nuclear Information System (INIS)

    Oosaki, Osamu; Masuda, Kenju.

    1980-01-01

    Purpose: To provide excellent electric properties and high reliability in a thermonuclear device by improving a current collecting board connected to a coil device. Constitution: A current collecting board element perforated with an opening for enserting a connecting terminal is sized to be inserted into a plating tank, and is surface treated in the plating tank. Only the current collecting board element preferably surface treated is picked up. A plurality of such current collecting board elements are connected and welded to form a large current collecting board. In this manner, the current collecting board having several m 2 to several ten order m 2 in area can be obtained as preferably surface treated at the connecting terminal hole. The current collecting board element can be determined in shape with the existing facility without increasing the size of a surface treating tank. (Kamimura, M.)

  16. Thermonuclear device

    International Nuclear Information System (INIS)

    Suzuki, Shohei

    1988-01-01

    Purpose: To obtain high voltage withstanding current introduction terminals not suffering from the effects of the reduction in the creeping voltage withstanding property by the application of magnetic fields. Constitution: This invention concerns a current introduction terminal for supplying electric current to coils for use in a thermonuclear device, etc. The conductor of the current introduction terminal on the side of vacuum is completely covered with solid insulator. This can eliminate the portion of securing the creeping withstanding voltage. The voltage withstanding characteristics of the solid insulator covering the portion of the conductor on the side of vacuum has a constant value irrespective of the atmosphere or the absence or presence of magnetic fields. Accordingly, the voltage withstanding characteristics of the current introduction terminal on the side of vacuum are determined by the property of the solid insulator, which is not reduced by the application of magnetic fields. (Ikeda, J.)

  17. Thermonuclear reactor

    International Nuclear Information System (INIS)

    Yasutomi, Yoshiyuki; Nakagawa, Moroo; Sawai, Yuichi; Chiba, Akio; Suzuki, Yasutaka.

    1997-01-01

    Silicon composited with reinforcing metals is used for a divertor cooling substrate having an effect as a cooling tube to provide a silicon base composite material having increased electric resistance and toughness. The blending ratio of reinforcing materials in the form of granules, whiskers or long fibers is controlled in order to control heat conductivity, electric resistivity and mechanical performances. The divertor cooling substrate comprising the silicon base composite material is integrated with a plasma facing material. The production method therefor includes ordinary metal matrix composite forming methods such as powder metallurgy, melting penetration method, high pressure solidification casting method, centrifugal casting method and vacuum casting method. Since the cooling plate is constituted with the light metal and highly electric resistant metal base composite material, sharing force due to eddy current can be reduced, and radiation exposure can be minimized. Accordingly, a cooling structure for a thermonuclear reactor effective for the improvement of environmental problems caused by waste disposal can be attained. (N.H.)

  18. Thermonuclear device

    International Nuclear Information System (INIS)

    Suzuki, Shohei.

    1980-01-01

    Purpose: To improve the plasma confining efficiency in a thermonuclear device having magnet coils using super-conducting wires by decreasing the uneven magnetic field resulted from current supply terminals and wirings. Constitution: Current introduction terminals of magnet coils using superconducting wires are short circuitted with a superconducting short circuit wire. Upon supplying current to the coils, the resistance of the coils is rendered superconductive and the resistance of the short circuit wire is rendered normally conductive heated by a heater and the switch is closed. In this case, most parts of the current are flown through the resistance of the coils and the switch is opened when the current arrives at a predetermined value to render the resistance of the short circuit wire superconductive. Then, the current transfers from the thyristor power source to the resistance of the short circuit wire, whereby the resistance of the coils and that of the short circuit wire from a permanent current loop. In this conditions, since current flows through the short circuit wire and the coils and not to the current introduction terminals, no uniform magnetic field is generated. (Kawakami, Y.)

  19. Thermonuclear device

    International Nuclear Information System (INIS)

    Honda, Takuro; Maki, Koichi.

    1997-01-01

    The present invention provides a thermonuclear device, in which integrity of a measuring device is kept, the reactor wall temperature and wear of armour materials are monitored accurately even under intense radiation rays, so that the flow rate of coolants and plasma power can be controlled by using the signals. Infrared rays generated from the surface of the armour materials disposed on a first wall are detected to measure the reactor wall temperature. Coolant flow rate and plasma power are controlled based on the obtained reactor wall temperature. In addition, infrared rays generated from the back of the armour materials are detected to obtain the surface temperature in order to avoid intense radiation rays from plasmas. The coolant flow rate and the plasma power are controlled based on the obtained temperature on the surface of the reactor thereby controlling the temperature of the first wall and the armour material to 300degC or lower in a case of the first wall made of stainless steel and 1000degC or lower in a case of the armour material made of graphite. (I.S.)

  20. Thermonuclear device

    International Nuclear Information System (INIS)

    Takano, Hirohisa; Nakamoto, Kazunari; Hanai, Satoshi.

    1984-01-01

    Purpose: To provide coils of high mechanical strength for use at the center of a torus type thermonuclear device. Constitution: A plurality of copper plates having cooling holes and bolt holes and insulation paper sheets of the same shape are prepared. The copper plate is different from the insulation paper sheet only in that the position-phase angle of the opening portion is larger by 15 - 30 0 . The copper plates and the insulation paper sheets are alternately stacked by a required number of turns while displacing the angle, and then clamped by bolts to form a mechanically strong coil with no metallurgical joining. Further, since the insulation paper sheets are not present in the radial direction and only one insulation paper sheet is inserted for each turn in the direction of the coil height, the space occupied by the coil can be decreased. According to this invention, the magnetic flux density at the center of the device can be increased as compared with the conventional case to thereby apply a higher voltage on the side of plasmas. (Moriyama, K.)

  1. Controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    Rebut, P.H.

    1992-01-01

    The author gives a chronological account of the research about thermonuclear fusion and presents the principle of JET thermonuclear reactor based upon the magnetic confinement. The problems of heating and confining a thermonuclear plasma may be regarded as solved. They make possible the definition of the size and geometry needed to realize a next-step tokamak (ITER, NET projects)

  2. Relative Proper Motions in the Rho Ophiuchi Cluster

    Science.gov (United States)

    2016-01-06

    identified as YSOs and may be newly identified cluster members. Key words: ISM: individual objects (Rho Ophiuchi cloud) – stars: formation – stars: pre-main...sequence 1. INTRODUCTION The majority of stars in the Galaxy form in clusters that once the binding mass of the molecular gas is removed, disperse into

  3. Asteroseismic observations and modelling of 70 Ophiuchi AB

    Energy Technology Data Exchange (ETDEWEB)

    Eggenberger, P; Miglio, A [Institut d' Astrophysique et de Geophysique de l' Universite de Liege, 17 Allee du 6 Aout, B-4000 Liege (Belgium); Carrier, F [Institute of Astronomy, University of Leuven, Celestijnenlaan 200 D, B-3001 Leuven (Belgium); Fernandes, J [Observatorio Astronomico da Universidade de Coimbra e Departamento de Matematica, FCTUC (Portugal); Santos, N C [Centro de AstrofIsica, Universidade do Porto, Rua das Estrelas, P-4150-762 Porto (Portugal)], E-mail: eggenberger@astro.ulg.ac.be

    2008-10-15

    The analysis of solar-like oscillations for stars belonging to a binary system provides an opportunity to probe the internal stellar structure and to test our knowledge of stellar physics. We present asteroseismic observations of 70 Oph A performed with the HARPS spectrograph together with a comprehensive theoretical calibration of the 70 Ophiuchi system.

  4. Controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    Sakanaka, P.H.

    1984-01-01

    A simplified review on the status of the controlled thermonuclear fusion research aiming to present the motivation, objective, necessary conditions and adopted methods to reach the objective. (M.C.K.) [pt

  5. Thermonuclear research development

    International Nuclear Information System (INIS)

    Velikhov, E.

    1977-01-01

    Tokamak 10, the world's largest thermonuclear facility was commissioned in 1975. Soviet scientists thus achieved enormous success in producing high-temperature plasma and constructing a thermonuclear fusion source. The problems which remain to be solved include finding a method of regenerating the deuterium-tritium fuel mixture and a method of purifying the reacting high-temperature plasma of heavy elements. The project is designed for a more powerful facility, namely the Tokamak 20 whose toroidal chamber will accommodate a current of 5 to 6 MA and whose plasma volume will be 400 m 3 . (Oy)

  6. Thermonuclear research development

    Energy Technology Data Exchange (ETDEWEB)

    Velikhov, E

    1977-04-01

    Tokamak 10, the world's largest thermonuclear facility was commissioned in 1975. Soviet scientists thus achieved enormous success in producing high-temperature plasma and constructing a thermonuclear fusion source. The problems which remain to be solved include finding a method of regenerating the deuterium-tritium fuel mixture and a method of purifying the reacting high-temperature plasma of heavy elements. The project is designed for a more powerful facility, namely the Tokamak 20 whose toroidal chamber will accommodate a current of 5 to 6 MA and whose plasma volume will be 400 m/sup 3/.

  7. Thermonuclear reaction rates. III

    International Nuclear Information System (INIS)

    Harris, M.J.; Fowler, W.A.; Caughlan, G.R.; Zimmerman, B.A.

    1983-01-01

    Stellar thermonuclear reaction rates are revised and updated, adding a number of new important reaction rates. Several reactions with large negative Q-values are included, and examples of them are discussed. The importance of the decay rates for Mg-26(p,n) exp 26 Al and Al-26(n,p) exp 26 Mg for stellar studies is emphasized. 19 references

  8. Controlled thermonuclear fusion

    CERN Document Server

    Bobin, Jean Louis

    2014-01-01

    The book is a presentation of the basic principles and main achievements in the field of nuclear fusion. It encompasses both magnetic and inertial confinements plus a few exotic mechanisms for nuclear fusion. The state-of-the-art regarding thermonuclear reactions, hot plasmas, tokamaks, laser-driven compression and future reactors is given.

  9. Resonant thermonuclear reaction rate

    International Nuclear Information System (INIS)

    Haubold, H.J.; Mathai, A.M.

    1986-01-01

    Basic physical principles for the resonant and nonresonant thermonuclear reaction rates are applied to find their standard representations for nuclear astrophysics. Closed-form representations for the resonant reaction rate are derived in terms of Meijer's G-function. Analytic representations of the resonant and nonresonant nuclear reaction rates are compared and the appearance of Meijer's G-function is discussed in physical terms

  10. Thermonuclear land of plenty

    Science.gov (United States)

    Gasior, P.

    2014-11-01

    Since the process of energy production in the stars has been identified as the thermonuclear fusion, this mechanism has been proclaimed as a future, extremely modern, reliable and safe for sustaining energetic needs of the humankind. However, the idea itself was rather straightforward and the first attempts to harness thermonuclear reactions have been taken yet in 40s of the twentieth century, it quickly appeared that physical and technical problems of domesticating exotic high temperature medium known as plasma are far from being trivial. Though technical developments as lasers, superconductors or advanced semiconductor electronics and computers gave significant contribution for the development of the thermonuclear fusion reactors, for a very long time their efficient performance was out of reach of technology. Years of the scientific progress brought the conclusions that for the development of the thermonuclear power plants an enormous interdisciplinary effort is needed in many fields of science covering not only plasma physics but also material research, superconductors, lasers, advanced diagnostic systems (e.g. spectroscopy, interferometry, scattering techniques, etc.) with huge amounts of data to be processed, cryogenics, measurement-control systems, automatics, robotics, nanotechnology, etc. Due to the sophistication of the problems with plasma control and plasma material interactions only such a combination of the research effort can give a positive output which can assure the energy needs of our civilization. In this paper the problems of thermonuclear technology are briefly outlined and it is shown why this domain can be a broad field for the experts dealing with electronics, optoelectronics, programming and numerical simulations, who at first glance can have nothing common with the plasma or nuclear physics.

  11. Controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    Trocheris, M.

    1975-01-01

    An outline is given of the present position of research into controlled fusion. After a brief reminder of the nuclear reactions of fusion and the principle of their use as a source of energy, the results obtained by the method of magnetic confinement are summarized. Among the many solutions that have been imagined and tried out to achieve a magnetic containing vessel capable of holding the thermonuclear plasma, the devices of the Tokamak type have a good lead and that is why they are described in greater detail. An idea is then given of the problems that arise when one intends conceiving the thermonuclear reactor based on the principle of the Tokamaks. The last section deals with fusion by lasers which is a new and most attractive alternative, at least from the viewpoint of basis physics. The report concludes with an indication of the stages to be passed through to reach production of energy on an industrial scale [fr

  12. Blankets for thermonuclear device

    International Nuclear Information System (INIS)

    Maki, Koichi; Fukumoto, Hideshi.

    1986-01-01

    Purpose: To produce tritium more than consumed, through thermonuclear reaction. Constitution: The energy spectrum of neutron generated by neutron multiplying reaction in a neutron multiplying blanket and moderated neutrons has a large ratio in a low energy section. In the low-energy absorption region of stainless steel which is a material of cooling pipes constituting a neutron multiplying blanket cooling channel, the neutrons are absorbed, lessening the neutron multiplying effect. To prevent this, the neutron multiplying blanket cooling channel is covered with tritium breeding blankets, thereby enabling the production of a substantially great amount of tritium more than the amount of tritium to be consumed by the thermonuclear reaction by preventing neutron absorption by the component materials of the cooling channel, improving the tritium breeding ratio by 20 to 25 %, and increasing the efficiency of use of neutrons for tritium generation. (Horiuchi, T.)

  13. Research into thermonuclear fusion

    International Nuclear Information System (INIS)

    Schumacher, U.

    1989-01-01

    The experimental and theoretical studies carried out in close international cooperation in the field of thermonuclear fusion by magnetic plasma confinement have achieved such progress towards higher plasma temperatures and densities, longer confinement times and, thus, increased fusion product, that emphasis now begins to be shifted from problems of physics to those of technology as a next major step is being prepared towards a large international project (ITER) to achieve thermonuclear burning. The generation and maintenance of a burning fusion plasma in an experimental physics phase will be followed by a phase of technical materials studies at high fluxes of fusion neutrons. These goals have been pursued since 1983 by an international study group at Garching working on the design of a Next European Torus (NET). Since May 1988, an international study group comprising ten experts each from the USSR, USA, Japan, and the European Community has begun to work on a design draft of ITER (International Thermonuclear Experimental Reactor) in Garching under the auspices of IAEA. (orig.) [de

  14. Thermonuclear Runaway model

    International Nuclear Information System (INIS)

    Sparks, W.M.; Kutter, G.S.; Starrfield, S.; Truran, J.W.

    1989-01-01

    The nova outburst requires an energy source that is energetic enough to eject material and is able to recur. The Thermonuclear Runaway (TNR) model, coupled with the binary nature of nova systems satisfies these conditions. The white dwarf/red dwarf binary nature of novae was first recognized as a necessary conditions by Kraft. The small separation characteristic of novae systems allows the cool, red secondary to overflow is Roche lobe. In the absence of strong, funneling magnetic fields, the angular momentum of this material prevents it from falling directly onto the primary, and it first forms a disk around the white dwarf. This material is eventually accreted from the disk onto the white dwarf. As the thickness of this hydrogen-rich layer increases, the degenerate matter at the base reaches a temperature that is high enough to initiate thermonuclear fusion of hydrogen. Thermonuclear energy release increases the temperature which in turn increases the energy generation rate. Because the material is degenerate, the pressure does not increase with temperature, which normally allows a star to adjust itself to a steady nuclear burning rate. Thus the temperature and nuclear energy generation increase and a TNR results. When the temperature reaches the Fermi temperature, degeneracy is lifted and the rapid pressure increase causes material expansion. The hydrogen-rich material either is ejected or consumed by nuclear burning, and the white dwarf returns to its pre-outburst state. The external source of hydrogen fuel from the secondary allows the while process to repeat. 43 refs., 8 figs

  15. The laser thermonuclear fusion

    International Nuclear Information System (INIS)

    Coutant, J.; Dautray, R.; Decroisette, M.; Watteau, J.P.

    1987-01-01

    Principle of the thermonuclear fusion by inertial confinement: required characteristics of the deuterium-tritium plasma and of the high power lasers to be used Development of high power lasers: active media used; amplifiers; frequency conversion; beam quality; pulse conditioning; existing large systems. The laser-matter interaction: collision and collective interaction of the laser radiation with matter; transport of the absorbed energy; heating and compression of deuterium-tritium; diagnoses and their comparison with the numerical simulation of the experiment; performances. Conclusions: difficulties to overcome; megajoule lasers; other energy source: particles beams [fr

  16. Thermonuclear reaction listing

    International Nuclear Information System (INIS)

    Fukai, Yuzo

    1993-01-01

    The following 10 elements, including T, are well known as nuclear fusion fuels: p, D, T, 3 He, 4 He, 6 Li, 7 Li, 9 Be, 10 B, 11 B, ( 12 C, 13 C), where 12 C and 13 C are considered only in the calculation of Q value. Accordingly the number of the thermonuclear reactions is 55, and 78, if including carbon elements. The reactions have some branches. For the branches having two and three reaction products, the reaction products, Q value and threshold energy are calculated by using a computer. We have investigated those of the branches having more than three products from the papers of Ajzenberg-Selove and so on. And also, by the same papers, we check whether the above mentioned branch has been observed or not. The results are as follows: (I) the number of reactions which have Q 0 branches only with γ ray production, and Q 0 and neutron production is 36(17), and (IV) that of reactions whose branch with Q > 0 does not produce neutrons is 9(3). The value in the parentheses shows the number of the case of the carbon elements. For 55 thermonuclear reactions induced by lighter nuclides than 11 B, the reaction products, the values of Q and threshold energy, and the papers with reaction cross section data are presented in the tables. (author)

  17. Thermonuclear investigation development

    International Nuclear Information System (INIS)

    Pistunovich, V.I.; Solov'ev, N.S.

    1975-01-01

    The patent situation, based mainly on a study of the situations of Great Britain, USA, France, Federal Republic of Germany and Japan from 1958 to 1974 is reviewed. Applicants have obtained around 300 patents on equipment for control of thermonuclear reactions. In the second half some decrease in the introduction of patents on high-temperature-plasma studies is noted. Multipole magnet systems for holding plasma and toroidal equipment of the takamak type have been developed recently. In the 70s, patents were published on the use of high-energy electrons for stabilization and heating of plasma in toroidal stationary systems. Starting with the mid 60s, considerable attention has been given to heating of plasma with laser radiation and to conversion of thermonuclear energy to electrical. There are 20 domestic patents on laser heating of plasma, and 75 and 45 domestic patents, respectively, on open and composite traps and 120 and 40 such patents abroad. While in the 60s equipment of different types was patented in many directions, part of which has not found further use, today work abroad is being patented basically on laser heating of plasma, toroidal magnetic systems, ion beam interference, and plasma bunching

  18. Inertia thermonuclear device

    International Nuclear Information System (INIS)

    Madarame, Haruki; Nakamura, Norio; Oomura, Hiroshi.

    1983-01-01

    Purpose: To enable effective recovery of the thermonuclear reaction energy and effective protection of a cylinder metal against thermal destruction by forming a uniform and stable liquid metal wall to the inside of a cylindrical member. Constitution: Cylindrical body having a lateral axis is rotatably supported so that a liquid metal wall for use in the wet wall type thermonuclear device is formed centrifugally. A liquid metal injection port for injecting the liquid metal to the cylindrical member is disposed to the lateral axis and a liquid metal exit for flowing out the injected liquid metal is disposed to the body of the cylindrical member, so as to form a moving liquid metal layer flowing from the injection port through the inner circumferential surface of the cylindrical member to the liquid metal exit port. Then, the liquid metal is centrifugally forced to the inner surface of the cylindrical body to form a uniform and stable liquid metal wall at the inner surface of the cylindrical body, whereby the reaction energy can effectively be recovered and the cylinder metal can effectively be protected against thermal destruction. (Yoshihara, H.)

  19. A METHANE IMAGING SURVEY FOR T DWARF CANDIDATES IN ρ OPHIUCHI

    International Nuclear Information System (INIS)

    Haisch, Karl E.; Barsony, Mary; Tinney, Chris

    2010-01-01

    We report on the results of the first deep, wide-field, near-infrared methane imaging survey of the ρ Ophiuchi cloud core to search for T dwarfs. Among the 6587 objects detected, 22 were identified as T dwarf candidates. Brown dwarf models indicate that at the age and distance of the ρ Ophiuchi cloud, these T dwarf candidates have masses between 1 and 2 Jupiter masses. If confirmed as genuine T dwarfs, these objects would be the youngest, lowest mass, and lowest gravity free-floating objects ever directly observed. The existence of these candidates suggests that the initial mass function of the ρ Ophiuchi cloud extends well into the regime of planetary mass objects. A large fraction (59% ± 16%) of our T dwarf candidates appear to be surrounded by circumstellar disks, and thus represents the lowest mass objects yet found to harbor circumstellar disks.

  20. International Thermonuclear Experimental Reactor

    International Nuclear Information System (INIS)

    Blevins, J.D.; Stasko, R.R.

    1989-09-01

    An international design team comprised of members from Canada, Europe, Japan, the Soviet Union, and the United States of America, are designing an experimental fusion test reactor. The engineering and testing objectives of this International Thermonuclear Experimental Reactor (ITER) are to validate the design and to demonstrate controlled ignition, extended burn of a deuterium and tritium plasma, and achieve steady state using technology expected to be available by 1990. The concept maximizes flexibility while allowing for a variety of plasma configurations and operating scenarios. During physics phase operation, the machine produces a 22 MA plasma current. In the technology phase, the machine can be reconfigured with a thicker shield and a breeding blanket to operate with an 18 MA plasma current at a major radius of 5.5 meters. Canada's involvement in the areas of safety, facility design, reactor configuration and maintenance builds on our internationally recognized design and operational expertise in developing tritium processes and CANDU related technologies

  1. Thermonuclear pulsors engineering

    International Nuclear Information System (INIS)

    Ramos, Ruben F.

    2001-01-01

    The neutronic radiation has several applications, such as activation analysis of different substances, neutron radiography, molecular structures study, cancer therapy, humidity detection and materials surface treatment, among others. The main obstacle for these applications is the generation of neutronic beams. Nuclear reactors, isotopic sources and particle accelerators are neutron generators commonly used. They share the disadvantages of being non-portable, and quite expensive. This work is mainly focused on the development of neutron generators suitable to the applications mentioned before, in which traditional generators are non-applicable. The main characteristics should be transportability and to be non-contaminating, which would allow in-situ tests. Plasma focus generators, which produce neutron pulses by thermonuclear fusion reactions, satisfy these requirements and are economically convenient. This last feature would assure competitively in the neutron sources market. (author)

  2. Thermonuclear fusion by laser

    International Nuclear Information System (INIS)

    Delpech, J.-F.; Fabre, Edouard.

    1978-01-01

    This paper is intended to describe the principle of inetia containment by laser and the research effort undertaken for this purpose. After having enumerated the principal thermonuclear reactions useful for fusion, the authors derive the rhoR criterion that characterizes inertia containment, as well as the Lawson criterion in the case of magnetic containment. The main physics problems involved in inertia containment by laser are enunciated and the article ends with a review of means resorted to in France and abroad for studying this problem. This review also reports C.N.R.S. bustling in this field, within the scope of competence of G.I.L.M. (Groupement de Recherches Coordonnees sur l'Interaction Laser-Matiere = Group for coordinated investigation of matter-laser interaction) established in Paris at the Ecole Polytechnique [fr

  3. Powerful lasers for thermonuclear fusion

    International Nuclear Information System (INIS)

    Basov, N.; Krokhin, O.; Sklizkov, G.; Fedotov, S.

    1977-01-01

    The parameters are discussed of the radiation of powerful lasers (internal energy of the plasma determined by the volume, density and temperature of the plasma, duration of the heating pulse, focusing of the laser pulse energy in a small volume of matter, radiation contrast) for attaining an effective thermonuclear fusion at minimum microexplosion energy. A survey is given of the methods of shaping laser pulses with limit parameters, and the principle of the construction of powerful laser systems is described. The general diagram and parameters are given of the Delfin thermonuclear apparatus and a diagram is presented of the focusing system of high luminosity for spherical plasma heating using spherical mirrors. A diagram is presented of the vacuum chamber and of the complex diagnostic apparatus for determining the basic parameters of thermonuclear plasma in the Delfin apparatus. The prospects are indicated of the further development of thermonuclear laser apparatus with neodymium and CO 2 lasers. (B.S.)

  4. The international thermonuclear reactor project

    International Nuclear Information System (INIS)

    James, T.R.

    1993-01-01

    The International Thermonuclear Experimental Reactor Project is a 6-year collaborative effort involving the U.S., Europe, Japan, and the Russian Federation to produce a detailed engineering design for the next-step fusion device

  5. Blanket for thermonuclear device

    International Nuclear Information System (INIS)

    Ozawa, Yoshihiro; Uda, Tatsuhiko; Maki, Koichi.

    1993-01-01

    The present invention provides a blanket of a thermonuclear device which produces tritium fuels consumed in plasmas while converting neutrons generated in the plasmas into heat energy. That is, zirconium is coated to at least one of neutron breeder pebbles and breeder pebbles, to suppress reaction between them by being in direct contact with each other at a high temperature. Further, fins are attached to a cooling pipe at a pitch smaller than the diameter of both of the pebbles, to prevent direct contact at whole surface of the pebbles and the cooling pipe, which would lower a temperature excessively. The length of the fin is controlled to control the thickness of a helium gas gap. With such constitution, direct contact of neutron breeder pebbles and the breeder pebble which are to be filled and mixed, and tend to react at a high temperature, can be prevented. The temperature of the breeding blanket is reliably prevented from lowering below a tritium emitting temperature. The structure is simplified and the production is facilitated. (I.S.)

  6. Controlled thermonuclear fusion reactors

    International Nuclear Information System (INIS)

    Walstrom, P.L.

    1976-01-01

    Controlled production of energy by fusion of light nuclei has been the goal of a large portion of the physics community since the 1950's. In order for a fusion reaction to take place, the fuel must be heated to a temperature of 100 million degrees Celsius. At this temperature, matter can exist only in the form of an almost fully ionized plasma. In order for the reaction to produce net power, the product of the density and energy confinement time must exceed a minimum value of 10 20 sec m -3 , the so-called Lawson criterion. Basically, two approaches are being taken to meet this criterion: inertial confinement and magnetic confinement. Inertial confinement is the basis of the laser fusion approach; a fuel pellet is imploded by intense laser beams from all sides and ignites. Magnetic confinement devices, which exist in a variety of geometries, rely upon electromagnetic forces on the charged particles of the plasma to keep the hot plasma from expanding. Of these devices, the most encouraging results have been achieved with a class of devices known as tokamaks. Recent successes with these devices have given plasma physicists confidence that scientific feasibility will be demonstrated in the next generation of tokamaks; however, an even larger effort will be required to make fusion power commercially feasible. As a result, emphasis in the controlled thermonuclear research program is beginning to shift from plasma physics to a new branch of nuclear engineering which can be called fusion engineering, in which instrumentation and control engineers will play a major role. Among the new problem areas they will deal with are plasma diagnostics and superconducting coil instrumentation

  7. [International Thermonuclear Experimental Reactor support

    International Nuclear Information System (INIS)

    Dean, S.O.

    1990-01-01

    This report summarizes the activities under LLNL Purchase Order B089367, the purpose of which is to ''support the University/Lawrence Livermore National Laboratory Magnetic Fusion Program by evaluating the status of research relative to other national and international programs and assist in long-range plans and development strategies for magnetic fusion in general and for ITER in particular.'' Two specific subtasks are included: ''to review the LLNL Magnet Technology Development Program in the context of the International Thermonuclear Experimental Reactor Design Study'' and to ''assist LLNL to organize and prepare materials for an International Thermonuclear Experimental Reactor Design Study information meeting.''

  8. Inertial thermonuclear fusion by laser

    International Nuclear Information System (INIS)

    Watteau, J.P.

    1993-12-01

    The principles of deuterium tritium (DT) magnetic or inertial thermonuclear fusion are given. Even if results would be better with heavy ions beams, most of the results on fusion are obtained with laser beams. Technical and theoretical aspects of the laser fusion are presented with an extrapolation to the future fusion reactor. (A.B.). 34 refs., 17 figs

  9. Control method for thermonuclear plasma

    International Nuclear Information System (INIS)

    Azuma, Kingo; Oda, Yasushi.

    1997-01-01

    CT (Compact Troid) is a doughnut-like shaped plasmas having a toroidal current and a poloidal current at the inside and forming a poloidal magnetic fluxes and toroidal magnetic flux. The structure of the CT is collapsed at a time of stationary state, accordingly, when it is injected to thermonuclear plasmas, particles can be supplied locally, and the state of the plasmas to be supplied can be changed by changing the direction of the injection. If a CT which is reverse to the poloidal magnetic fields is injected, plasmas with excessive ions can be supplied locally thereby enabling to form magnetic field in the thermonuclear plasmas. If the magnetic fields are formed in the vicinity of the surface of the thermonuclear plasmas, fast ions which have come over the magnetic field structure can be returned to the central portion of the plasmas. Then, confining performance of thermonuclear plasmas can be greatly improved, the efficiency for fuel supply can be increased, and energy required for ignition can be suppressed. (N.H.)

  10. Temperature measurements in thermonuclear plasmas

    International Nuclear Information System (INIS)

    Breton, D.

    1958-01-01

    The temperatures needed to produce thermonuclear reactions are of the order of several million degrees Kelvin. Devising methods for measuring such temperatures has been the subject of research in many countries. In order to present the problem clearly and to demonstrate its importance, the author reviews the various conditions which must be fulfilled in order that reactions may be qualified as thermonuclear. The relationship between the temperature and the cross-section of the reactions is studied, and it is shown that the notion of temperature in the plasmas is complex, which leads to a consideration of the temperature of the ions and that of the electrons. None of the methods for the temperature measurements is completely satisfactory because of the hypotheses which must be made, and which are seldom fulfilled during high-intensity discharges in the plasmas. In practice it is necessary to use several methods simultaneously. (author) [fr

  11. Plasma and controlled thermonuclear reaction

    Energy Technology Data Exchange (ETDEWEB)

    Kapitsa, P L [AN SSSR, Moscow. Inst. Fizicheskikh Problem

    1980-06-01

    Two contemporary trends of research are characterized aiming at the thermonuclear reactor, viz., tokamak type equipment and pulsed heating of a deuterium-tritium mixture using focused laser light. There is a third trend based on the use of high-power continuous wave (CW) microwave generators which allow producing a rope discharge. The design is described of an anticipated CW thermonuclear reactor. Using current experimental facilities, a continuous high-frequency discharge can be obtained at a pressure of 25 atm and electron temperature of 50 million K. The major problem involved in the design of a CW reactor is the heating of ions to the same temperature as the electron temperature and the reduction in ion gas thermal conductivity.

  12. Thermonuclear controlled fusion: international cooperation

    International Nuclear Information System (INIS)

    Conscience, J.-F.

    2001-01-01

    This report summarizes the current worldwide status of research in the field of thermonuclear controlled fusion as well as the international research programme planed for the next decades. The two main projects will be the ITER facility (International Thermonuclear Experimental Reactor) that should produce 10 times more energy than the energy injected, and the IFMIF (International Fusion Materials Irradiation Facility) designed to study the reactions of materials under intense neutron fluxes. The future of the pioneering JET facility (Joint European Torus) is also discussed. The engagement of the various countries (USA, Japan, Germany, Russian Federation and Canada) and international organisations (EURATOM and IEA) in terms of investment and research is described. Switzerland is involved in this program through an agreement with EURATOM and is mainly dedicated to experimental studies with the TCV machine in Lausanne and numerical studies of plasma configurations. It will participate to the development of the microwave plasma heating system for the ITER machine

  13. Magnetohydrodynamics and the thermonuclear problem

    Energy Technology Data Exchange (ETDEWEB)

    Alfven, H [Department of Electronics, Royal Institute of Technology, Stockholm (Sweden)

    1958-07-01

    The importance of magnetohydrodynamics and plasma physics for the solution of thermonuclear problem is presented in the paper. Methods for capture of a plasma by a magnetic field are discussed. From the study it is concluded that in principle it is possible to shoot heated plasma into a magnetic field and capture it there. A possible method of capturing plasma which is shot into a magnetic field is illustrated. Magnetohydrodynamic research performed during the last decade in Stockholm is presented. Following a long series of investigations of relatively cool plasmas, it has been started a series of experimental investigations on hot plasmas, concentrating on the fundamental properties of the plasma. New ways of the approach to the thermonuclear problem are analysed. Experiments have been with discharges of a few hundred kiloamps to produce fast-moving magnetized plasmas, in order to investigate whether they could be captured by magnetic fields in the discussed way.

  14. Structure of thermonuclear reactor wall

    International Nuclear Information System (INIS)

    Yamazaki, Seiichiro.

    1991-01-01

    In a thermonuclear reactor wall, there has been a worry that the brazing material is melted by high temperature heat and particle load, to peel off the joined portion and the protecting material is destroyed by temperature elevation, to expose the heat sink material. Then, in the reactor core structures of a thermonuclear reactor, such as a divertor plate comprising a protecting material made of carbon material and the heat sink material joined by brazing, a plate material made of a so-called refractory metal having a high atomic number such as tungsten, molybdenum or the alloy thereof is embedded or attached to an accurate position of the protecting material. This can prevent the brazing portion from destruction by escaping electrons generated upon occurrence of abnormality in the thermonuclear reactor, and peeling or destroy of the protecting material and the heat sink material. Sufficient characteristics of plasmas can always be maintained by disposing a material having a small atomic number, for example, carbon material, to the position facing to the plasmas. (N.H.)

  15. First wall of thermonuclear device

    International Nuclear Information System (INIS)

    Kizawa, Makoto; Koizumi, Makoto; Nishihara, Yoshihiro.

    1990-01-01

    The first wall of a thermonuclear device is constituted with inner wall tiles, e.g. made of graphite and metal substrates for fixing them. However, since the heat expansion coefficient is different between the metal substrates and intermediate metal members, thermal stresses are caused to deteriorate the endurance of the inner wall tiles. In view of the above, low melting metals are disposed at the portion of contact between the inner wall tiles and the metal substrates and, further, a heat pipe structure is incorporated into the metal substrates. Under the thermal load, for example, during operation of the thermonuclear device, the low melting metals at the portion of contact are melted into liquid metals to enhance the state of contact between the inner wall tiles and the metal substrate to reduce the heat resistance and improve the heat conductivity. Even if there is a difference in the heat expansion coefficient between the inner wall tiles and the metal substrates, neither sharing stresses not thermal stresses are caused. Further, since the heat pipe structure is incorporated into the metal substrates, the lateral unevenness of the temperature in the metal substrates can be eliminated. Thus, the durability of the inner wall tiles can be improved. (N.H.)

  16. Insulation structure of thermonuclear device

    International Nuclear Information System (INIS)

    Suzuki, Takayuki; Usami, Saburo; Tsukamoto, Hideo; Kikuchi, Mitsuru

    1998-01-01

    The present invention provides an insulating structure of a thermonuclear device, in which insulation materials between toroidal coils are not broken even if superconductive toroidal coils are used. Namely, a tokamak type thermonuclear device of an insulating structure type comprises superconductive toroidal coils for confining plasmas arranged in a circular shape directing the center each at a predetermined angle, and the toroidal coils are insulated from each other. The insulation materials are formed by using a biaxially oriented fiber reinforced plastics. The contact surface of the toroidal coils and the insulating materials are arranged so that they are contact at a woven surface of the fiber reinforced plastics. Either or both of the contact surfaces of the fiber reinforced plastics and the toroidal coils are coated with a high molecular compound having a low friction coefficient. With such a constitution, since the interlayer shearing strength of the biaxially oriented fiber reinforced plastics is about 1/10 of the compression strength, the shearing stress exerted on the insulation material is reduced. Since a static friction coefficient on the contact surface is reduced to provide a structure causing slipping, shearing stress does not exceeds a predetermined limit. As a result, breakage of the insulation materials between the toroidal coils can be prevented. (I.S.)

  17. Reactor wall in thermonuclear device

    International Nuclear Information System (INIS)

    Shibui, Masanao.

    1988-01-01

    Purpose: To always monitor the life of armours in reactor walls and automatically shutdown the reactor if it should be operated in excess of the limit of use. Constitution: Monitoring material of lower melting point than armours (for example beryllium pellets) as one of the reactor wall constituents of a thermonuclear device are embedded in a region leaving the thickness corresponding to the allowable abrasion of the armour. In this structure, if the armours are abrased due to particle loads of a plasma and the abrasion exceeds a predetermined allowable level, the monitoring material is exposed to the plasma and melted and evaporated. Since this can be detected by impurity monitors disposed in the reactor, it is possible to recognize the limit for the working life of the armours. If the thermonuclear reactor should be operated accidentally exceeding the life of the armours, since a great amount of the monitoring materials have been evaporated, they flow into the plasma to increase the plasma radiation loss thereby automatically eliminate the plasma. (K.M.)

  18. Ecological problems of thermonuclear energetics. Review

    Energy Technology Data Exchange (ETDEWEB)

    Sivintsev, Yu V

    1980-01-01

    A review of preliminary quantitative estimates of radiation hazard of thermonuclear reactors is presented. Main attention is given to three aspects: nonradiation effect on environment, radionuclide blow-ups at normal operation and emergency situations with their consequences. The given data testify to great radiological advantages of thermonuclear energetics as compared with the modern nuclear energetics with thermal and prospective fast reactors.

  19. The international thermonuclear reactor (ITER)

    International Nuclear Information System (INIS)

    Fowler, T.K.; Henning, C.D.

    1987-01-01

    Four governmental groups, representing Europe, Japan, USSR and U.S. met in March 1987 to consider a new international design of a magnetic fusion device for the 1990's. An interim group was appointed. The author gives a brief synopsis of what might be thought of as a draft charter. The starting point is the objective of the ITER device, which is summarized as demonstrating both scientific and technical feasibility of fusion. The paper presents an update on the current thinking and technical aspects for the International Thermonuclear Experimental Reactor (ITER). This covers not only what is happening in the U.S. but also some reports of preliminary thinking of the last technical work that occurred in Vienna

  20. Plasma and controlled thermonuclear reaction

    International Nuclear Information System (INIS)

    Kapitsa, P.

    1980-01-01

    The principle and prospects are given of three methods of achieving controlled thermonuclear reaction. The original and so far most promising TOKAMAK method is presented invented in the USSR. Another method is the heating of a sphere about 1 mm in diameter from a mixture of deuterium and tritium by focused laser light from all sides. The third method consists in continuous plasma heating. A rope-like plasma discharge at a temperature of more than a million K results in the gas from microwave oscillations. The discharge is placed in a magnetic field and the ion temperature is increased by magneto-acoustic waves. A reactor is proposed operating on this principle and problems are pointed out which will have to be resolved. (M.S.)

  1. Plasma and controlled thermonuclear reaction

    Energy Technology Data Exchange (ETDEWEB)

    Kapitsa, P

    1980-06-01

    The principle and prospects are given of three methods of achieving controlled thermonuclear reaction. The original and so far most promising TOKAMAK method is presented invented in the USSR. Another method is the heating of a sphere about 1 mm in diameter from a mixture of deuterium and tritium by focused laser light from all sides. The third method consists in continuous plasma heating. A rope-like plasma discharge at a temperature of more than a million K results in the gas from microwave oscillations. The discharge is placed in a magnetic field and the ion temperature is increased by magneto-acoustic waves. A reactor is proposed operating on this principle and problems are pointed out which will have to be resolved.

  2. Cooling device in thermonuclear device

    International Nuclear Information System (INIS)

    Honda, Tsutomu.

    1988-01-01

    Purpose: To prevent loss of cooling effect over the entire torus structure directly after accidental toubles in a cooling device of a thermonuclear device. Constitution: Coolant recycling means of a cooling device comprises two systems, which are alternately connected with in-flow pipeways and exit pipeways of adjacent modules. The modules are cooled by way of the in-flow pipeways and the exist pipeways connected to the respective modules by means of the coolant recycling means corresponding to the respective modules. So long as one of the coolant recycling means is kept operative, since every one other modules of the torus structure is still kept cooled, the heat generated from the module put therebetween, for which the coolant recycling is interrupted, is removed by means of heat conduction or radiation from the module for which the cooling is kept continued. No back-up emergency cooling system is required and it can provide high economic reliability. (Kamimura, M.)

  3. First wall of thermonuclear device

    International Nuclear Information System (INIS)

    Miki, Nobuharu.

    1992-01-01

    In a first wall of a thermonuclear device, armour tiles are metallurgically bonded to a support substrate only for the narrow area of the central portion thereof, while bonded by metallurgical bonding with cooling tubes of low mechanical toughness, separated from each other in other regions. Since the bonding area with the support substrate of great mechanical rigidity is limited to the narrow region at the central portion of the armour tiles, cracking are scarcely caused at the end portion of the bonding surface. In other regions, since cooling tubes of low mechanical rigidity are bonded metallurgically, they can be sufficiently withstand to high thermal load. That is, even if the armour tiles are deformed while undergoing thermal load from plasmas, since the cooling tubes absorb it, there is no worry of damaging the metallurgically bonded face. Since the cooling tubes are bonded directly to the armour tiles, they absorb the heat of the armour tiles efficiently. (N.H.)

  4. Controlled thermonuclear fusion. Present state and prospective

    International Nuclear Information System (INIS)

    Consoli, T.

    1976-01-01

    The interest of thermonuclear fusion for energy production is underlined. The present state of the research in this field is presented, emphasis being given to Tokamak configurations. The problems concerning confinement and additional heating in these devices are presented [fr

  5. Thermonuclear reaction generation method and device

    International Nuclear Information System (INIS)

    Imazaki, Kazuo

    1998-01-01

    The present invention provides a method of and a device for causing thermonuclear reaction capable of obtaining extremely high profits (about 1000 times), capable of forming a target which is strong against instability upon implosion as a problem of an inertia process and capable of realizing utilization of nuclear fusion. Namely, elementary particles such as pion, muon and K particles are deposited a portion or some portion of thermonuclear fuel materials by using high energy ions and highly brilliant γ rays generated from a high energy accelerator. The thermonuclear fuel materials are compressed to high density. The nuclear fusion reaction is promoted to ignite and burn thermonuclear fuels. A portion of nuclear fuels is ignited selectively by the means. High profits can be obtained. Since there is no need to attain implosion rate required for self ignition of nuclear fuels, a target of low aspect ratio can be used. (I.S.)

  6. Merging White Dwarfs and Thermonuclear Supernovae

    OpenAIRE

    van Kerkwijk, Marten H.

    2012-01-01

    Thermonuclear supernovae result when interaction with a companion reignites nuclear fusion in a carbon-oxygen white dwarf, causing a thermonuclear runaway, a catastrophic gain in pressure, and the disintegration of the whole white dwarf. It is usually thought that fusion is reignited in near-pycnonuclear conditions when the white dwarf approaches the Chandrasekhar mass. I briefly describe two long-standing problems faced by this scenario, and our suggestion that these supernovae instead resul...

  7. Baking method for thermonuclear reactor

    International Nuclear Information System (INIS)

    Kobayashi, Shigetada.

    1986-01-01

    Purpose: To improve the heat transmission property to the reactor core structures thereby shortening the baking time for the reactor core in thermonuclear reactors. Constitution: High temperature airs are supplied from a baking system to cooling pipeways disposed within reactor core structures and helium gas is supplied from a helium gas supply system through the reactor core structures to the inside of the reactor core for scavenging. The scavenging operation may be combined with vacuum suction. Further, the inside of the reactor is scavenged while maintaining at such a negative pressure as within a range not degrading the heat conduction property. Since the helium gas is chemically inert and poor in the depositing property, it shows no adsorbability even for the material heated to high temperature. Further, since the diffusion and heat conduction properties are high, the heat conduction property to the materials upon baking can be improved to shorten the baking time. No disadvantages are caused by the introduction of the helium gas upon baking. (Kawakami, Y.)

  8. Shielding wall for thermonuclear device

    International Nuclear Information System (INIS)

    Uchida, Takaho.

    1989-01-01

    This invention concerns shielding walls opposing to plasmas of a thermonuclear device and it is an object thereof to conduct reactor operation with no troubles even if a portion of shielding wall tiles should be damaged. That is, the shielding wall tiles are constituted as a dual layer structure in which the lower base tiles are connected by means of bolts to first walls. Further, the upper surface tiles are bolt-connected to the layer base tiles. In this structure, the plasma thermal loads are directly received by the surface layer tiles and heat is conducted by means of conduction and radiation to the underlying base tiles and the first walls. Even upon occurrence of destruction accidents to the surface layer tiles caused by incident heat or electromagnetic force upon elimination of plasmas, since the underlying base tiles remain as they are, the first walls constituted with stainless steels, etc. are not directly exposed to the plasmas. Accordingly, the integrity of the first walls having cooling channels can be maintained and sputtering intrusion of atoms of high atom number into the plasmas can be prevented. (I.S.)

  9. Shielding member for thermonuclear device

    Energy Technology Data Exchange (ETDEWEB)

    Onozuka, Masanori

    1997-06-30

    In a thermonuclear device for shielding fast neutrons by shielding members disposed in a shielding vessel (vacuum vessel and structures such as a blanket disposed in the vacuum vessel), the shielding member comprises a large number of shielding wires formed fine and short so as to have elasticity. The shielding wires are sealed in a shielding vessel together with water, and when the width of the shielding vessel is changed, the shielding wires follow after the change of the width while elastically deforming in the shielding vessel, so that great stress and deformation are not formed thereby enabling to improve reliability. In addition, the length, the diameter and the shape of each of the shielding wires can be selected in accordance with the shielding space of the shielding vessel. Even if the shape of the shielding vessel is complicated, the shielding wires can be inserted easily. Accordingly, the filling rate of the shielding members can be changed easily. It can be produced more easily compared with a conventional spherical pebbles. It can be produced more easily than existent spherical shielding pebbles thereby enabling to reduce the production cost. (N.H.)

  10. Divertor plate for thermonuclear reactor

    International Nuclear Information System (INIS)

    Yamazaki, Seiichiro; Sato, Keisuke; Nishio, Satoshi.

    1993-01-01

    In a divertor plate for a thermonuclear reactor, adjacent cooling pipes are electrically insulated from each other and pipes made of a gradient functional material prepared by compositing ceramics having an insulation property and metals are metallurgically joined to at least one portion of each of the cooling pipes. Electric current caused upon occurrence of plasma disruption is interrupted by the insulation portion, so that a large circuit is not formed and electromagnetic force is decreased to such a extent that the divertor plate is not ruptured. Since a header of the cooling pipes can be installed at any optional position, the installation space can be reduced. Further, since inlet and exit collection headers can be disposed on both ends of the cooling pipes, it is possible to shorten the length of the cooling pipe of the divertor plate corresponded to high heat fluxes and reduce the pressure loss on the side of coolants to about 1/2. Further, turn back portions of small radius of curvature of the cooling pipes are eliminated to reduce the cost and extend the lifetime and, in addition, protection tiles can be attached easily. (N.H.)

  11. First wall for thermonuclear device

    International Nuclear Information System (INIS)

    Shibuya, Yoji.

    1988-01-01

    Purpose: To reduce the thermal stresses resulted to tiles and suppress the temperature rise for mounting jigs in first walls for a thermonuclear device. Constitution: A support mounting rod as a tile mounting and fixing jig and a fixing support connected therewith are disposed to the inside of an armour tile composed of high melting material and, further, a spring is disposed between the lower portion of the tile and the base plate. The armour tile can easily be fixed to the base plate by means of the resilient member by rotating the support member and abutting the support member against the support member abutting portion of the base plate. Further, since the contact and fixing surface of the armour tile and the fixing jig is situated below the tile inside the cooled base plate, the temperature rise can be suppressed as compared with the usual case. Since screw or like other clamping portion is not used for fixing the tile, heat resistant ceramics can be used with no restriction only to metal members, to thereby moderate the restriction in view of the temperature. (Kamimura, M.)

  12. IRAS observations of dust heating and energy balance in the Rho Ophiuchi dark cloud

    Science.gov (United States)

    Greene, Thomas P.; Young, Erick T.

    1989-01-01

    The equilibrium process dust emission in the Rho Ophiuchi dark cloud is studied. The luminosity of the cloud is found to closely match the luminosity of the clouds's known embedded and external radiation sources. There is no evidence for a large population of undetected low-luminosity sources within the cloud and unknown external heating is also only a minor source of energy. Most of the cloud's luminosity is emitted in the mid-to-far-IR. Dust temperature maps indicate that the dust is not hot enough to heat the gas to observed temperatures. A simple cloud model with a radiation field composed of flux HD 147889, S1, and Sco OB2 associations predicts the observed IRAS 60 to 100 micron in-band flux ratios for a mean cloud density n(H2) = 1400. Flattened 12 and 25 micron observations show much extended emission in these bands, suggesting stochastic heating of very small grains or large molecules.

  13. Thermonuclear power plants and the environment

    International Nuclear Information System (INIS)

    Becka, J.

    1978-01-01

    Environmental safety and protection from the effects of the thermonuclear power plants are discussed. Factors are assessed which should be considered in the choice of fuel and breeding material of a thermonuclear reactor, the problems of structural material activation and the overall reactor concepts. Main specifications are given of the US thermonuclear power plant projects with D-T reaction based reactors. The overall amounts of tritium in the reactor cycles are shown. The potential biological risk is evaluated for the different materials considered for the UWMAK-1 project. Discussed are possible pathways of activity release in normal plant operation, non-radioactive aspects, such as waste heat, the magnetic field effect on personnel and population, etc., as well as possible environmental impacts in case of accidents. (B.S.)

  14. Inertia-confining thermonuclear molten salt reactors

    International Nuclear Information System (INIS)

    Furukawa, Kazuo; Yamanaka, Chiyoe; Nakai, Sadao; Imon, Shunji; Nakajima, Hidenori; Nakamura, Norio; Kato, Yoshio.

    1984-01-01

    Purpose: To increase the heat generating efficiency while improving the reactor safety and thereby maintaining the energy balance throughout the reactor. Constitution: In an inertia-confining type D-T thermonuclear reactor, the blanket is made of lithium-containing fluoride molten salts (LiF.BeF 2 , LiF.NaF.KF, LiF.KF, etc) which are cascaded downwardly in a large thickness (50 - 100 cm) along the inner wall of the thermonuclear reaction vessel, and neutrons generated by explosive compression are absorbed to lithium in the molten salts to produce tritium, Heat transportation is carried out by the molten salts. (Ikeda, J.)

  15. Thermonuclear energy and the power industry in the future

    International Nuclear Information System (INIS)

    Velikhov, E.P.

    1986-01-01

    The leader of the USSR thermonuclear program, the vicepresident of the Academy of Science, comrade Velikhov tells about the modern state and perspective of thermonuclear investigations, as well as about the problems on the international cooperation in this field

  16. Spectrophotometry of RS Oph during the nebular phase

    International Nuclear Information System (INIS)

    Bohigas, J.; Echevarria, J.; Diego, F.; Sarmiento, J.A.

    1989-01-01

    Blue-wavelength spectroscopic observations of RS Oph, 201 day after the 1985 outburst are presented. An analysis of the TiO bands indicates a spectral type M4III for the secondary and a distance of 2 kpc to the system. The system of forbidden lines is excited by a shock wave, whereas Balmer emission is mainly produced by photoionization. The source of photons is probably residual thermonuclear burning occurring at the surface of the white dwarf. (author)

  17. Important problems of future thermonuclear reactors*

    Directory of Open Access Journals (Sweden)

    Sadowski Marek J.

    2015-06-01

    Full Text Available This paper concerns important and difficult problems connected with a design and construction of thermonuclear reactors, which have to use nuclear fusion reactions of heavy isotopes of hydrogen, i.e., deuterium (D and tritium (T. There are described conditions in which such reactions can occur, and different methods of a high-temperature plasma generation, i.e., high-current electrical discharges, intense microwave pulses, and injection of energetic neutral atoms (NBI. There are also presented experimental facilities which can contain hot plasma for an appropriate period, and particularly so-called tokamaks. The second part presents the technical problems which must be solved in order to build a thermonuclear reactor, that might be used for energetic purposes. There are considered problems connected with a choice of constructional materials for a vacuum chamber, its internal parts, external windings generating a magnetic field, and necessary shields. The next part considers the handling of radioactive tritium; the using of alpha particles (4He for additional heating of plasma; recuperation of hydrogen isotopes absorbed in the tokamak internal parts, and a removal of a helium excess. There is presented a scheme of a future thermonuclear power plant and critical comments on a road map which should enable the construction of an industrial thermonuclear reactor (DEMO.

  18. Advance in physics of laser thermonuclear fusion

    International Nuclear Information System (INIS)

    Afanasev, J.; Basov, N.; Gamalij, J.; Krokhin, O.; Rozanov, V.

    1977-01-01

    A survey is given of current advance in the physics of laser thermonuclear fusion (LTF). The LTF physical model is discussed with regard to the optimal laser-target systems not only for attaining the physical limit but also for future thermonuclear reactors. The basic physical principles of LTF are formulated which make use of the fact that in focusing laser radiation on the surface of a substance a high density may be attained of the energy flux (10 5 to 10 6 J) and thereby also a high velocity of energy release in the substance. A detailed description is given of the processes which take place in laser irradiation of a spherical target. The problem is discussed of hydrodynamic stability in the compression of matter in laser thermonuclear targets, the concept is explained of the physical threshold of a thermonuclear reaction in laser excitation as are the conditions for attaining this threshold. The quantitative criterion is examined of the attainment of the physical threshold of LTF for pulsed systems. (B.S.)

  19. Analysis of induction phenomena in thermonuclear experiments

    International Nuclear Information System (INIS)

    Deeds, W.E.; Dodd, C.V.

    1976-01-01

    Many of the problems involving transients induced by changing currents in the large coils of thermonuclear machines are identical to those arising in nondestructive testing by eddy currents. There are three chief methods used for calculating such induction phenomena: analytical boundary-value solutions, relaxation or iteration techniques, and model experiments. Some of the results obtained by each of these methods are described below

  20. Thermonuclear plasma physic: inertial confinement fusion

    International Nuclear Information System (INIS)

    Bayer, Ch.; Juraszek, D.

    2001-01-01

    Inertial Confinement Fusion (ICF) is an approach to thermonuclear fusion in which the fuel contained in a spherical capsule is strongly compressed and heated to achieve ignition and burn. The released thermonuclear energy can be much higher than the driver energy, making energetic applications attractive. Many complex physical phenomena are involved by the compression process, but it is possible to use simple analytical models to analyze the main critical points. We first determine the conditions to obtain fuel ignition. High thermonuclear gains are achieved if only a small fraction of the fuel called hot spot is used to trigger burn in the main fuel compressed on a low isentrope. A simple hot spot model will be described. The high pressure needed to drive the capsule compression are obtained by the ablation process. A simple Rocket model describe the main features of the implosion phase. Several parameters have to be controlled during the compression: irradiation symmetry, hydrodynamical stability and when the driver is a laser, the problems arising from interaction of the EM wave with the plasma. Two different schemes are examined: Indirect Drive which uses X-ray generated in a cavity to drive the implosion and the Fast Ignitor concept using a ultra intense laser beam to create the hot spot. At the end we present the Laser Megajoule (LMJ) project. LMJ is scaled to a thermonuclear gain of the order of ten. (authors)

  1. Thermonuclear model for high energy transients

    International Nuclear Information System (INIS)

    Woosley, S.E.

    1982-01-01

    The thermonuclear model for x- and γ-ray bursts is discussed. Different regimes of nuclear burning are reviewed, each appropriate to a given range of (steady state) accretion rate. Accretion rates in the range 10 -14 to 10 -8 Msub solar y -1 all appear capable of producing x-ray transients of various durations and intervals. Modifications introduced by radiatively driven mass loss, the thermal inertia of the envelope, different burning mechanisms, and two-dimensional considerations are discussed as are difficulties encountered when the thermonuclear model is confronted with observations of rapidly recurrent bursts (less than or equal to 10 min), and super-Eddington luminosities and temperatures. Results from a numerical simulation of a combined hydrogen-helium runaway initiated at pycnonuclear density are presented for the first time. The thermonuclear model for γ-ray bursts is also reviewed and updated, particularly with regard to the breakdown of the steady state hypothesis employed in previous work. Solely on the basis of nuclear instability, γ-ray bursts of various types appear possible for a very broad variety of accretion rates (approx. 10 -17 to approx. 10 -11 Msub solar y -1 ) although other considerations may restrict this range. The thermonuclear model appears capable of yielding a great diversity of high energy transient phenomena for various accretion rates, magnetic field configurations, and neutron star envelope histories

  2. SMA and CARMA observations of young brown dwarfs in ρ Ophiuchi and Taurus

    Directory of Open Access Journals (Sweden)

    Lee C.-F.

    2011-07-01

    Full Text Available Molecular outflows provide vital information about the earliest stages in the birth of stars, studying the molecular outflow properties is therefore crucial for understanding how stars form. Brown dwarfs with masses between that of stars and planets are not massive enough to maintain stable hydrogen-burning fusion reactions during most of their lifetime. Their origins are subject to much debate in recent literature because their masses are far below the typical mass where core collapse is expected to occur. Based on Submillimeter Array (SMA and Combined Array for Research in Millimeter-wave Astronomy (CARMA observations, we present the first detections of bipolar molecular outflows from young brown dwarfs in ρ Ophiuchi and Taurus. Our results demonstrate that the bipolar molecular outflow operates down to brown dwarf masses, occurring in brown dwarfs as a scaled-down version of the universal process seen in young low-mass stars. This demonstrates that brown dwarfs and low-mass stars likely share the same formation mechanism.

  3. Rates of Thermonuclear Reactions in Dense Plasmas

    International Nuclear Information System (INIS)

    Tsytovich, V.N.; Bornatici, M.

    2000-01-01

    The problem of plasma screening of thermonuclear reactions has attracted considerable scientific interest ever since Salpeter's seminal paper, but it is still faced with controversial statements and without any definite conclusion. It is of relevant importance to thermonuclear reactions in dense astrophysical plasmas, for which charge screening can substantially affect the reaction rates. Whereas Salpeter and a number of subsequent investigations have dealt with static screening, Carraro, Schafer, and Koonin have drawn attention to the fact that plasma screening of thermonuclear reactions is an essentially dynamic effect. In addressing the issue of collective plasma effects on the thermonuclear reaction rates, the first critical overview of most of the work carried out so far is presented and the validity of the test particle approach is assessed. In contrast to previous investigations, we base our description on the kinetic equation for nonequilibrium plasmas, which accounts for the effects on the rates of thermonuclear reactions of both plasma fluctuations and screening and allows one to analyze explicitly the effects of the fluctuations on the reaction rates. Such a kinetic formulation is more general than both Salpeter's approach and the recently developed statistical approaches and makes it possible to obtain a more comprehensive understanding of the problem. A noticeable result of the fluctuation approach is that the static screening, which affects both the interaction and the self-energy of the reacting nuclei, does not affect the reaction rates, in contrast with the results obtained so far. Instead, a reduction of the thermonuclear reaction rates is obtained as a result of the effect of plasma fluctuations related to the free self-energy of the reacting nuclei. A simple physical explanation of the slowing down of the reaction rates is given, and the relation to the dynamically screened test particle approach is discussed. Corrections to the reaction rates

  4. Deuterides of light elements: low-temperature thermonuclear burn-up and applications to thermonuclear fusion problems

    International Nuclear Information System (INIS)

    Frolov, A.M.; Smith, V.H.; Smith, G.T.

    2002-01-01

    Thermonuclear burn-up and thermonuclear applications are discussed for a number of deuterides and DT hydrides of light elements. These deuterides and corresponding DT hydrides are often used as thermonuclear fuels or components of such fuels. In fact, only for these substances thermonuclear energy gain exceeds (at some densities and temperatures) the bremsstrahlung loss and other high-temperature losses, i.e., thermonuclear burn-up is possible. Herein, thermonuclear burn-up in these deuterides and DT hydrides is considered in detail. In particular, a simple method is proposed to determine the critical values of the burn-up parameter x c for these substances and their mixtures at different temperatures and densities. The results for equimolar DT mixtures coincide quite well with the results of previous calculations. Also, the natural or Z limit is determined for low-temperature thermonuclear burn-up in the deuterides of light elements. (author)

  5. Fast fission assisted ignition of thermonuclear microexplosions

    International Nuclear Information System (INIS)

    Winterberg, F.

    2006-01-01

    It is shown that the requirements for fast ignition of thermonuclear microexplosions can be substantially relaxed if the deuterium-tritium (DT) hot spot is placed inside a shell of U-238 (Th-232). An intense laser - or particle beam-projected into the shell leads to a large temperature gradient between the hot DT and the cold U-238 (Th-232), driving thermomagnetic currents by the Nernst effect, with magnetic fields large enough to entrap within the hot spot the α-particles of the DT fusion reaction. The fast fission reactions in the U-238 (Th-232) shell implode about 1/2 of the shell onto the DT, increasing its density and reaction rate. With the magnetic field generated by the Nernst effect, there is no need to connect the target to a large current carrying transmission line, as it is required for magnetized target fusion, solving the so-called ''stand off'' problem for thermonuclear microexplosions. (orig.)

  6. A Game Theoretic Model of Thermonuclear Cyberwar

    Energy Technology Data Exchange (ETDEWEB)

    Soper, Braden C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-08-23

    In this paper we propose a formal game theoretic model of thermonuclear cyberwar based on ideas found in [1] and [2]. Our intention is that such a game will act as a first step toward building more complete formal models of Cross-Domain Deterrence (CDD). We believe the proposed thermonuclear cyberwar game is an ideal place to start on such an endeavor because the game can be fashioned in a way that is closely related to the classical models of nuclear deterrence [4–6], but with obvious modifications that will help to elucidate the complexities introduced by a second domain. We start with the classical bimatrix nuclear deterrence game based on the game of chicken, but introduce uncertainty via a left-of-launch cyber capability that one or both players may possess.

  7. Towards upper power levels: thermonuclear fusion

    International Nuclear Information System (INIS)

    Vedel, Jean

    1983-01-01

    This paper is a brief introduction to the use of power lasers to achieve controlled thermonuclear fusion. After shortly describing thermonuclear fusion and the conditions of temperature, density and duration required it is showed how the laser enables such conditions to be created. The neodymium-doped glass laser NOVA that is being installed at the Livermore laboratory in the USA is described; at the time of its completion in 1984, this laser will be the most powerful in the world. In comparison, the OCTAL laser in operation at the Limeil establishment ''Centre d'Etudes'' of ''Commissariat Francais a l'Energie Atomique'' (the French atomic energy authority) is more modest; it is presented here [fr

  8. Merging white dwarfs and thermonuclear supernovae.

    Science.gov (United States)

    van Kerkwijk, M H

    2013-06-13

    Thermonuclear supernovae result when interaction with a companion reignites nuclear fusion in a carbon-oxygen white dwarf, causing a thermonuclear runaway, a catastrophic gain in pressure and the disintegration of the whole white dwarf. It is usually thought that fusion is reignited in near-pycnonuclear conditions when the white dwarf approaches the Chandrasekhar mass. I briefly describe two long-standing problems faced by this scenario, and the suggestion that these supernovae instead result from mergers of carbon-oxygen white dwarfs, including those that produce sub-Chandrasekhar-mass remnants. I then turn to possible observational tests, in particular, those that test the absence or presence of electron captures during the burning.

  9. Thermonuclear fusion: Current status and future prospects

    International Nuclear Information System (INIS)

    Bruhns, H.; Maisonnier, Ch.

    1992-01-01

    Thermonuclear Fusion holds great promises for becoming an important energy source for the future. Fusion research and development is undertaken in al major countries of the world. The European Community pursues fusion in a large programme which embraces all R and D in the field of magnetic confinement fusion in the Member States, and to which Sweden and Switzerland are fully associated. The long-term objective of the programme is the joint creation of safe, environmentally sound prototype reactors. The main R and D line of the Community Fusion Programme is fusion by toroidal magnetic confinement on the basis of the Tokamak concept. Some related concepts are also studied which possibly could offer advantages for a reactor, and keep-in-touch activities exist for other approaches. Several small and medium sized specialised devices in Associated Laboratories have been built by the Community Fusion Programme as well as the Joint European Torus (JET Joint Undertaking) which is the largest and the most successful fusion device in the world. Recently, fusion power in the megawatt range has been achieved in JET. The long timescale and the large effort needed for the development of fusion as an energy source have been important elements to foster international collaboration. Engineering Design Activities for an International Thermonuclear Experimental Reactor (ITER) are undertaken, under the auspices of the IAEA, by the European Community, Japan, the Russian Federation and the United States of America. The objective of ITER is to achieve self-sustained thermonuclear burn and its control under long-pulse operation and to provide basic data for the engineering of a demonstration fusion reactor. (author)

  10. Rates of the main thermonuclear reactions

    International Nuclear Information System (INIS)

    Abramovich, S.N.; Guzhovskii, B.Ya.; Dunaeva, S.A.; Fomushkin, E.F.

    1992-01-01

    The data on the cross sections of main thermonuclear reactions have been estimated with an account of the latest experimental results in a form of S-factor spline presentation. Based on this estimation, the reates of these reactions in 0.0001-1 MeV temperature range in the supposition of Maxwell distribution of relative velocities have been computed. The Maxwell-Boltzmann averaged -factors were calculated according to the table values of the reaction rates. Then the -factors were approximated with the 3 order spline-function. The necessity of the account of electron shielding and intramolecular movement at low temperatures is discussed (orig.)

  11. Department of Thermonuclear Research annual report 1993

    International Nuclear Information System (INIS)

    Sadowski, M.; Pawlowicz, W.

    1994-01-01

    Department of Thermonuclear Research Annual Report 1993 presents a short review of theoretical, experimental and technological studies performed within the framework of the research program - Plasma Physics. Theoretical studies of a tokamak edge plasma, inner shell ionization by positrons, heat transfer in thin foils, and numerical simulation of HV pulse generators, are summarized. Experimental studies of X-rays and charged particles (including fusion protons) emitted from Plasma-Focus facilities, as well as measurements of plasma-ion streams generated by IONOTRON devices, are described shortly. Also presented are technological studies on data acquisition systems and material engineering, in particular the modification of solid surfaces with the plasma-ion streams. (author)

  12. Thermonuclear 36Cl pulse in natural water

    International Nuclear Information System (INIS)

    Bentley, H.W.; Davis, S.N.; Gifford, S.; Phillips, E.M.; Elmore, D.; Tubbs, L.E.; Gove, H.E.

    1982-01-01

    The enhanced concentration of 3 6Cl, produced by neutron activation of seawater and released into the environment during atmospheric thermonuclear tests in the 1950s, has been used as a tracer in natural water systems. The results of numerical modelling and analyses of water samples are presented which indicate that in the mid-latitudes the fallout peak was 3 orders of magnitude above the natural background, and that the period of enhanced 36 Cl fallout was 1953 to about 1964. The advantages of 36Cl as an environmental tracer are discussed. (U.K.)

  13. Controlled thermonuclear reactions and Tora Supra program

    International Nuclear Information System (INIS)

    1988-01-01

    The research programs for the nuclear energy production by means of thermonuclear fusion are shown. TORA SUPRA, Joint European Torus, Next European Torus and those developed at the Atomic Energy Center are described. The controlled fusion necessary conditions, the energy and confinement balance, and the research of a better tokamak configuration are discussed. A description of TORA SUPRA, the ways of achieving the project and the expected delays are shown. The Controlled Fusion Research Department functions, concerning these programs, are described. The importance of international cooperation and the perspectives about the use of controlled fusion are underlined [fr

  14. Status report on controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    1990-06-01

    The International Fusion Research Council (IFRC), an advisory body to the International Atomic Energy Agency, reports on the current status of fusion; this report updates its 1978 status report. This report contains a General Overview and Executive Summary, and reports on all current approaches to fusion throughout the world; a series of technical reports is to be published elsewhere. This report is timely in that it not only shows progress which has occurred over the past, but interfaces with possible future devices, in particular the International Thermonuclear Experimental Reactor (ITER), whose conceptual design phase is nearing completion. 5 refs, 6 figs

  15. Thermonuclear ignition in the next generation tokamaks

    International Nuclear Information System (INIS)

    Johner, J.

    1989-04-01

    The extrapolation of experimental rules describing energy confinement and magnetohydrodynamic - stability limits, in known tokamaks, allow to show that stable thermonuclear ignition equilibria should exist in this configuration, if the product aB t x of the dimensions by a magnetic-field power is large enough. Quantitative application of this result to several next-generation tokamak projects show that those kinds of equilibria could exist in such devices, which would also have enough additional heating power to promote an effective accessible ignition

  16. Department of Thermonuclear Research. Annual report 1988

    International Nuclear Information System (INIS)

    Sadowski, M.

    1989-01-01

    Department of Thermonuclear Research annual report 1988 presents a short review of theoretical, experimental and technological studies performed within a framework of two research programs: diagnostics of high-temperature plasma and nuclear technology. We describe theoretical investigations on the modelling of Tokamak edge plasmas, ion motions, atomic collisions, high-voltage electrode systems and plasma-focus (PF) facilities. The experimental studies on plasma-ion streams, high-current discharges of the PF-type, and on the interaction of ion beams with gaseous targets, are shortly summarized. Also presented are technological studies on electronic and high-voltage systems, as well as applications of the IONOTRON type plasma devices. (author)

  17. Department of Thermonuclear Research annual report 1993

    Energy Technology Data Exchange (ETDEWEB)

    Sadowski, M; Pawlowicz, W [eds.; Soltan Inst. for Nuclear Studies, Otwock-Swierk (Poland)

    1994-12-31

    Department of Thermonuclear Research Annual Report 1993 presents a short review of theoretical, experimental and technological studies performed within the framework of the research program - Plasma Physics. Theoretical studies of a tokamak edge plasma, inner shell ionization by positrons, heat transfer in thin foils, and numerical simulation of HV pulse generators, are summarized. Experimental studies of X-rays and charged particles (including fusion protons) emitted from Plasma-Focus facilities, as well as measurements of plasma-ion streams generated by IONOTRON devices, are described shortly. Also presented are technological studies on data acquisition systems and material engineering, in particular the modification of solid surfaces with the plasma-ion streams. (author).

  18. Repairing method and device for thermonuclear device

    International Nuclear Information System (INIS)

    Sakurai, Akiko; Masumoto, Hiroshi; Tachikawa, Nobuo.

    1995-01-01

    The present invention provides a method of and a device for repairing a first wall and a divertor disposed in a vacuum vessel of a thermonuclear device. Namely, an armour tile of the divertor secured, by a brazing material, in a vacuum vessel of the thermonuclear device in which high temperature plasmas of deuterium and tritium are confined to cause fusion reaction is induction-heated or heated by microwaves to melt the brazing material. Only the armour tile is thus exchanged by its attachment/detachment. This device comprises, in the vacuum vessel, an armour tile attaching/detaching manipulator and a repairing manipulator comprising a heating manipulator having induction heating coils at the top end thereof. Induction heating coils are connected to an AC power source. According to the present invention, the armour tile is exchanged without taking the divertor out of the vacuum vessel. Therefore, cutting of a divertor cooling tube for taking the divertor out of the vacuum vessel and re-welding of the divertor for attaching it to the vacuum vessel again are no more necessary. (I.S.)

  19. Radio-emission of pre-main sequence stars of the Rho Ophiuchi cloud: observations and interpretation

    International Nuclear Information System (INIS)

    Andre, P.

    1987-11-01

    Observations of the radio continuum emission of a young star population have been made at VLA on the whole molecular cloud Rho Ophiuchi, one of the closest site of star formation. A dozen of stellar sources have been detected. Radio emission of some identified objects seems to have a magnetic nature and be produced by gyrosynchrotron mechanism. In particular, one of the sources shows a radio radiation circularly polarized; two other stars have a radiation strongly variable probably due to magnetic eruptions more important than those detected in X radiation. More generally, radio observations select probably a specific population of young stars characterized by magnetic field presence extended on several stellar radii and by absence of dense circumstellar environment. Spatial distribution of these objects suggest, they are younger than most of the pre-main sequence stars [fr

  20. MOLECULAR OUTFLOWS IN THE SUBSTELLAR DOMAIN: MILLIMETER OBSERVATIONS OF YOUNG VERY LOW MASS OBJECTS IN TAURUS AND ρ OPHIUCHI

    International Nuclear Information System (INIS)

    Ngoc Phan-Bao; Lee, Chin-Fei; Ho, Paul T. P.; Tang, Ya-Wen

    2011-01-01

    We report here our search for molecular outflows from young very low mass stars and brown dwarfs in Taurus and ρ Ophiuchi. Using the Submillimeter Array and the Combined Array for Research in Millimeter-wave Astronomy, we have observed four targets at 1.3 mm wavelength (230 GHz) to search for CO J = 2 → 1 outflows. A young very low mass star MHO 5 (in Taurus) with an estimated mass of 90 M J , which is just above the hydrogen-burning limit, shows two gas lobes that are likely outflows. While the CO map of MHO 5 does not show a clear structure of outflow, possibly due to environment gas, its position-velocity diagram indicates two distinct blue- and redshifted components. We therefore conclude that they are components of a bipolar molecular outflow from MHO 5. We estimate an outflow mass of 7.0 x 10 -5 M sun and a mass-loss rate of 9.0 x 10 -10 M sun . These values are over two orders of magnitude smaller than the typical ones for T Tauri stars and somewhat weaker than those we have observed in the young brown dwarf ISO-Oph 102 of 60 M J in ρ Ophiuchi. This makes MHO 5 the first young very low mass star showing a bipolar molecular outflow in Taurus. The detection boosts the scenario that very low mass objects form like low-mass stars but in a version scaled down by a factor of over 100.

  1. RS CVn binary systems

    International Nuclear Information System (INIS)

    Linsky, J.L.

    1984-01-01

    The author attempts to place in context the vast amount of data obtained in the last few years as a result of X-ray, ultraviolet, optical, and microwave observations of RS CVn and similar spectroscopic binary systems. He concentrates on the RS CVn systems and their long-period analogs, and restricts the scope by attempting to answer on the basis of the recent data and theory following questions: (1) Are the original defining characteristics still valid and still adequate? (2) What is the evidence for discrete active regions? (3) Have we derived any meaningful physical properties for the atmospheres of RS CVn systems? (4) What are the flare observations telling us about magnetic fields in the RS CVn systems? (5) Is there evidence for systematic trends in RS CVn systems with spectral type?

  2. Department of Thermonuclear Research annual report 1990

    Energy Technology Data Exchange (ETDEWEB)

    Sadowski, M [ed.

    1991-03-01

    Department of Thermonuclear Research Annual Report 1990 presents the most important results of theoretical, experimental, and technological studies, carried out within a framework of two programs: Diagnostics of High-Temperature Plasma (CPBP 01.10) and Nuclear Technology (CPBR 5.8). Theoretical studies of tokamak edge plasmas, charged particle motions, strong refraction effects, current pulse generators, classical models of atomic collisions, and electron mechanisms of the Coulomb barrier tunneling, are shortly summarized. Experimental studies of X-ray, ion, and proton emission from the RPI-type devices, as well as optimization tests and electron beam measurements at the PF-type facilities, are described. Technological studies of opto-electronic transmission systems, modifications of diagnostic equipment, design and construction of new PF facilities, as well as applications of the IONOTRON-type devices, are also presented. (author). 56 refs, 20 figs.

  3. Transition to thermonuclear burn in fusion plasmas

    International Nuclear Information System (INIS)

    Anderson, D.; Hamnen, H.; Lisak, M.

    1991-01-01

    An analytical investigation is made of the time evolution of the 1-D temperature profile in a fusion reactor plasma where the nonlinear energy balance equation is dominated by alpha-particle heating and thermal conduction losses. Special emphasis is given to the problem of establishing sufficient conditions for the transition to thermonuclear burn for given initial temperature profiles. In particular, it is demonstrated that for strongly nonlinear alpha-particle heating, temperature profiles initially peaked on-axis are more easily ignited than profiles similar in form to the equilibrium profile of the energy balance equation. Simple analytical criteria for ignition are established and are shown to compare favourably with results of numerical calculations. (author)

  4. Department of Thermonuclear Research annual report 1991

    Energy Technology Data Exchange (ETDEWEB)

    Sadowski, M; Pawlowicz, W [eds.

    1992-02-01

    Department of Thermonuclear Research Annual Report 1991 presents a short review of theoretical, experimental, and technological studies carried out within the framework of two research programs: Plasma Physics and Development of Diagnostics Data Acquisition. Theoretical studies of a tokamak edge plasma, validity of inverse Abel transformation for strongly refracting objects, simulation of the pulse generators operation, and a numerical analysis of electron capture in p + H{sup +} collisions, are described. Experimental studies of corpuscular beams and X-rays from different plasma facilities, development of diagnostic techniques and of data acquisition systems, as well as experiments with the generation of cryogenic pellets for plasma research, are shortly summarized. Also presented are technological studies concerning the modernization of the PF- and RPI-type facilities and the application of the IONOTRON-type devices for the modification of semiconductor and metal surfaces. (author). 27 refs, 24 figs.

  5. Vacuum problems of thermonuclear reactor design

    International Nuclear Information System (INIS)

    Paty, L.

    1981-01-01

    A thermonuclear reactor can be considered to be a vacuum system in which constant concentration should be maintained of reacting particles while permanently discharging the undesirable particles using a system of pumps. The discharging proceeds in two stages: in the former, the reactor is degassed using external pumps connected to the reactor chamber through a pumping pipe. The latter in which hydrogen is admitted, uses high pump-rate machines based on the principle of the binding of the gas to the pump surface and must not introduce molecules of higher atomic mass in the system. Turbomolecular pumps of diffusion oil pumps are most suitable for the former stage while condensation, cryosorption, titanium pumping machines and special pumping methods are most suitable for the latter stage. Examples are shown of the pump system design for Tokamak 10 and for facilities at the Euratom laboratory in Fontenay-aux-Roses. (M.D.)

  6. Baking exhaustion device in thermonuclear device

    Energy Technology Data Exchange (ETDEWEB)

    Kondo, Mitsunori.

    1987-02-02

    Purpose: To rapidly remove tritium and impurity from the vacuum region in the access port of the baking exhaustion device in a thermonuclear device. Constitution: Each of the gaps at the boundary between a fixed shielding member and a blanket module and at the boundary between the blanket and a divertor is made extremely small so as to minimize the neutron streaming from plasmas. Accordingly, in the case of evacuating the vacuum region in the access port, the gap conductance is extremely poor and the exhaustion speed is low. Then, baking pipeways for flowing high temperature fluids are embedded to the surface layer at the position facing to the vacuum region and the plasma evacuation duct and the vacuum region are connected with an evacuation duct of the access port. By flowing high temperature fluids in the pipeways and conducting evacuation, baking exhaustion can be carried out rapidly. (Kamimura, M.).

  7. Magnetic Reconnection Driven by Thermonuclear Burning

    Science.gov (United States)

    Gatto, R.; Coppi, B.

    2017-10-01

    Considering that fusion reaction products (e.g. α-particles) deposit their energy on the electrons, the relevant thermal energy balance equation is characterized by a fusion source term, a relatively large longitudinal thermal conductivity and an appropriate transverse thermal conductivity. Then, looking for modes that are radially localized around rational surfaces, reconnected field configurations are found that can be sustained by the electron thermal energy source due to fusion reactions. Then this process can be included in the category of endogenous reconnection processes and may be viewed as a form of the thermonuclear instability that can develop in an ignited inhomogeneous plasma. A complete analysis of the equations supporting the relevant theory is reported. Sponsored in part by the U.S. DoE.

  8. Status report on controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    1990-01-01

    The International Fusion Research Council has prepared this report on the current status of fusion, an update of its 1978 report, at the request of the Director General of the International Atomic Energy Agency. The report consists of an introductory note by the Director General, an Executive Summary and General Overview published in this document, and a series of technical reports. The background of fusion as an energy source is documented and compared with fission. The two approaches to thermonuclear fusion, magnetic confinement and inertial confinement, are discussed. The viability with respect to economic, environmental, and safety aspects is discussed. Fusion programs in the European Community, Japan, the USSR, the USA, as well as smaller programs in other countries are described. The status of fusion physics and technology is elucidated, and future directions and plans are indicated. 5 refs, 6 figs

  9. Protection device for a thermonuclear device

    International Nuclear Information System (INIS)

    Kawashima, Shuichi.

    1986-01-01

    Purpose: To exactly detect the void coefficients of coolants even under high magnetic fields thereby detect the overheat of a thermonuclear device at an early stage. Constitution: The protecting device of this invention comprises a laser beam generation device, a laser beam detection device and an accident detection device. The laser generation device always generates laser beams, which are permeated through coolants and detected by the laser beam detection device, the optical amount of which is transmitted to the accident detection device. The accident detection device judges the excess or insufficiency of the detected optical amount with respect to the optical amount of the laser beams under the stationary state as a reference and issues an accident signal. Since only the optical cables that do not undergo the effect of the magnetic fields are exposed to high magnetic fields in the protection device of this invention, a high reliability can be maintained. (Kamimura, M.)

  10. The International Thermonuclear Experimental Reactor configuration evolution

    International Nuclear Information System (INIS)

    Lousteau, D.C.; Nelson, B.E.; Lee, V.D.; Thomson, S.L.; Miller, J.M.; Lindquist, W.B.

    1989-01-01

    The International Thermonuclear Experimental Reactor (ITER) conceptual design activities consist of two phases: a definition phase, completed in September 1988, and a design phase, now in progress. The definition phase was successful in identifying a consistent set of technical characteristics and the broad definition of the required reactor configuration and hardware. Scheduled for completion in November 1990, the design phase is producing a more detailed definition of the required components, a first cost estimate, and a description of site requirements. A major activity in the ITER design phase is the period of joint work conducted at the Max Planck Institute for Plasma Physics, Garching, Federal Republic of Germany, from June through October 1989. An official report of the findings and conclusions of this activity will be submitted to and published by the International Atomic Energy Agency (IAEA). This paper highlights the evolution of the reactor mechanical configuration since the conclusion of the definition phase. 8 figs., 2 tabs

  11. Surface effects in controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    Kaminsky, M.

    1975-08-01

    During the operation of large size plasma facilities and future controlled thermonuclear fusion reactors the surfaces of such major components as container walls, beam limiters, diverter walls and beam-dump walls of the injector region will be exposed to particle and photon bombardment from primary plasma radiations and from secondary radiations. Such radiations can cause, for example, physical and chemical sputtering, blistering, particle- and photon-impact induced desorption, secondary electron and x-ray emission, backscattering, nuclear reactions, photo-decomposition of surface compounds, photocatalysis, and vaporization. Such effects in turn can (a) seriously damage and erode the bombarded surface and (b) release major quantities of impurities which will contaminate the plasma. The effects of some of the major surface phenomena on the operation of plasma facilities and future fusion reactors are discussed

  12. Department of Thermonuclear Research annual report 1990

    International Nuclear Information System (INIS)

    Sadowski, M.

    1991-03-01

    Department of Thermonuclear Research Annual Report 1990 presents the most important results of theoretical, experimental, and technological studies, carried out within a framework of two programs: Diagnostics of High-Temperature Plasma (CPBP 01.10) and Nuclear Technology (CPBR 5.8). Theoretical studies of tokamak edge plasmas, charged particle motions, strong refraction effects, current pulse generators, classical models of atomic collisions, and electron mechanisms of the Coulomb barrier tunneling, are shortly summarized. Experimental studies of X-ray, ion, and proton emission from the RPI-type devices, as well as optimization tests and electron beam measurements at the PF-type facilities, are described. Technological studies of opto-electronic transmission systems, modifications of diagnostic equipment, design and construction of new PF facilities, as well as applications of the IONOTRON-type devices, are also presented. (author). 56 refs, 20 figs

  13. Thermonuclear reactor materials composed of glassy carbons

    International Nuclear Information System (INIS)

    Kazumata, Yukio.

    1979-01-01

    Purpose: To improve the durability to plasma radiation by the use of glassy carbon as the structural materials for the first wall and the blanket in thermonuclear devices. Constitution: The glassy carbon (glass-like carbon) is obtained by forming specific organic substances into a predetermined configuration and carbonizing them by heat decomposition under special conditions. They are impermeable carbon material of 1.40 - 1.70 specific gravity, less graphitizable and being almost in isotropic crystal forms in which isotropic structure such as in graphite is scarcely observed. They have an extremely high hardness, are less likely to be damaged when exposed to radiation and have great strength and corrosion resistance. Accordingly, the service life of the reactor walls and the likes can remarkably be increased by using the materials. (Horiuchi, T.)

  14. Department of Thermonuclear Research annual report 1991

    International Nuclear Information System (INIS)

    Sadowski, M.; Pawlowicz, W.

    1992-02-01

    Department of Thermonuclear Research Annual Report 1991 presents a short review of theoretical, experimental, and technological studies carried out within the framework of two research programs: Plasma Physics and Development of Diagnostics Data Acquisition. Theoretical studies of a tokamak edge plasma, validity of inverse Abel transformation for strongly refracting objects, simulation of the pulse generators operation, and a numerical analysis of electron capture in p + H + collisions, are described. Experimental studies of corpuscular beams and X-rays from different plasma facilities, development of diagnostic techniques and of data acquisition systems, as well as experiments with the generation of cryogenic pellets for plasma research, are shortly summarized. Also presented are technological studies concerning the modernization of the PF- and RPI-type facilities and the application of the IONOTRON-type devices for the modification of semiconductor and metal surfaces. (author). 27 refs, 24 figs

  15. Thermonuclear model for γ-ray bursts

    International Nuclear Information System (INIS)

    Woosley, S.E.

    1981-01-01

    The evolution of magnetized neutron stars with field strengths of approx. 10 12 gauss that are accreting mass onto kilometer-sized polar regions at a rate of approx. 13 M 0 yr -1 is examined. Based on the results of one-dimensional calculations, one finds that stable hydrogen burning, mediated by the hot CNO-cycle, will lead to a critical helium mass in the range 10 20 to 10 22 g km -2 . Owing to the extreme degeneracy of the electron gas providing pressure support, helium burning occurs as a violent thermonuclear runaway which may propagate either as a convective deflagration (Type I burst) or as a detonation wave (Type II burst). Complete combustion of helium into 56 Ni releases from 10 38 to 10 40 erg km -2 and pushes hot plasma with β > 1 above the surface of the neutron star. Rapid expansion of the plasma channels a substantial fraction of the explosion energy into magnetic field stress. Spectral properties are expected to be complex with emission from both thermal and non-thermal processes. The hard γ-outburst of several seconds softens as the event proceeds and is followed by a period, typically of several minutes duration, of softer x-ray emission as the subsurface ashes of the thermonuclear explosion cool. In this model, most γ-ray bursts currently being observed are located at a distance of several hundred parsecs and should recur on a timescale of months to centuries with convective deflagrations (Type I bursts) being the more common variety. An explanation for Jacobson-like transients is also offered

  16. Continuously renewed wall for a thermonuclear reactor

    International Nuclear Information System (INIS)

    Livshits, A.I.; Pustovojt, YU.M.; Samartsev, A.A.; Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow. Inst. Atomnoj Ehnergii)

    1982-01-01

    The possibility of creating a continuously renewed first wall of a thermonuclear reactor is experimentally investigated. The following variants of the wall are considered: the wall is double, its part turned to plasma is made of comparatively thin material. The external part separated from it by a small gap appears to be protected from interaction with plasma and performs structural functions. The gap contains the mixture of light helium and hydrogen and carbon-containing gas. The light gas transfers heat from internal part of the wall to the external part. Carbon-containing gas provides continuous renewal of carbon coating of the operating surface. The experiment is performed with palladium membrane 20 μm thick. Carbon is introduced into the membrane by benzol pyrolysis on one of the surfaces at the membrane temperature of 900 K. Carbon removal from the operating side of the wall due to its spraying by fast particles is modelled by chemical itching with oxygen given to the operating membrane wall. Observation of the carbon release on the operating surface is performed mass-spectrometrically according to the observation over O 2 transformation into CO and CO 2 . It is shown that in cases of benzol pressure of 5x10 -7 torr, carbon current on the opposite surface is not less than 3x10 12 atoms/sm 2 s and corresponds to the expected wall spraying rate in CF thermonuclear reactors. It is also shown that under definite conditions the formation and maintaining of a through protective carbon coating in the form of a monolayer or volumetric phase is possible

  17. Localized thermonuclear runaways and volcanoes on degenerate dwarf stars

    Energy Technology Data Exchange (ETDEWEB)

    Shara, M.M.

    1982-10-15

    Practically all studies to date of thermonuclear runaways on degenerate dwarf stars in binary systems have considered only spherically symmetric eruptions. We emphasize that even slightly non-spherically symmetric accretion leads to transverse temperature gradients in the dwarfs' accreted envelopes. Over a rather broad range of parameter space, thermalization time scales in accreted envelopes are much longer than thermonuclear runaway time scales. Thus localized thermonuclear runaways (i.e., runaways much smaller than the host degenerate star) rather than spherically symmetric global eruptions are likely to occur on many degenerate dwarfs. Localized runaways are more likely to occur on more massive and/or hotter dwarfs.

  18. RS-WebPredictor

    DEFF Research Database (Denmark)

    Zaretzki, J.; Bergeron, C.; Huang, T.-W.

    2013-01-01

    Regioselectivity-WebPredictor (RS-WebPredictor) is a server that predicts isozyme-specific cytochrome P450 (CYP)-mediated sites of metabolism (SOMs) on drug-like molecules. Predictions may be made for the promiscuous 2C9, 2D6 and 3A4 CYP isozymes, as well as CYPs 1A2, 2A6, 2B6, 2C8, 2C19 and 2E1....... RS-WebPredictor is the first freely accessible server that predicts the regioselectivity of the last six isozymes. Server execution time is fast, taking on average 2s to encode a submitted molecule and 1s to apply a given model, allowing for high-throughput use in lead optimization projects.......Availability: RS-WebPredictor is accessible for free use at http://reccr.chem.rpi.edu/ Software/RS-WebPredictor....

  19. Probing thermonuclear burning on accreting neutron stars

    Science.gov (United States)

    Keek, L.

    2008-12-01

    Neutron stars are the most compact stars that can be directly observed, which makes them ideal laboratories to study physics at extreme densities. Neutron stars in low-mass X-ray binaries accrete hydrogen and helium from a lower-mass companion star through Roche lobe overflow. This matter undergoes thermonuclear burning in the neutron star envelope, creating carbon and heavier elements. The fusion process may proceed in an unstable manner, resulting in a thermonuclear runaway. Within one second the entire surface is burned, which is observable as a sharp rise in the emitted X-ray flux: a type I X-ray burst. Afterwards the neutron star surface cools down on a timescale of ten to one hundred seconds. During these bursts the surface of an accreting neutron star can be observed directly, which makes them instrumental for studying this type of stars. We have studied rare kinds of X-ray bursts. One such rare burst is the superburst, which lasts a thousand times longer than an ordinary burst. Superbursts are thought to result from the explosive burning of a thick carbon layer, which lies deeper inside the neutron star, close to a layer known as the crust. A prerequisite for the occurrence of a superburst is a high enough temperature, which is set by the temperature of the crust and the heat conductivity of the envelope. The latter is lowered by the presence of heavy elements that are produced during normal X-ray bursts. Using a large set of observations from the Wide Field Camera's onboard the BeppoSAX satellite, we find that, at high accretion rate, sources which do not exhibit normal bursts likely have a longer superburst recurrence time, than the observed superburst recurrence time of one burster. We analyze in detail the first superburst from a transient source, which went into outburst only 55 days before the superburst. Recent models of the neutron star crust predict that this is too small a time to heat the crust sufficiently for superburst ignition, indicating

  20. Brazilian programme for plasma physics and controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    Chian, A.C.L.; Reusch, M.F.; Nascimento, I.C.; Pantuso-Sudano, J.

    1992-01-01

    A proposal for a National Programme of Plasma Physics and Controlled Thermonuclear Fusion in Brazil is presented, aimimg the dissemination of the researchers thought in plasma physics for the national authorities and the scientific community. (E.O.)

  1. An electromagnetic spherical phased array thermonuclear fusion reactor

    International Nuclear Information System (INIS)

    Okress, E.C.

    1983-01-01

    Discussed are salient physics aspects of a microwave singly reentrant spherical periodic phased array of uniformally distributed identical coaxial radiation elements in an essentially simulated infinite array environment. The array is capable of maintaining coherence or phase control (to the limit of the order of 300 GHz) of its spherically converging electromagnetic transverse magnetic mode radiation field, for confinement (and heating) of thermonuclear plasma in steady-state or inertial thermonuclear fusion. The array also incorporates capability for coaxial directional coupler extraction of fusionpower. The radiation elements of the array are shielded against DT Thermonuclear plasma emissions (i.e., neutrons and bremsstrahlung) by either sufficiently (available) low less tangent and cooled, spherically concentric shield (e.g., Titanium oxide); or alternately by identical material dome windows mounted on each radiation element's aperture of the array. The pump microwave power required for thermonuclear fusion feasibility comprises an array of phase-locked available klystron amplifiers (comparable gyratron amplifiers remain to be developed)

  2. Thermonuclear generation program: risks and safety

    International Nuclear Information System (INIS)

    Goes, Alexandre Gromann de Araujo

    1999-01-01

    This work deals with the fundamental concepts of risk and safety related to nuclear power generation. In the first chapter, a general evaluation of the various systems for energy generation and their environmental impacts is made. Some definitions for safety and risk are suggested, based on the already existing regulatory processes and also on the current tendencies of risk management. Aspects regarding the safety culture are commented. The International Nuclear Event Scale (INES), a coherent and clear mechanism of communication between nuclear specialists and the general public, is analyzed. The second chapter examines the thermonuclear generation program in Brazil and the role of the National Nuclear Energy Commission. The third chapter presents national and international scenarios in terms of safety and risks, available policies and the main obstacles for future development of nuclear energy and nuclear engineering, and strategies are proposed. In the last chapter, comments about possible trends and recommendations related to practical risk management procedures, taking into account rational criteria for resources distribution and risk reduction are made, envisaging a closer integration between nuclear specialists and the society as a whole, thus decreasing the conflicts in a democratic decision-making process

  3. Power source device for thermonuclear device

    International Nuclear Information System (INIS)

    Ozaki, Akira.

    1992-01-01

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

  4. Helical type thermonuclear device and control method

    International Nuclear Information System (INIS)

    Ishigaki, Yukio.

    1990-01-01

    In a conventional helical type thermonuclear device, electric current flows in the toroidal direction under magnetic fields of helical coils and vertical magnetic coils, by which a circulating electric field is caused. Therefore, there is a problem that electrons as a seed are generated by cosmic rays, etc., the electrons are confined in a magnetic field boundary, are accelerated by the circulating electric field, to reach a high energy level, collide against structures in a vacuum vessel and emit a great amount of X-rays. Then, compensation coils for offsetting the magnetic fields generated upon energization and deenergization of the vertical magnetic coils and the power source therefor are disposed at the positions opposing to each other on both sides of the vertical magnetic coils for controlling the variation coefficient rate of electric current upon energization and deenergization of the vertical magnetic coils. Since the compensation coils also offset the magnetic field generated upon energization and deenergization of the vertical magnetic field coils by this control, the circulating magnetic field is not caused in the vacuum vessel to reduce the X-ray radiation by electrons at high energy level. (N.H.)

  5. Department of Thermonuclear Research annual report 1992

    International Nuclear Information System (INIS)

    Sadowski, M.; Pawlowicz, W.

    1993-02-01

    Department of Thermonuclear Research annual report 1992 presents the most important results of theoretical, experimental and technological studies carried out within a framework of the research program - Plasma Physics and an additional grant - Study of Surface Melting of Selected Materials with a Plasma stream (contract with the Committee for Scientific Research - KBN). Theoretical studies of tokamak edge plasmas, atomic collisions, heat transfer, and numerical codes, are shortly summarized. Experimental studies of X-rays and particles emitted from Plasma-Focus facilities, calibration of nuclear track detectors, optimization of PF discharges with additional gas targets, magnetic probe measurements, new diagnostic and experimental arrangements, as well as mass- and energy-analysis of ions from IONOTRON-type devices, are described. Also presented are technological studies, modernization of experimental facilities, design of new control systems, tests on uniformity and reproducibility of plasma streams as the formation of photovoltaic cells and modifications of solid surfaces by means of plasma streams from the IONOTRON and PF devices. (author)

  6. Department of Thermonuclear Research annual report 1992

    Energy Technology Data Exchange (ETDEWEB)

    Sadowski, M; Pawlowicz, W [eds.; Soltan Inst. for Nuclear Studies, Otwock-Swierk (Poland)

    1993-02-01

    Department of Thermonuclear Research annual report 1992 presents the most important results of theoretical, experimental and technological studies carried out within a framework of the research program - Plasma Physics and an additional grant - Study of Surface Melting of Selected Materials with a Plasma stream (contract with the Committee for Scientific Research - KBN). Theoretical studies of tokamak edge plasmas, atomic collisions, heat transfer, and numerical codes, are shortly summarized. Experimental studies of X-rays and particles emitted from Plasma-Focus facilities, calibration of nuclear track detectors, optimization of PF discharges with additional gas targets, magnetic probe measurements, new diagnostic and experimental arrangements, as well as mass- and energy-analysis of ions from IONOTRON-type devices, are described. Also presented are technological studies, modernization of experimental facilities, design of new control systems, tests on uniformity and reproducibility of plasma streams as the formation of photovoltaic cells and modifications of solid surfaces by means of plasma streams from the IONOTRON and PF devices. (author).

  7. Energy balance of controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    Hashmi, M.; Staudenmaier, G.

    2000-01-01

    It is shown that a discrepancy and incompatibility persist between basic physics and fusion-literature regarding the radiation losses from a thermonuclear plasma. Whereas the fusion-literature neglects the excitation or line radiation completely, according to basic physics it depends upon the prevailing conditions and cannot be neglected in general. Moreover, for a magnetized plasma, while the fusion-literature assumes a self-absorption or reabsorption of cyclotron or synchrotron radiation emitted by the electrons spiraling along the magnetic field, the basic physics does not allow any effective reabsorption of cyclotron or synchrotron radiation. As is demonstrated, fallacious assumptions and notions, which somehow or other crept into the fusion-literature, are responsible for this discrepancy. In the present work, the theory is corrected. On the grounds of basic physics, a complete energy balance of magnetized and non-magnetized plasmas is presented for pulsed, stationary and self-sustaining operations by taking into account the energy release by reactions of light nuclei as well as different kinds of diffusive (conduction) and radiative (bremsstrahlung, cyclotron or synchrotron radiation and excitation radiation) energy losses. Already the energy losses by radiation make the energy balance negative. Hence, a fusion reactor-an energy producing device-seems to be beyond the realms of realization. (orig.)

  8. Operating large controlled thermonuclear fusion research facilities

    International Nuclear Information System (INIS)

    Gaudreau, M.P.J.; Tarrh, J.M.; Post, R.S.; Thomas, P.

    1987-01-01

    The MIT Tara Tandem Mirror is a large, state of the art controlled thermonuclear fusion research facility. Over the six years of its design, implementation, and operation, every effort was made to minimize cost and maximize performance by using the best and latest hardware, software, and scientific and operational techniques. After reviewing all major DOE fusion facilities, an independent DOE review committee concluded that the Tara operation was the most automated and efficient of all DOE facilities. This paper includes a review of the key elements of the Tara design, construction, operation, management, physics milestones, and funding that led to this success. The authors emphasize a chronological description of how the system evolved from the proposal stage to a mature device with an emphasis on the basic philosophies behind the implementation process. This description can serve both as a qualitative and quantitative database for future large experiment planning. It includes actual final costs and manpower spent as well as actual run and maintenance schedules, number of data shots, major system failures, etc. The paper concludes with recommendations for the next generation of facilities

  9. BAYESIAN ESTIMATION OF THERMONUCLEAR REACTION RATES

    Energy Technology Data Exchange (ETDEWEB)

    Iliadis, C.; Anderson, K. S. [Department of Physics and Astronomy, University of North Carolina at Chapel Hill, Chapel Hill, NC 27599-3255 (United States); Coc, A. [Centre de Sciences Nucléaires et de Sciences de la Matière (CSNSM), CNRS/IN2P3, Univ. Paris-Sud, Université Paris–Saclay, Bâtiment 104, F-91405 Orsay Campus (France); Timmes, F. X.; Starrfield, S., E-mail: iliadis@unc.edu [School of Earth and Space Exploration, Arizona State University, Tempe, AZ 85287-1504 (United States)

    2016-11-01

    The problem of estimating non-resonant astrophysical S -factors and thermonuclear reaction rates, based on measured nuclear cross sections, is of major interest for nuclear energy generation, neutrino physics, and element synthesis. Many different methods have been applied to this problem in the past, almost all of them based on traditional statistics. Bayesian methods, on the other hand, are now in widespread use in the physical sciences. In astronomy, for example, Bayesian statistics is applied to the observation of extrasolar planets, gravitational waves, and Type Ia supernovae. However, nuclear physics, in particular, has been slow to adopt Bayesian methods. We present astrophysical S -factors and reaction rates based on Bayesian statistics. We develop a framework that incorporates robust parameter estimation, systematic effects, and non-Gaussian uncertainties in a consistent manner. The method is applied to the reactions d(p, γ ){sup 3}He, {sup 3}He({sup 3}He,2p){sup 4}He, and {sup 3}He( α , γ ){sup 7}Be, important for deuterium burning, solar neutrinos, and Big Bang nucleosynthesis.

  10. Vacuum exhaust duct used for thermonuclear device

    International Nuclear Information System (INIS)

    Tachikawa, Nobuo; Kondo, Mitsuaki; Honda, Tsutomu.

    1990-01-01

    The present invention concerns a vacuum exhaust duct used for a thermonuclear device. A cylindrical metal liners is lined with a gap to the inside of a vacuum exhaust duct main body. Bellows are connected to both ends of the metal liners and the end of the bellows is welded to the vacuum exhaust duct main body. Futher, a heater is mounted to the metal liner on the side of the vacuum exhaust duct main body, and the metal liner is heated by the heater to conduct baking for the vacuum exhaust duct main body. Accordingly, since there is no requirement for elevating the temperature of the vacuum exhaust duct upon conducting baking, the vacuum exhaust duct scarcely suffers substantial deformation due to heat expansion. Further, there is also no substantial deformation for the bellows disposed between the outer circumference of the vacuum vessel and a portion of a vacuum exhaust duct, so that the durability of the bellows is greatly improved. (I.S.)

  11. High heat flux device of thermonuclear device

    International Nuclear Information System (INIS)

    Tachikawa, Nobuo.

    1994-01-01

    The present invention provides an equipments for high heat flux device (divertor) of a thermonuclear device, which absorbs thermal deformation during operation, has a high installation accuracy, and sufficiently withstands for thermal stresses. Namely, a heat sink member is joined to a structural base. Armour tiles are joined on the heat sink member. Cooling pipes are disposed between the heat sink member and the armour tiles. With such a constitution, the heat sink member using a highly heat conductive material having ductility, such as oxygen free copper, the cooling pipes using a material having excellent high temperature resistance and excellent elongation, such as aluminum-dispersed reinforced copper, and the armour tiles are completely joined on the structural base. Therefore, when thermal deformation tends to cause in the high heat flux device such as a divertor, cooling pipes cause no plastic deformation because of their high temperature resistance, but the heat sink member such as a oxygen free copper causes plastic deformation to absorb thermal deformation. As a result, the high heat flux device such as a divertor causes no deformation. (I.S.)

  12. Operating large controlled thermonuclear fusion research facilities

    International Nuclear Information System (INIS)

    Gaudreau, M.P.J.; Tarrh, J.M.; Post, R.S.; Thomas, P.

    1987-10-01

    The MIT Tara Tandem Mirror is a large, state of the art controlled thermonuclear fusion research facility. Over the six years of its design, implementation, and operation, every effort was made to minimize cost and maximize performance by using the best and latest hardware, software, and scientific and operational techniques. After reviewing all major DOE fusion facilities, an independent DOE review committee concluded that the Tara operation was the most automated and efficient of all DOE facilities. This paper includes a review of the key elements of the Tara design, construction, operation, management, physics milestones, and funding that led to this success. We emphasize a chronological description of how the system evolved from the proposal stage to a mature device with an emphasis on the basic philosophies behind the implementation process. This description can serve both as a qualitative and quantitative database for future large experiment planning. It includes actual final costs and manpower spent as well as actual run and maintenance schedules, number of data shots, major system failures, etc. The paper concludes with recommendations for the next generation of facilities. 13 refs., 15 figs., 3 tabs

  13. Controlled thermonuclear fusion: research on magnetic fusion

    International Nuclear Information System (INIS)

    Paris, P.J.

    1988-12-01

    Recent progress in thermonuclear fusion research indicates that the scientists' schedule for the demonstration of the scientific feasibility will be kept and that break-even will be attained in the course of the next decade. To see the implementation of ignition, however, the generation of future experiments must be awaited. These projects are currently under study. With technological research going on in parallel, they should at the same time contribute to the design of a reactor. Fusion reactors will be quite different from the fission nuclear reactors we know, and the waste of the plants will also be of a different nature. It is still too early to define the precise design of a fusion reactor. On the basis of a toric machine concept like that of the tokamak, we can, however, envisage that the problems with which we are confronted will be solved one after the other. As we have just seen, these will be the objectives of the future experimental installations where ignition will be possible and where the flux of fast neutrons will be so strong that they will allow the study of low-activation materials which will be used in the structure of the reactor. But this is also a task in which from now onwards numerous laboratories in Europe and in the world participate. The works are in fact punctiform, and often the mutual incidences can only be determined by an approach simulated by numerical codes. (author) 19 figs., 6 tabs., 8 refs

  14. Vacuum pumping for controlled thermonuclear reactors

    International Nuclear Information System (INIS)

    Watson, J.S.; Fisher, P.W.

    1976-01-01

    Thermonuclear reactors impose unique vacuum pumping problems involving very high pumping speeds, handling of hazardous materials (tritium), extreme cleanliness requirements, and quantitative recovery of pumped materials. Two principal pumping systems are required for a fusion reactor, a main vacuum system for evacuating the torus and a vacuum system for removing unaccelerated deuterium from neutral beam injectors. The first system must pump hydrogen isotopes and helium while the neutral beam system can operate by pumping only hydrogen isotopes (perhaps only deuterium). The most promising pumping techniques for both systems appear to be cryopumps, but different cryopumping techniques can be considered for each system. The main vacuum system will have to include cryosorption pumps cooled to 4.2 0 K to pump helium, but the unburned deuterium-tritium and other impurities could be pumped with cryocondensation panels (4.2 0 K) or cryosorption panels at higher temperatures. Since pumping speeds will be limited by conductance through the ducts and thermal shields, the pumping performance for both systems will be similar, and other factors such as refrigeration costs are likely to determine the choice. The vacuum pumping system for neutral beam injectors probably will not need to pump helium, and either condensation or higher temperature sorption pumps can be used

  15. Thermonuclear model for x-ray transients

    International Nuclear Information System (INIS)

    Wallace, R.K.; Woosley, S.E.; Weaver, T.A.

    1982-01-01

    The thermonuclear evolution of a 1.41 M sub solar neutron star accreting both solar and metal-deficient mixtures of hydrogen, helium, and heavy elements at rates ranging from about 10 -11 to 10 -10 M sub solar per year is examined using a one-dimensional numerical model. The metal deficient compositions may result either from placement of the neutron star in a binary system with a Population II red giant or from gravitational settling of heavy ions in the accreted material. For such accretion rates and metallicities, hydrogen burning, mediated by the β-limited CNO cycle, is stable and leads to the accumulation of a thick helium layer with mass 10 23 to 10 25 g and temperature 0.7 less than or equal to T 8 less than or equal to 1.2. Helium ignition occurs under extremely degenerate circumstances and is catastrophically violent. In the lower t helium shells this runaway is propagated as a convective deflagration, for the thicker layers a detonation front is set up which steepens into a strong relativistic shock wave in the neutron star envelope. In all models greatly super-Eddington luminosities in the outer layers of the neutron star lead to a sustained epoch of radiatively driven mass loss. Observationally, such models may correspond to rapid x-ray transients. The hopeless prospect for constructing a one-dimensional model for γ-ray bursts without magnetic field confinement is discussed and uncertainties pointed out in the strong screening correction for helium burning reaction

  16. Tokamak nonmaxwellian plasma dynamics in thermonuclear regime

    International Nuclear Information System (INIS)

    Cotsaftis, M.

    1987-01-01

    To reach ignition in a Tokamak plasma, large additional power P aux has to be injected in the device on top of the Joule heating P OH =VI r , V the plasma loop voltage, I r the resistive port of plasma current. Typi-cally JH ∼ 1 KeV, whereas ignition would requi- re IG ∼ 7-10 KeV. To gain this factor 7, one at least should inject additional power P aux ∼ 7P OH , supposing that nothing, especially the heat transport, is modified. This is by far not the case, with the so-called energy lifetime degradation, largely observed in oil experiments (but less dramatic with divertors), where energy lifetime tau E behaves like P tot -b with b∼1/2. In large machines where ignition temperature is the target to be imperiously reached, this implies to inject a very large power, typically P aux ∼ 50 to 100 MW, depending on size and parameters and on actual transport. So it is of importance with such figures, or even larger ones owing to uncertain ties, to optimize at best injected power by increasing its efficiency, both with respect to possible transport laws, and to physical phenomena governing heat flow in the system from the sources. This leads to the concept of scenarios, as time sequences of power input, where physical properties of the plasma system are used to build up ion temperature so that ignition is reached with minimum P tot = P OH + P aux and with fixed Q = Q o > 1. Elements for this study are given. The method is outlined. The resulting system of equations describing the evolution of a thermonuclear plasma is given

  17. THE COMPOSITION OF INTERSTELLAR GRAINS TOWARD ζ OPHIUCHI: CONSTRAINING THE ELEMENTAL BUDGET NEAR THE DIFFUSE-DENSE CLOUD TRANSITION

    Energy Technology Data Exchange (ETDEWEB)

    Poteet, Charles A.; Whittet, Douglas C. B. [New York Center for Astrobiology, Department of Physics, Applied Physics and Astronomy, Rensselaer Polytechnic Institute, 110 Eighth Street, Troy, NY 12180 (United States); Draine, Bruce T., E-mail: charles.poteet@gmail.com [Princeton University Observatory, Peyton Hall, Princeton, NJ 08544 (United States)

    2015-03-10

    We investigate the composition of interstellar grains along the line of sight toward ζ Ophiuchi, a well-studied environment near the diffuse-dense cloud transition. A spectral decomposition analysis of the solid-state absorbers is performed using archival spectroscopic observations from the Spitzer Space Telescope and Infrared Space Observatory. We find strong evidence for the presence of sub-micron-sized amorphous silicate grains, principally comprised of olivine-like composition, with no convincing evidence of H{sub 2}O ice mantles. However, tentative evidence for thick H{sub 2}O ice mantles on large (a ≈ 2.8 μm) grains is presented. Solid-state abundances of elemental Mg, Si, Fe, and O are inferred from our analysis and compared to standard reference abundances. We find that nearly all of the Mg and Si atoms along the line of sight reside in amorphous silicate grains, while a substantial fraction of the elemental Fe resides in compounds other than silicates. Moreover, we find that the total abundance of elemental O is largely inconsistent with the adopted reference abundances, indicating that as much as ∼156 ppm of interstellar O is missing along the line of sight. After taking into account additional limits on the abundance of elemental O in other O-bearing solids, we conclude that any missing reservoir of elemental O must reside on large grains that are nearly opaque to infrared radiation.

  18. ROBATEL RS 24 packaging

    International Nuclear Information System (INIS)

    Robatel, M.; Bochard, C.

    1986-01-01

    The ROBATEL RS 24 packaging for light-water reactor fuel assemblies is discussed. The cask uses a strength frame of carbon steel sheets, lead gamma ray shielding, neutron shielding of aluminous concrete, a thermal protection system for the gamma shielding, and a natural convection thermal transfer system

  19. Application of controlled thermonuclear reactor fusion energy for food production

    International Nuclear Information System (INIS)

    Dang, V.D.; Steinberg, M.

    1975-06-01

    Food and energy shortages in many parts of the world in the past two years raise an immediate need for the evaluation of energy input in food production. The present paper investigates systematically (1) the energy requirement for food production, and (2) the provision of controlled thermonuclear fusion energy for major energy intensive sectors of food manufacturing. Among all the items of energy input to the ''food industry,'' fertilizers, water for irrigation, food processing industries, such as beet sugar refinery and dough making and single cell protein manufacturing, have been chosen for study in detail. A controlled thermonuclear power reactor was used to provide electrical and thermal energy for all these processes. Conceptual design of the application of controlled thermonuclear power, water and air for methanol and ammonia synthesis and single cell protein production is presented. Economic analysis shows that these processes can be competitive. (auth)

  20. Capacitor requirements for controlled thermonuclear experiments and reactors

    International Nuclear Information System (INIS)

    Boicourt, G.P.; Hoffman, P.S.

    1975-01-01

    Future controlled thermonuclear experiments as well as controlled thermonuclear reactors will require substantial numbers of capacitors. The demands on these units are likely to be quite severe and quite different from the normal demands placed on either present energy storage capacitors or present power factor correction capacitors. It is unlikely that these two types will suffice for all necessary Controlled Thermonuclear Research (CTR) applications. The types of capacitors required for the various CTR operating conditions are enumerated. Factors that influence the life, cost and operating abilities of these types of capacitors are discussed. The problems of capacitors in a radiation environment are considered. Areas are defined where future research is needed. Some directions that this research should take are suggested. (U.S.)

  1. The ''Dolphin'' power laser installation for spherical thermonuclear target heating

    International Nuclear Information System (INIS)

    Basov, N.G.; Bykovskij, N.E.; Danilov, A.E.

    1978-01-01

    12-channel laser installation the ''Dolphin'' for thermonuclear target heating in the radiation spheric geometry has been developed to carry out series of physical investigations of laser-thermonuclear plasma system, optimization of target heating conditions and obtaining a comparatively large value of thermonuclear output in ratio to the energy of absorbed light radiation in the target. The description of installation main elements, consisting of the following components, is given: 1)neodymium laser with the maximum permissible radiation energy of 10kJ, with light pulse duration of 10 -10 /10 -9 c and radiation divergence of approximately 5x10 -4 rad; 2)vacuum chamber, where laser radiation interaction with plasma takes place; 3)diagnostic means of laser and plasma parameters and 4)focus system. The focus system provides a high degree of target spherical radiation symmetry at current maximum density on its surface of approximately 10 15 W/cm 2

  2. Capacitor requirements for controlled thermonuclear experiments and reactors

    International Nuclear Information System (INIS)

    Boicourt, G.P.; Hoffman, P.S.

    1975-01-01

    Future controlled thermonuclear experiments as well as controlled thermonuclear reactors will require substantial numbers of capacitors. The demands on these units are likely to be quite severe and quite different from the normal demands placed on either present energy storage capacitors or present power factor correction capacitors. It is unlikely that these two types will suffice for all necessary Controlled Thermonuclear Research (CTR) applications. The types of capacitors required for the various CTR operating conditions are enumerated. Factors that influence the life, cost and operating abilities of these types of capacitors are discussed. The problems of capacitors in a radiation environment are considered. Areas are defined where future research is needed. Some directions that this research should take are suggested

  3. Laser thermonuclear fusion with force confinement of hot plasma

    International Nuclear Information System (INIS)

    Korobkin, V.V.; Romanovsky, M.Y.

    1994-01-01

    The possibility of the utilization of laser radiation for plasma heating up to thermonuclear temperatures with its simultaneous confinement by ponderomotive force is investigated. The plasma is located inside a powerful laser beam with a tubelike section or inside a cavity of duct section, formed by several intersecting beams focused by cylindrical lenses. The impact of various physical processes upon plasma confinement is studied and the criteria of plasma confinement and maintaining of plasma temperature are derived. Plasma and laser beam stability is considered. Estimates of laser radiation energy necessary for thermonuclear fusion are presented

  4. The LOFT perspective on neutron star thermonuclear bursts

    DEFF Research Database (Denmark)

    in ’t Zand, J.J.M.; Altamirano, D.; Ballantyne, D. R.

    This is a White Paper in support of the mission concept of the Large Observatory for X-ray Timing (LOFT), proposed as a medium-sized ESA mission. We discuss the potential of LOFT for the study of thermonuclear X-ray bursts on accreting neutron stars. For a summary, we refer to the paper....

  5. Fabrication of an alumina torus for thermonuclear fusion containment

    International Nuclear Information System (INIS)

    Hauth, W.E.; Blake, R.D.; Dickinson, J.M.; Rutz, H.L.; Stoddard, S.D.

    1978-05-01

    A 235-cm-diam torus has been fabricated for plasma containment during thermonuclear fusion experiments. This 30-cm-diam torus consists of sixty 99.5%-alumina segments, 80% of which are assembled by forming vacuum-tight ceramic-to-ceramic seals. Selection of sealing materials and techniques are discussed

  6. Feasibility studies of thermonuclear neutron capture synthesis of SHE

    International Nuclear Information System (INIS)

    Meldner, H.W.

    1978-01-01

    A variety of thermonuclear neutron sources and neutron capture targets were investigated for their potential of allowing signigicant production of heavy, perhaps superheavy, isotopes. The neutron sources considered range from inertial confinement microexplosives to (underground) macroexplosives. Optimal capture targets appear to be composites containing uranium and protactinium. 1 figure

  7. Sonoluminescence, shock waves, and micro-thermonuclear fusion

    International Nuclear Information System (INIS)

    Moss, W.C.; Clarke, D.B.; White, J.W.; Young, D.A.

    1995-08-01

    We have performed numerical hydrodynamic simulations of the growth and collapse of a sonoluminescing bubble in a liquid. Our calculations show that spherically converging shock waves are generated during the collapse of the bubble. The combination of the shock waves and a realistic equation of state for the gas in the bubble provides an explanation for the measured picosecond optical pulse widths and indicates that the temperatures near the center of the bubble may exceed 3O eV. This leads naturally to speculation about obtaining micro-thermonuclear fusion in a bubble filled with deuterium (D 2 ) gas. Consequently, we performed numerical simulations of the collapse of a D 2 bubble in D 2 0. A pressure spike added to the periodic driving amplitude creates temperatures that may be sufficient to generate a very small, but measurable number of thermonuclear D-D fusion reactions in the bubble

  8. Atypical Thermonuclear Supernovae from Tidally Crushed White Dwarfs

    International Nuclear Information System (INIS)

    Rosswog, S.; Ramirez-Ruiz, E.; Hix, William Raphael

    2008-01-01

    Suggestive evidence has accumulated that intermediate mass black holes (IMBHs) exist in some globular clusters. Some stars will inevitably wander sufficiently close to the hole to suffer a tidal disruption. IMBHs can disrupt not only solar-type stars but also compact white dwarf stars. We investigate the fate of white dwarfs that approach the hole close enough to be disrupted and compressed to such an extent that explosive nuclear burning is triggered. Based on a precise modeling of the gas dynamics together with the nuclear reactions, it is argued that thermonuclear ignition is a natural outcome for white dwarfs of all masses passing well within the tidal radius. A good fraction of the star is accreted, yielding high luminosities that persist for up to a year. A peculiar, underluminous thermonuclear explosion accompanied by a soft X-ray transient signal would, if detected, be a compelling testimony for the presence of an IMBH

  9. 1D thermonuclear model for x-ray transients

    International Nuclear Information System (INIS)

    Wallace, R.K.

    1982-01-01

    The thermonuclear evolution of a 1.41 M solar mass neutron star, with a radius of 14.3 km, accreting various mixtures of hydrogen, helium, and heavy elements at rates of 10 -11 to 10 -10 M solar mass/yr is examined, in conjunction with S.E. Woosley and T.A. Weaver, using a one-dimensional numerical model. We have ignored any effects due to general relativity or magnetic fields. Two cases shall be discussed. In both models, the accretion rate is such that the hydrogen shell burns to helium in steady state, with the hydrogen burning stabilized by the β-limited CNO cycle. A thick helium shell is produced, which is eventually ignited under extremely degenerate conditions, producing a thermonuclear runaway

  10. Overview of International Thermonuclear Experimental Reactor (ITER) engineering design activities*

    Science.gov (United States)

    Shimomura, Y.

    1994-05-01

    The International Thermonuclear Experimental Reactor (ITER) [International Thermonuclear Experimental Reactor (ITER) (International Atomic Energy Agency, Vienna, 1988), ITER Documentation Series, No. 1] project is a multiphased project, presently proceeding under the auspices of the International Atomic Energy Agency according to the terms of a four-party agreement among the European Atomic Energy Community (EC), the Government of Japan (JA), the Government of the Russian Federation (RF), and the Government of the United States (US), ``the Parties.'' The ITER project is based on the tokamak, a Russian invention, and has since been brought to a high level of development in all major fusion programs in the world. The objective of ITER is to demonstrate the scientific and technological feasibility of fusion energy for peaceful purposes. The ITER design is being developed, with support from the Parties' four Home Teams and is in progress by the Joint Central Team. An overview of ITER Design activities is presented.

  11. Shock Ignition of Thermonuclear Fuel with High Areal Density

    International Nuclear Information System (INIS)

    Betti, R.; Zhou, C. D.; Anderson, K. S.; Theobald, W.; Solodov, A. A.; Perkins, L. J.

    2007-01-01

    A novel method by C. Zhou and R. Betti [Bull. Am. Phys. Soc. 50, 140 (2005)] to assemble and ignite thermonuclear fuel is presented. Massive cryogenic shells are first imploded by direct laser light with a low implosion velocity and on a low adiabat leading to fuel assemblies with large areal densities. The assembled fuel is ignited from a central hot spot heated by the collision of a spherically convergent ignitor shock and the return shock. The resulting fuel assembly features a hot-spot pressure greater than the surrounding dense fuel pressure. Such a nonisobaric assembly requires a lower energy threshold for ignition than the conventional isobaric one. The ignitor shock can be launched by a spike in the laser power or by particle beams. The thermonuclear gain can be significantly larger than in conventional isobaric ignition for equal driver energy

  12. Shock ignition of thermonuclear fuel with high areal density.

    Science.gov (United States)

    Betti, R; Zhou, C D; Anderson, K S; Perkins, L J; Theobald, W; Solodov, A A

    2007-04-13

    A novel method by C. Zhou and R. Betti [Bull. Am. Phys. Soc. 50, 140 (2005)] to assemble and ignite thermonuclear fuel is presented. Massive cryogenic shells are first imploded by direct laser light with a low implosion velocity and on a low adiabat leading to fuel assemblies with large areal densities. The assembled fuel is ignited from a central hot spot heated by the collision of a spherically convergent ignitor shock and the return shock. The resulting fuel assembly features a hot-spot pressure greater than the surrounding dense fuel pressure. Such a nonisobaric assembly requires a lower energy threshold for ignition than the conventional isobaric one. The ignitor shock can be launched by a spike in the laser power or by particle beams. The thermonuclear gain can be significantly larger than in conventional isobaric ignition for equal driver energy.

  13. Study on structural materials used in thermonuclear fusion technology

    International Nuclear Information System (INIS)

    Billa, R.; Amaral, D.

    1995-01-01

    The main problem related to the construction of a thermonuclear fusion reactor is the absence of suitable materials for the process, concerning to temperature limits, heat flux and life time. The first wall is the most critical part of the structure, being submitted to radiation effects, ionic corrosion and coolant, besides thermal fatigue and tension produced by cyclical burning. The AISI 316(17-12SPH) stainless steel is used as structural material, which has a wide known database. This work proposes an alternative material study to be used in the future thermonuclear fusion reactors. As a option a study on the utilization of Cr-Mn(Fe-17 Mn-10 Cr-0,1 C) steels and their alloy variations is presented

  14. Divertor, thermonuclear device and method of neutralizing high temperature plasma

    International Nuclear Information System (INIS)

    Ikegami, Hideo.

    1995-01-01

    The thermonuclear device comprises a thermonuclear reactor for taking place fusion reactions to emit fusion plasmas, and a divertor made of a hydrogen occluding material, and the divertor is disposed at a position being in contact with the fusion plasmas after nuclear fusion reaction. The divertor is heated by fusion plasmas after nuclear fusion reaction, and hydrogen is released from the hydrogen occluding material as a constituent material. A gas blanket is formed by the released hydrogen to cool and neutralize the supplied high temperature nuclear fusion plasmas. This prevents the high temperature plasmas from hitting against the divertor, elimination of the divertor by melting and evaporation, and solve a problem of processing a divertor activated by neutrons. In addition, it is possible to utilize hydrogen isotopes of fuels effectively and remove unnecessary helium. Inflow of impurities from out of the system can also be prevented. (N.H.)

  15. Trapping of pellet cloud radiation in thermonuclear plasmas

    International Nuclear Information System (INIS)

    Sergeev, V.Yu.; Miroshinikov, I.V.; Sudo, Shigeru; Namba, C.; Lisitsa, V.S.

    2001-01-01

    The experimental and theoretical data on radiation trapping in clouds of pellets injected into thermonuclear plasmas are presented. The theoretical modeling is performed in terms of equivalent Stark spectral line widths under condition of LTE (Sakha-Boltzman) in pellet cloud plasmas. It is shown that a domain of blackbody radiation could exist in hydrogen pellet clouds resulting in ''pellet disappearance'' effect which is absent in a case of impurity pellet clouds. Reasons for this difference are discussed. (author)

  16. Effect of excited states on thermonuclear reaction rates

    International Nuclear Information System (INIS)

    Sargood, D.G.

    1983-01-01

    Values of the ratio of the thermonuclear reaction rate of a reaction, with target nuclei in a thermal distribution of energy states, to the reaction rate with all target nuclei in their ground states are tabulated for neutron, proton and α-particle induced reactions on the naturally occurring nuclei from 20 Ne to 70 Zn, at temperatures of 1, 2, 3.5 and 5x10 9 K. The ratios are determined from reaction rates based on statistical model cross sections

  17. D+D thermonuclear fusion reactions with polarized particles

    International Nuclear Information System (INIS)

    Kozma, P.

    1986-01-01

    Polarization measurements from the 2 H(d, n) 3 He and 2 H(d, p) 3 H thermonuclear reactions at deuteron energies below 1 MeV are anayzed. Results of analysis enable to discuss the existence of 4 He excited states in the vicinity of d+d threshold energy as well as to extrapolate total cross-sections σ tot (d+d) into the region of very low energies

  18. What is the Plasma Focus Thermonuclear Pulsors Technology?

    International Nuclear Information System (INIS)

    Ramos, R.; Gonzalez, J.; Moreno, C.; Clausse, A.

    2003-01-01

    In this paper we describe a type of neutron generators, called Plasma Focus, which is suitable to several applications, where traditional generators are non-applicable.The main characteristics are its transportability and to be non-contaminating, which would allow in-situ tests.The Plasma Focus, produces neutron pulses by thermonuclear fusion reactions, satisfy these requirements and it is comparatively non expensive.This last feature would assure competitivity in the neutron sources market

  19. Role of thermonuclear instability in recent models of nova stars

    Energy Technology Data Exchange (ETDEWEB)

    Secco, L [Padua Univ. (Italy). Ist. di Astronomia

    1981-10-11

    In this paper we review models of nova-star explosion based on the original suggestion by Kraft and developed during about ten years (from 1967). We aim at summarizing here the most salient results of those theoretical models and to point out the many aspects of the problems that are still unsettled. In particular, we analyse thermonuclear instabilities both in perfect and electron-degenerate gas, since they seem to be at the base of the nova explosion phenomena.

  20. Paula, RS, Brasil

    Directory of Open Access Journals (Sweden)

    Solon Jonas Longhi

    2006-01-01

    Full Text Available The present work is part of studies and researches developed at Long Duration Ecological Project - PELD/CNPq, located in São Francisco de Paula’s National Forest (FLONA, RS. The objective of this paper was to identify and to characterize the different stages of succession in mixed rainy forest remains. The work had been accomplished in ten permanent conglomerates of 100m x 100m (10.000m2, which were divided into ten strips of 10m x 100m (1.000m2 and these ones subdivided into ten subunits of 10m x 10m (100m2. In this research, a strip of 10m x 100m was selected for each conglomerate, totaling 100 subunits (stands, where it had been installed, at DBH height, dendrometric bands in all trees with CBH ≥ 30cm, for annual diameters measurement. The cluster analysis was accomplished through the Twinspan program, using a data matrix with ninety-nine stands (one of those was unconsidered by the absence of individuals with CBH ≥ 30cm having as variable the annual increment in diameter (obtained in two years of observations of sixty nine species. Three floristic groups was obtained, indicating stages of succession in the forest: a group separated a less developed stage of succession denominated secondary forest, being Nectandra megapotamica and Cryptocaria aschersoniana the indicative species; a second group indicated an intermediate stage of succession in the forest, being Sebastiania commersoniana and Ocotea pulchella the indicative species; and a third group of primary forest, whose indicative species was Araucaria angustifolia.

  1. Integration of element technology and system supporting thermonuclear fusion

    International Nuclear Information System (INIS)

    2003-01-01

    A special committee for integrated system technology survey on thermonuclear fusion (TNF) was begun on June, 1999, under an aim to generally summarize whole of shapes on technology to realize TNF reactor to summarize present state of every technologies and their positioning in whole of their TNF technology. On a base of survey of these recent informations, this report is comprehensively summarized for an integrated system technology on TNF. It has outlines on magnetic field enclosing method, outlines on inertia enclosing method, element technology supporting TNF, new power generation techniques, and ripple effects on TNF technology. (G.K.)

  2. Thermonuclear runaways in thick hydrogen rich envelopes of neutron stars

    Science.gov (United States)

    Starrfield, S. G.; Kenyon, S.; Truran, J. W.; Sparks, W. M.

    1981-01-01

    A Lagrangian, fully implicit, one dimensional hydrodynamic computer code was used to evolve thermonuclear runaways in the accreted hydrogen rich envelopes of 1.0 Msub solar neutron stars with radii of 10 km and 20 km. Simulations produce outbursts which last from about 750 seconds to about one week. Peak effective temeratures and luninosities were 26 million K and 80 thousand Lsub solar for the 10 km study and 5.3 millison and 600 Lsub solar for the 20 km study. Hydrodynamic expansion on the 10 km neutron star produced a precursor lasting about one ten thousandth seconds.

  3. The role of materials in controlled thermonuclear research

    Energy Technology Data Exchange (ETDEWEB)

    Craston, J L; Hancox, R; Robson, A E [U.K. Atomic Energy Authority, AERE, Harwell (United Kingdom); Kaufman, S; Miles, H T; Ware, A A; Wesson, J A [AEI Research Laboratory, Aldermaston (United Kingdom)

    1958-07-01

    It is the purpose of this paper to examine the processes occurring at the wall and to discuss their importance in the choice of materials both for present equipment and for future designs. The emphasis is laid primarily on plasma contamination but other effects are considered, such as thermal stress fatigue and radiation damage of the wall. The principal problems associated with the choice of wall material for a high current discharge tube have been discussed, both under the conditions which exist in present systems and under the conditions which are anticipated in a thermonuclear reactor.

  4. Ratcheting problems for ITER [International Thermonuclear Experimental Reactor

    International Nuclear Information System (INIS)

    Majumdar, S.

    1991-01-01

    Because of the presence of high cyclic thermal stress, pressure-induced primary stress, and disruption-induced high cyclic primary stress, ratcheting of the first wall poses a serious challenge to the designers of ITER (International Thermonuclear Experimental Reactor). Existing design tools such as the Bree diagram in the ASME Boiler and Pressure Vessels Code, are not directly applicable to ITER, because of important differences in geometry and loading modes. Available alternative models for ratcheting are discussed and new Bree diagrams, that are more relevant for fusion reactor applications, are proposed. 9 refs., 17 figs

  5. Zone-plate coded imaging of thermonuclear burn

    International Nuclear Information System (INIS)

    Ceglio, N.M.

    1978-01-01

    The first high-resolution, direct images of the region of thermonuclear burn in laser fusion experiments have been produced using a novel, two-step imaging technique called zone-plate coded imaging. This technique is extremely versatile and well suited for the microscopy of laser fusion targets. It has a tomographic capability, which provides three-dimensional images of the source distribution. It is equally useful for imaging x-ray and particle emissions. Since this technique is much more sensitive than competing imaging techniques, it permits us to investigate low-intensity sources

  6. Approximating the r-process on earth with thermonuclear explosions

    International Nuclear Information System (INIS)

    Becker, S.A.

    1992-01-01

    The astrophysical r-process can be approximately simulated in certain types of thermonuclear explosions. Between 1952 and 1969 twenty-three nuclear tests were fielded by the United States which had as one of their objectives the production of heavy transuranic elements. Of these tests, fifteen were at least partially successful. Some of these shots were conducted under the project Plowshare Peaceful Nuclear Explosion Program as scientific research experiments. A review of the program, target nuclei used, and heavy element yields achieved, will be presented as well as discussion of plans for a new experiment in a future nuclear test

  7. Thermonuclear reaction rates in a deuterium-tritium plasma

    International Nuclear Information System (INIS)

    Beckman, L.

    1978-12-01

    In a deuterium-tritium plasma six thermonuclear reactions take place between the deuterons, tritons and the 3 He-particles formed in about half of the d-d-reactions. The rate constants for these six reactions have been calculated from the latest evaluations of the reaction cross sections which were available. In some cases, notably the reactions t+t, t+ 3 He and 3 He+ 3 He, the number of published cross section measurements is small, and the uncertainty in the calculated rate constants consequently large. Analytical expressions for the rate constants as functions of the plasma temperature have been set up. (author)

  8. Flaw detection device for plasma facing wall in thermonuclear device

    International Nuclear Information System (INIS)

    Doi, Akira.

    1996-01-01

    The present invention concerns plasma facing walls of a thermonuclear device and provides a device for detecting a thickness of amour tiles accurately and efficiently with no manual operation. Namely, the position of the plasma facing surface of the amour tile is measured using a structure to which the amour tiles are to be disposed as a reference. Also in a case of disposing new armor tiles, the position of the plasma facing surface of the armor tiles is measured to thereby measure the wearing amount of the amour tiles based on the difference between the reference and the measured value. If a measuring means capable of measuring a plurality of amour tiles at once is used efficiency of the measurement and the detection can be enhanced. Several ten thousands of amour tiles are disposed to the plasma facing wall in a large scaled thermonuclear device, and a plenty of time was required for the detection. However, the present invention can improve the accuracy for the measurement and detection and provide time and labors-saving. (I.S.)

  9. Atomic and molecular physics of controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    Joachain, C.J.; Post, D.E.

    1983-01-01

    This book attempts to provide a comprehensive introduction to the atomic and molecular physics of controlled thermonuclear fusion, and also a self-contained source from which to start a systematic study of the field. Presents an overview of fusion energy research, general principles of magnetic confinement, and general principles of inertial confinement. Discusses the calculation and measurement of atomic and molecular processes relevant to fusion, and the atomic and molecular physics of controlled thermonuclear research devices. Topics include recent progress in theoretical methods for atomic collisions; current theoretical techniques for electron-atom and electronion scattering; experimental aspects of electron impact ionization and excitation of positive ions; the theory of charge exchange and ionization by heavy particles; experiments on electron capture and ionization by multiply charged ions; Rydberg states; atomic and molecular processes in high temperature, low-density magnetically confined plasmas; atomic processes in high-density plasmas; the plasma boundary region and the role of atomic and molecular processes; neutral particle beam production and injection; spectroscopic plasma diagnostics; and particle diagnostics for magnetic fusion experiments

  10. Nuclear Physics Constraints on the Characteristics of Astrophysical Thermonuclear Flashes

    International Nuclear Information System (INIS)

    Truran, James W

    2012-01-01

    We review the nuclear physics that is associated with the outbursts of Type Ia (thermonuclear) supernova explosions and with the thermonuclear runaway events that define the outbursts of both classical novae and recurrent novae. We describe how distinguishing characteristics of these two classes of astrophysical explosion are strongly dependent both upon fuel ignition in degenerate matter and upon the rates of critical charged-particle reaction rates and weak interaction rates. In this centennial celebration of the important contributions of Rutherford and his collaborators to our understanding of the structure of the nucleus of an atom, it is quite interesting to note the evolution of the α-particle scattering experiments described in Rutherford's seminal paper (Rutherford 1911) to current studies of α-particle induced reactions and their defining roles in studies of stellar, nova, and supernova nucleosynthesis. We identify and discuss for example: (1) the manner in which (α, p) reactions in proximity to the Z = N line carry the major flows from 12 C and 16 O to 56 Ni in Type Ia supernovae; and (2) the critical role of the 15 O(α, γ) 19 Ne reaction in possibly effecting 'breakout' of the Hot CNO cycles at the highest temperatures achievable in Classical Novae. In this contribution, we first review the current status our understanding of Type Ia supernova events and then that of Classical Novae.

  11. The Influence of Stellar Spin on Ignition of Thermonuclear Runaways

    Science.gov (United States)

    Galloway, Duncan K.; in ’t Zand, Jean J. M.; Chenevez, Jérôme; Keek, Laurens; Sanchez-Fernandez, Celia; Worpel, Hauke; Lampe, Nathanael; Kuulkers, Erik; Watts, Anna; Ootes, Laura; The MINBAR collaboration

    2018-04-01

    Runaway thermonuclear burning of a layer of accumulated fuel on the surface of a compact star provides a brief but intense display of stellar nuclear processes. For neutron stars accreting from a binary companion, these events manifest as thermonuclear (type-I) X-ray bursts, and recur on typical timescales of hours to days. We measured the burst rate as a function of accretion rate, from seven neutron stars with known spin rates, using a burst sample accumulated over several decades. At the highest accretion rates, the burst rate is lower for faster spinning stars. The observations imply that fast (>400 Hz) rotation encourages stabilization of nuclear burning, suggesting a dynamical dependence of nuclear ignition on the spin rate. This dependence is unexpected, because faster rotation entails less shear between the surrounding accretion disk and the star. Large-scale circulation in the fuel layer, leading to enhanced mixing of the burst ashes into the fuel layer, may explain this behavior; further numerical simulations are required to confirm this.

  12. Power supply for magnetic coils in thermonuclear devices

    International Nuclear Information System (INIS)

    Shimada, Ryuichi; Tamura, Sanae; Kishimoto, Hiroshi.

    1981-01-01

    Purpose: To decrease the load fluctuations in an external power supply, as well as to increase the operation efficiency capacity of thermonuclear devices. Constitution: Electrical power with the same frequency as that of a dynamo generator is supplied by a power supply-driving power source including a frequency converter and the like to DC converters for driving plasma-exciting and -controlling coils. At the same time, the electrical power from the frequency converter is supplied to the dynamo generator with flywheel to add accumulate energies to the EC converters. Accordingly, the energy for the great power pulses in a short time comprises the sum of the energy supplied from the dynamo generator with flywheel and the energy supplied continuously from the outside to eliminate the need of providing a stand-by period for the re-acceleration of the dynamo generator with flywheel even if the scale of the thermonuclear device is enlarged and energy consumed in one cycle is increased, whereby the decrease in the operation efficiency can be prevented and the capacity of the flywheel can be reduced. (Yoshino, Y.)

  13. 28. Zvenigorod conference on the plasma physics and controlled thermonuclear synthesis. Theses of reports

    International Nuclear Information System (INIS)

    2001-01-01

    Theses of reports, presented at the 28th Conference on the plasma physics and controlled thermonuclear synthesis (Zvenigorod, 19-23 February 2001) are published. 246 reports were heard at the following sections: magnetic confinement, theory and experiments; inertial thermonuclear synthesis; plasma processes and physics of gas-discharge plasma; physical bases of plasma technologies. 17 reports had the summarizing character [ru

  14. Isotopic hydrology of Berrocal area (Toledo, Spain): I: Tritium in springs with thermonuclear resources

    International Nuclear Information System (INIS)

    1995-01-01

    This book the study on isotopic hydrology in El Berrocal, Toledo (Spain). The special topic was the study about the tritium of springs with thermonuclear source. The study are articulated in 3 chapter: 1.- Chemical analysis of wastes 2.- Tritium with thermonuclear source 3.- Human resources

  15. Direct conversion of nuclear energy into radiation: New direction in thermonuclear laser fusion

    International Nuclear Information System (INIS)

    Babaev, Yu.N.; Vedenov, A.A.; Filyukov, A.A.

    1995-01-01

    In investigations dealing with thermonuclear fusion, a radical new direction appeared some time ago, namely the direct conversion of nuclear and thermonuclear energy into radiation energy. This paper reviews early work on this topic in Russia and the United States and discusses some recent new directions

  16. Interleukin-6-receptor polymorphisms rs12083537, rs2228145, and rs4329505 as predictors of response to tocilizumab in rheumatoid arthritis

    DEFF Research Database (Denmark)

    Enevold, Christian; Baslund, Bo; Linde, Louise

    2014-01-01

    Tocilizumab (TCZ), a monoclonal antibody targeting the human interleukin-6-receptor (IL-6R), is indicated for the treatment of rheumatoid arthritis (RA). We examined whether three IL6R single-nucleotide polymorphisms rs12083537, rs2228145 (formerly rs8192284), and rs4329505 with previously report...

  17. Transport simulation of ITER [International Thermonuclear Engineering Reactor] startup

    International Nuclear Information System (INIS)

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

    1989-01-01

    The present International Thermonuclear Engineering Reactor (ITER) reference configurations are the ''Technology Phase,'' in which the plasma current is maintained noninductively at a subignition density, and the ''Physics Phase,'' which is ignited but requires inductive maintenance of the current. The WHIST 1.5-D transport code is used to evaluate the volt-second requirements of both configurations. A slow current ramp (60-80's) is required for fixed-radius startup in ITER to avoid hollow current density profiles. To reach the operating point requires about 203 V·s for the Technology Phase (18 MA) and about 270 V·s for the Physics Phase (22 MA). The resistive losses can be reduced with expanding-radius startup. 5 refs., 4 figs

  18. First fusion neutrons from a thermonuclear weapon device

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    An account of the first observation of thermonuclear neutrons from a hydrogen weapon, the George shot, is presented. A personal narrative by the researchers J. Allred and L. Rosen includes such topics as the formation of the experimental team, description of the experimental technique, testing the experimental apparatus, testing the effects of a blast, a description of the test area, and the observation of neutrons from fusion. Excerpts are presented from several chapters of the Scientific Director's report on the atomic weapons tests of 1951. Also included is a brief description of the basic design of the hydrogen bomb, a recounting of subsequent developments, and short scientific biographies of the researchers. 21 figures, 2 tables

  19. Blue energy - The story of thermonuclear fusion energy

    International Nuclear Information System (INIS)

    Laval, G.

    2007-01-01

    The author has written a story of thermonuclear fusion as a future source of energy. This story began about 50 years ago and its last milestone has been the decision of building the ITER machine. This decision has been taken by an international collaboration including a large part of the humanity which shows how great are the expectations put on fusion and that fusion deserves confidence now. For long years fusion energy has been the subject of large controversy due to the questioning about the overcoming of huge theoretical and technological difficulties. Different machines have been built to assess new theoretical developments and to prepare the next step. The physics of hot plasmas has been understood little by little at the pace of the discovery of new instabilities taking place in fusion plasmas. The 2 unique today options: the tokamak-type machine and the laser-driven inertial confinement machine took the lead relatively quickly. (A.C.)

  20. Magnet systems for the International Thermonuclear Experimental Reactor

    International Nuclear Information System (INIS)

    Henning, C.D.; Miller, J.R.

    1988-01-01

    The definition phase for the International Thermonuclear Experimental Reactor (ITER) has been nearly completed, thus beginning a three-year design effort by teams from the European Community (EC), Japan, US, and USSR. Preliminary parameters for the superconducting magnet system have been established to guide more detailed design work. Radiation tolerance of the superconductors and insulators has been important because it sets requirements for the neutron-shield dimension and sensitively influences reactor size. Major levels of mechanical stress appear in the structural cases of the inboard legs of the toroidal-field (TF) coils. The winding packs of the TF coils include significant fractions of steel that provide support against in-plane separating loads, but they offer little support against out-of-plane loads unless shear-bonding of the conductors can be maintained. Heat removal from nuclear and ac loads has not limited the fundamental design, but it has nonnegligible economic consequences. 3 refs., 3 figs., 5 tabs

  1. Local wall power loading variations in thermonuclear fusion devices

    International Nuclear Information System (INIS)

    Carroll, M.C.; Miley, G.H.

    1989-01-01

    A 2 1/2-dimensional geometric model is presented that allows calculation of power loadings at various points on the first wall of a thermonuclear fusion device. Given average wall power loadings for brems-strahlung, cyclotron radiation charged particles, and neutrons, which are determined from various plasma-physics computation models, local wall heat loads are calculated by partitioning the plasma volume and surface into cells and superimposing the heating effects of the individual cells on selected first-wall differential areas. Heat loads from the entire plasma are thus determined as a function of position on the first-wall surface. Significant differences in local power loadings were found for most fusion designs, and it was therefore concluded that the effect of local power loading variations must be taken into account when calculating temperatures and heat transfer rates in fusion device first walls

  2. Structure of pipeline or duct for thermonuclear reactor

    International Nuclear Information System (INIS)

    Yamazaki, Seiichiro; Kobayashi, Takeshi; Fujioka, Junzo; Nishio, Satoshi; Okawa, Yoshinao; Sato, Keisuke.

    1992-01-01

    An electrically insulating material comprising a gradient function material is bonded metallurgically to a pipeline or a duct to be disposed to a magnetic field-confining type thermonuclear reactor. The gradient material has an ingredient approximate to ceramics on the side of an electrically insulative ceramic portion and an ingredient approximate to a metal on the other side. The intermediate portion between them, has a continuous gradient ingredient. Further, in the gradient portion of the electrically insulative portion, a heat expansion coefficient is also varied continuously or stepwise in addition to the electrical insulative property. Accordingly, even when a temperature distribution is caused during operation and welding upon production, thermal stresses applied to the pipelines is moderated. Further, since the electrically insulative ceramics are interposed with no support by an electric conductor, sufficient electrical insulation can be ensured. (T.M.)

  3. Laser induced sonofusion: A new road toward thermonuclear reactions

    Energy Technology Data Exchange (ETDEWEB)

    Sadighi-Bonabi, Rasoul, E-mail: Sadighi@sharif.ir [Sharif University of Technology, P.O. Box 11365-91, Tehran (Iran, Islamic Republic of); Gheshlaghi, Maryam [Payame noor University, P.O. Box 19395-3697, Tehran (Iran, Islamic Republic of); Laser and optics research school, Nuclear Science and Technology Research Institute (NSTRL), P.O. Box 14155-1339, Tehran (Iran, Islamic Republic of)

    2016-03-15

    The Possibility of the laser assisted sonofusion is studied via single bubble sonoluminescence (SBSL) in Deuterated acetone (C{sub 3}D{sub 6}O) using quasi-adiabatic and hydro-chemical simulations at the ambient temperatures of 0 and −28.5 °C. The interior temperature of the produced bubbles in Deuterated acetone is 1.6 × 10{sup 6} K in hydro-chemical model and it is reached up to 1.9 × 10{sup 6} K in the laser induced SBSL bubbles. Under these circumstances, temperature up to 10{sup 7} K can be produced in the center of the bubble in which the thermonuclear D-D fusion reactions are promising under the controlled conditions.

  4. Stochastic models of edge turbulent transport in the thermonuclear reactors

    International Nuclear Information System (INIS)

    Volchenkov, Dima

    2005-01-01

    Two-dimensional stochastic model of turbulent transport in the scrape-off layer (SOL) of thermonuclear reactors is considered. Convective instability arisen in the system with respect to perturbations reveals itself in the strong outward bursts of particle density propagating ballistically across the SOL. The criterion of stability for the fluctuations of particle density is formulated. A possibility to stabilize the system depends upon the certain type of plasma waves interactions and the certain scenario of turbulence. A bias of limiter surface would provide a fairly good insulation of chamber walls excepting for the resonant cases. Pdf of the particle flux for the large magnitudes of flux events is modeled with a simple discrete time toy model of I-dimensional random walks concluding at the boundary. The spectra of wandering times feature the pdf of particle flux in the model and qualitatively reproduce the experimental statistics of transport events

  5. ITER [International Thermonuclear Experimental Reactor] reactor building design study

    International Nuclear Information System (INIS)

    Thomson, S.L.; Blevins, J.D.; Delisle, M.W.

    1989-01-01

    The International Thermonuclear Experimental Reactor (ITER) is at the midpoint of a two-year conceptual design. The ITER reactor building is a reinforced concrete structure that houses the tokamak and associated equipment and systems and forms a barrier between the tokamak and the external environment. It provides radiation shielding and controls the release of radioactive materials to the environment during both routine operations and accidents. The building protects the tokamak from external events, such as earthquakes or aircraft strikes. The reactor building requirements have been developed from the component designs and the preliminary safety analysis. The equipment requirements, tritium confinement, and biological shielding have been studied. The building design in progress requires continuous iteraction with the component and system designs and with the safety analysis. 8 figs

  6. Synthetic report 2012. Research programme on controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    Vaucher, C.; Tran, M. Q.; Villard, L.; Marot, L.

    2013-01-01

    Since 1961, Switzerland participates in the research on thermonuclear fusion thanks to the creation of the Research Centre in Plasma Physics. In 1979 it entered into partnership with the European programme on fusion through its adhesion to EURATOM. The thermonuclear fusion is an interesting energy source because the basic fuel is practically inexhaustible and its use does not release any significant CO 2 quantity and very little radioactive residues. But its working up faces enormous physical and technological difficulties. The International Thermonuclear Reactor (ITER), presently in construction, has to demonstrate the technological feasibility of the controlled fusion. Il will be followed by DEMO, foreseen for 2040-2050, which must guarantee the economical rentability. At CRPP the research projects are partitioned onto several sites: at the Swiss Federal Institute of Technology (EPFL) in Lausanne, they concern the physics of the magnetic confinement with the Variable Geometry Tokamak (TCV), the development of theoretical models and the numerical simulation, the plasma heating and the generation of hyper frequency waves; the Paul Scherrer Institute (PSI) studies the superconductivity and the materials; the interactions between the plasma and the Tokamak walls are studied at the Basel University for the structures of ITER. Thanks to its large flexibility, TCV allows the creation and the control of plasmas of very different forms. The injection system of millimetric waves allows orienting the injected power according to specific profiles. By using the asymmetry of the flow in the toroidal sense, the plasma rotation could be measured with a much better accuracy than before. In TCV, by playing on the form of the plasma, it was possible to strongly reduce the energy quantity which is expelled by the Edge Localized Modes (ELM) onto the wall of the vacuum chamber. The ‘snowflake’ configuration created in TCV allows distributing the ELM energy onto several impact

  7. Coupling and absorption of lower-hybrid waves in a thermonuclear plasma

    International Nuclear Information System (INIS)

    Puri, S.; Tutter, M.

    1975-01-01

    The three important aspects, namely 1) accessibility, 2) matching and 3) absorption of the lower-hybrid waves in a thermonuclear plasma are studied under idealized but physically pertinent conditions within the framework of linearized theory. (orig.) [de

  8. Compilation and evaluation of atomic and molecular data relevant to controlled thermonuclear research needs: USA programs

    International Nuclear Information System (INIS)

    Barnett, C.F.

    1976-01-01

    The U.S. role in the compilation and evaluation of atomic data for controlled thermonuclear research is discussed in the following three areas: (1) atomic structure data, (2) atomic collision data, and (3) surface data

  9. Demonstration of thermonuclear conditions in magnetized liner inertial fusion experiments

    International Nuclear Information System (INIS)

    Gomez, M. R.; Slutz, S. A.; Sefkow, A. B.; Hahn, K. D.; Hansen, S. B.; Knapp, P. F.; Schmit, P. F.; Ruiz, C. L.; Sinars, D. B.; Harding, E. C.; Jennings, C. A.; Awe, T. J.; Geissel, M.; Rovang, D. C.; Smith, I. C.; Chandler, G. A.; Cooper, G. W.; Cuneo, M. E.; Harvey-Thompson, A. J.; Hess, M. H.

    2015-01-01

    The magnetized liner inertial fusion concept [S. A. Slutz et al., Phys. Plasmas 17, 056303 (2010)] utilizes a magnetic field and laser heating to relax the pressure requirements of inertial confinement fusion. The first experiments to test the concept [M. R. Gomez et al., Phys. Rev. Lett. 113, 155003 (2014)] were conducted utilizing the 19 MA, 100 ns Z machine, the 2.5 kJ, 1 TW Z Beamlet laser, and the 10 T Applied B-field on Z system. Despite an estimated implosion velocity of only 70 km/s in these experiments, electron and ion temperatures at stagnation were as high as 3 keV, and thermonuclear deuterium-deuterium neutron yields up to 2 × 10 12 have been produced. X-ray emission from the fuel at stagnation had widths ranging from 50 to 110 μm over a roughly 80% of the axial extent of the target (6–8 mm) and lasted approximately 2 ns. X-ray yields from these experiments are consistent with a stagnation density of the hot fuel equal to 0.2–0.4 g/cm 3 . In these experiments, up to 5 × 10 10 secondary deuterium-tritium neutrons were produced. Given that the areal density of the plasma was approximately 1–2 mg/cm 2 , this indicates the stagnation plasma was significantly magnetized, which is consistent with the anisotropy observed in the deuterium-tritium neutron spectra. Control experiments where the laser and/or magnetic field were not utilized failed to produce stagnation temperatures greater than 1 keV and primary deuterium-deuterium yields greater than 10 10 . An additional control experiment where the fuel contained a sufficient dopant fraction to substantially increase radiative losses also failed to produce a relevant stagnation temperature. The results of these experiments are consistent with a thermonuclear neutron source

  10. Pulsating Instability of Turbulent Thermonuclear Flames in Type Ia Supernovae

    Science.gov (United States)

    Poludnenko, Alexei Y.

    2014-01-01

    Presently, one of the main explosion scenarios of type Ia supernovae (SNIa), aimed at explaining both "normal" and subluminous events, is the thermonuclear incineration of a white-dwarf in a single-degenerate system. The underlying engine of such explosions is the turbulent thermonuclear flame. Modern, large-scale, multidimensional simulations of SNIa cannot resolve the internal flame structure, and instead must include a subgrid-scale prescription for the turbulent-flame properties. As a result, development of robust, parameter-free, large-scale models of SNIa crucially relies on the detailed understanding of the turbulent flame properties during each stage of the flame evolution. Due to the complexity of the flame dynamics, such understanding must be validated by the first-principles direct numerical simulations (DNS). In our previous work, we showed that sufficiently fast turbulent flames are inherently susceptible to the development of detonations, which may provide the mechanism for the deflagration-to-detonation transition (DDT) in the delayed-detonation model of SNIa. Here we extend this study by performing detailed analysis of the turbulent flame properties at turbulent intensities below the critical threshold for DDT. We carried out a suite of 3D DNS of turbulent flames for a broad range of turbulent intensities and system sizes using a simplified, single-step, Arrhenius-type reaction kinetics. Our results show that at the later stages of the explosion, as the turbulence intensity increases prior to the possible onset of DDT, the flame front will become violently unstable. We find that the burning rate exhibits periodic pulsations with the energy release rate varying by almost an order of magnitude. Furthermore, such flame pulsations can produce pressure waves and shocks as the flame speed approaches the critical Chapman-Jouguet deflagration speed. Finally, in contrast with the current theoretical understanding, such fast turbulent flames can propagate at

  11. Thermal insulation layer for the vacuum containers of a thermonuclear device

    International Nuclear Information System (INIS)

    Nishikawa, Masana; Yamada, Masao; Kameari, Akihisa; Niikura, Setsuo.

    1980-01-01

    Purpose: To prevent temperature rise of a thermal insulation layer for a vacuum container of a thermonuclear device higher than allowable value when irradiated by neutron by constructing the layer of a cooling unit in thermal insulation material. Constitution: A metal plate attached with cooling pipes is buried in a thermal insulation material forming a thermal insulation layer to form the layer provided between a vacuum container of a thermonuclear device and a shield. (Yoshihara, H.)

  12. XXXII Zvenigorod conference on the plasma physics and controlled thermonuclear synthesis. Theses of reports

    International Nuclear Information System (INIS)

    2005-01-01

    Theses of the reports, presented at the XXXII International conference on the plasma physics and controlled thermonuclear synthesis (Zvenigorod, 14-18 February 2005) are published. The total number of reports is 322, including 16 summarizing ones. The other reports are distributed by the following sections: magnetic confinement of high-temperature plasma (88 reports), inertial thermonuclear fusion (65), physical processes in low-temperature plasma (99) and physical bases of the plasma and beam technologies (54) [ru

  13. Joint development effort Thermonuclear Fusion. Programme budgeting 1984

    International Nuclear Information System (INIS)

    1985-01-01

    The joint KfK and IPP project for the development of thermonuclear fusion device is established as the centerpiece of Federal German efforts in this field. It is meant to enhance the German contribution to the European programme and thus foster the chances of a joint European large-scale experiment to be started in the Federal Republic of Germany. IPP's tasks in the project are to study the physical principles and aspects, whereas KfK is responsible for the technological aspects. Work at IPP is focused on divertor experiments with the ASDEX series in order to go deeper into the problems that could not be solved by the JET experiments, namely those of the plasma boundary and control of impurities. Stellarator experiments are made in order to study the potentials of this toroidal confinement concept for steady-state operation. The IPP which always has been working in the plasma physics field devotes all activities to the joint effort. KfK has established a special project group for this purpose, PKF. The budgeting programme presented therefore covers the IPP entire working schedule, and that of PKF of the KfK. (orig./GG) [de

  14. Thermonuclear dynamo inside ultracentrifuge with supersonic plasma flow stabilization

    Energy Technology Data Exchange (ETDEWEB)

    Winterberg, F. [University of Nevada, Reno, Reno, Nevada (United States)

    2016-01-15

    Einstein's general theory of relativity implies the existence of virtual negative masses in the rotational reference frame of an ultracentrifuge with the negative mass density of the same order of magnitude as the positive mass density of a neutron star. In an ultracentrifuge, the repulsive gravitational field of this negative mass can simulate the attractive positive mass of a mini-neutron star, and for this reason can radially confine a dense thermonuclear plasma placed inside the centrifuge, very much as the positive mass of a star confines its plasma by its own attractive gravitational field. If the centrifuge is placed in an externally magnetic field to act as the seed field of a magnetohydrodynamic generator, the configuration resembles a magnetar driven by the release of energy through nuclear fusion, accelerating the plasma to supersonic velocities, with the magnetic field produced by the thermomagnetic Nernst effect insulating the hot plasma from the cold wall of the centrifuge. Because of the supersonic flow and the high plasma density the configuration is stable.

  15. Thermonuclear burst oscillations: where firestorms meet fundamental physics.

    CERN Multimedia

    CERN. Geneva

    2017-01-01

    Neutron stars offer a unique environment in which to develop and test theories of the strong force. Densities in neutron star cores can reach up to ten times the density of a normal atomic nucleus, and the stabilising effect of gravitational confinement permits long-timescale weak interactions. This generates matter that is neutron-rich, and opens up the possibility of stable states of strange matter, something that can only exist in neutron stars. Strong force physics is encoded in the Equation of State (EOS), the pressure-density relation, which links to macroscopic observables such as mass M and radius R via the stellar structure equations. By measuring and inverting the M-R relation we can recover the EOS and diagnose the underlying dense matter physics. One very promising technique for simultaneous measurement of M and R exploits hotspots (burst oscillations) that form on the neutron star surface when material accreted from a companion star undergoes a thermonuclear explosion (a Type I X-ray burst). As ...

  16. Thermonuclear dynamo inside ultracentrifuge with supersonic plasma flow stabilization

    Science.gov (United States)

    Winterberg, F.

    2016-01-01

    Einstein's general theory of relativity implies the existence of virtual negative masses in the rotational reference frame of an ultracentrifuge with the negative mass density of the same order of magnitude as the positive mass density of a neutron star. In an ultracentrifuge, the repulsive gravitational field of this negative mass can simulate the attractive positive mass of a mini-neutron star, and for this reason can radially confine a dense thermonuclear plasma placed inside the centrifuge, very much as the positive mass of a star confines its plasma by its own attractive gravitational field. If the centrifuge is placed in an externally magnetic field to act as the seed field of a magnetohydrodynamic generator, the configuration resembles a magnetar driven by the release of energy through nuclear fusion, accelerating the plasma to supersonic velocities, with the magnetic field produced by the thermomagnetic Nernst effect insulating the hot plasma from the cold wall of the centrifuge. Because of the supersonic flow and the high plasma density the configuration is stable.

  17. Thermonuclear dynamo inside ultracentrifuge with supersonic plasma flow stabilization

    International Nuclear Information System (INIS)

    Winterberg, F.

    2016-01-01

    Einstein's general theory of relativity implies the existence of virtual negative masses in the rotational reference frame of an ultracentrifuge with the negative mass density of the same order of magnitude as the positive mass density of a neutron star. In an ultracentrifuge, the repulsive gravitational field of this negative mass can simulate the attractive positive mass of a mini-neutron star, and for this reason can radially confine a dense thermonuclear plasma placed inside the centrifuge, very much as the positive mass of a star confines its plasma by its own attractive gravitational field. If the centrifuge is placed in an externally magnetic field to act as the seed field of a magnetohydrodynamic generator, the configuration resembles a magnetar driven by the release of energy through nuclear fusion, accelerating the plasma to supersonic velocities, with the magnetic field produced by the thermomagnetic Nernst effect insulating the hot plasma from the cold wall of the centrifuge. Because of the supersonic flow and the high plasma density the configuration is stable

  18. Cryogenic instrumentation needs in the controlled thermonuclear research program

    International Nuclear Information System (INIS)

    Walstrom, P.L.

    1976-01-01

    The magnet development effort for the controlled thermonuclear research program will require extensive testing of superconducting coils at various sizes from small-scale models to full-size prototypes. Extensive use of diagnostic instrumentation will be required and to make detailed comparisons of predicted and actual performance in magnet tests and to monitor the test facility for incipient failure modes. At later stages of the program, cryogenic instrumentation will be required to monitor magnet system performance in fusion power reactors. Measured quantities may include temperature, strain, deflection, coil resistance, helium coolant pressure and flow, current, voltages, etc. The test environment, which includes high magnetic fields (up to 8-10 T) and low temperature, makes many commercial measuring devices inoperative or at least inaccurate. In order to ensure reliable measurements, careful screening of commercial devices for performance in the test environment will be required. A survey of potentially applicable instrumentation is presented along with available information on operation in the test environment based on experimental data or on analysis of the physical characteristics of the device. Areas where further development work is needed are delineated

  19. Method for baking a liner in thermonuclear device

    International Nuclear Information System (INIS)

    Yamamoto, Keiichi.

    1978-01-01

    Purpose: To attain effective baking for liners in a tokamak device by connecting the narrow portions and the wide portions of the liners with dielectric materials and supplying a constant current to these portions. Method: Split type liners disposed in the vacuum vessel of a thermonuclear device are connected with dielectric materials at their wide portions and narrow portions and they are baked by supplying a constant current at a same density to the wide and narrow portions to rise their temperature uniformly. The wide portions are formed in such a way that the sum of their cross sectional areas is equal to the sum of the cross sectional areas of the narrow portions, and they form a parallel circuit. The parallel circuit consisting of the wide portions and the parallel circuit consisting of the narrow portions are connected in series to each other and connected to the constant current supply circuit, by which a constant current is supplied to the wide and the narrow portions. (Moriyama, K.)

  20. Thermonuclear Tokamak plasmas in the presence of fusion alpha particles

    International Nuclear Information System (INIS)

    Anderson, D.; Hamnen, H.; Lisak, M.

    1988-01-01

    In this overview, we have focused on several results of the thermonuclear plasma research pertaining to the alpha particle physics and diagnostics in a fusion tokamak plasma. As regards the discussion of alpha particle effects, two distinct classes of phenomena have been distinguished: the simpler class containing phenomena exhibited by individual alpha particles under the influence of bulk plasma properties and, the more complex class including collective effects which become important for increasing alpha particle density. We have also discussed several possibilities to investigate alpha particle effects by simulation experiments using an equivalent population of highly energetic ions in the plasma. Generally, we find that the present theoretical knowledge on the role of fusion alpha particles in a fusion tokamak plasma is incomplete. There are still uncertainties and partial lack of quantitative results in this area. Consequently, further theoretical work and, as far a possible, simulation experiments are needed to improve the situation. Concerning the alpha particle diagnostics, the various diagnostic techniques and the status of their development have been discussed in two different contexts: the escaping alpha particles and the confined alpha particles in the fusion plasma. A general conclusion is that many of the different diagnostic methods for alpha particle measurements require further major development. (authors)

  1. Divertor impurity monitor for the International Thermonuclear Experimental Reactor

    Science.gov (United States)

    Sugie, T.; Ogawa, H.; Nishitani, T.; Kasai, S.; Katsunuma, J.; Maruo, M.; Ebisawa, K.; Ando, T.; Kita, Y.

    1999-01-01

    The divertor impurity monitoring system of the International Thermonuclear Experimental Reactor has been designed. The main functions of this system are to identify impurity species and to measure the two-dimensional distributions of the particle influxes in the divertor plasmas. The wavelength range is 200-1000 nm. The viewing fans are realized by molybdenum mirrors located in the divertor cassette. With additional viewing fans seeing through the gap between the divertor cassettes, the region approximately from the divertor leg to the x point will be observed. The light from the divertor region passes through the quartz windows on the divertor port plug and the cryostat, and goes through the dog-leg optics in the biological shield. Three different type of spectrometers: (i) survey spectrometers for impurity species monitoring, (ii) filter spectrometers for the particle influx measurement with the spatial resolution of 10 mm and the time resolution of 1 ms, and (iii) high dispersion spectrometers for high resolution wavelength measurements are designed. These spectrometers are installed just behind the biological shield (for λthe transmission loss in fiber and in the diagnostic room (for λ⩾450 nm) from the point of view of accessibility and flexibility. The optics have been optimized by a ray trace analysis. As a result, 10-15 mm spatial resolution will be achieved in all regions of the divertor.

  2. Vacuum vessel of thermonuclear device and manufacturing method thereof

    International Nuclear Information System (INIS)

    Kurita, Genichi; Nagashima, Keisuke; Uchida, Takaho; Shibui, Masanao; Ebisawa, Katsuyuki; Nakagawa, Satoshi.

    1997-01-01

    The present invention provides a vacuum vessel of a thermonuclear device using, as a material of a plasma vacuum vessel, a material to be less activated and having excellent strength as well as a manufacturing method thereof. Namely, the vacuum vessel is made of titanium or a titanium alloy. In addition, a liner layer comprising a manganese alloy, nickel alloy, nickel-chromium alloy or aluminum or aluminum alloy is formed. With such a constitution, the wall substrate made of titanium or a titanium alloy can be isolated by the liner from hydrogen or plasmas. As a result, occlusion of hydrogen to titanium or the titanium alloy can be prevented thereby enabling to prevent degradation of the material of the wall substrate of the vacuum vessel. In addition, since the liner layer has relatively high electric resistance, a torus circumferential resistance value required for plasma ignition can be ensured by using it together with the vessel wall made of titanium alloy. (I.S.)

  3. Focused Study of Thermonuclear Bursts on Neutron Stars

    Science.gov (United States)

    Chenevez, Jérôme

    2009-05-01

    X-ray bursters form a class of Low Mass X-Ray Binaries where accreted material from a donor star undergoes rapid thermonuclear burning in the surface layers of a neutron star. The flux released can temporarily exceed the Eddington limit and drive the photosphere to large radii. Such photospheric radius expansion bursts likely eject nuclear burning ashes into the interstellar medium, and may make possible the detection of photoionization edges. Indeed, theoretical models predict that absorption edges from 58Fe at 9.2 keV, 60Zn and 62Zn at 12.2 keV should be detectable by the future missions Simbol-X and NuSTAR. A positive detection would thus probe the nuclear burning as well as the gravitational redshift from the neutron star. Moreover, likely observations of atomic X-ray spectral components reflected from the inner accretion disk have been reported. The high spectral resolution capabilities of the focusing X-ray telescopes may therefore make possible to differentiate between the potential interpretations of the X-ray bursts spectral features.

  4. Industrial opportunities on the International Thermonuclear Experimental Reactor (ITER) project

    International Nuclear Information System (INIS)

    Ellis, W.R.

    1996-01-01

    Industry has been a long-term contributor to the magnetic fusion program, playing a variety of important roles over the years. Manufacturing firms, engineering-construction companies, and the electric utility industry should all be regarded as legitimate stakeholders in the fusion energy program. In a program focused primarily on energy production, industry's future roles should follow in a natural way, leading to the commercialization of the technology. In a program focused primarily on science and technology, industry's roles, in the near term, should be, in addition to operating existing research facilities, largely devoted to providing industrial support to the International Thermonuclear Experimental Reactor (ITER) Project. Industrial opportunities on the ITER Project will be guided by the amount of funding available to magnetic fusion generally, since ITER is funded as a component of that program. The ITER Project can conveniently be discussed in terms of its phases, namely, the present Engineering Design Activities (EDA) phase, and the future (as yet not approved) construction phase. 2 refs., 3 tabs

  5. Ignition and burn control characteristics of thermonuclear plasmas

    International Nuclear Information System (INIS)

    Chaniotakis, E.A.

    1990-01-01

    Achieving the long sought goal of fusion energy requires the attainment of an ignited and controlled thermonuclear plasma. Obtaining an ignited plasma in a tokamak device requires consideration of both the physics of the plasma and the engineering of the machine. With the aide of completely analytical procedure optimized and ignited tokamaks are obtained under various physics assumptions. These designs show the possible advantage of tokamaks characterized by high (∼4.5) aspect ratio, and high (∼15 T) toroidal magnetic field. The control of an ignited plasma is investigated by using auxiliary power modulation. With auxiliary power stable operating points can be created with Q ∼50. Recognizing the need for a fast 1 1/2-D transport model for studying profile effects the plasma transport equations are solved using variational methods. A computer model based on the variational method has been developed. This model solves the 1 1/2-D transport equation very fast with little loss of accuracy. 74 refs., 70 figs., 8 tabs

  6. X-ray sources in stars formation areas: T Tauri stars and proto-stars in the rho Ophiuchi dark cloud

    International Nuclear Information System (INIS)

    Grosso, Nicolas

    1999-01-01

    This thesis studies from large to small scales, X-ray sources in the rho Ophiuchi dark cloud. After some background on the formation of the low-mass young stars (Chapter 1), Chapter 2 takes an interest in the T Tauri star population. Chapter 3 tackles the search of the magnetic activity at the younger stage of protostar, presenting a powerful X-ray emission from an IR protostar, called YLW15, during a flare, and a quasi-periodic flare of the same source; as well as a new detection of another IR protostar in the ROSAT archives. It ends with a review of protostar detections. Some IR protostar flares show a very long increasing phase. Chapter 4 links this behaviour with a modulation by the central star rotation. The standard model of jet emission assumes that the central star rotates at the same speed that the inner edge of its accretion disk. This chapter shows that the observation of the YLW15 quasi-periodic flare suggests rather that the forming star rotates faster than its accretion disk, at the break up limit. The synchronism with the accretion disk, observed on T Tauri stars, must be reach progressively by magnetic breaking during the IR protostar stage, and more or less rapidly depending on the forming star mass. Recent studies have shown that T Tauri star X-ray emission could ionize the circumstellar disk, and play a role in the instability development, as well as stimulate the accretion. The protostar X-ray emission might be higher than the T Tauri star one, Chapter 5 presents a millimetric interferometric observation dedicated to measure this effect on YLW15. Finally, Chapter 6 reassembles conclusions and perspectives of this work. (author) [fr

  7. Research programme on controlled thermonuclear fusion - Synthesis report 2010

    International Nuclear Information System (INIS)

    Vaucher, C.; Tran, M. Q.; Villard, L.; Marot, L.

    2011-01-01

    Since 1978, research on thermonuclear fusion in Switzerland is closely related to the research programme of the European Atomic Energy Community (EURATOM). The Swiss projects tackle aspects of plasma physics and fusion technology. Switzerland participates to the construction and operation of the Joint European Torus (JET). The International Thermonuclear Experimental Reactor (ITER) is being built; the first plasma is expected in 2019. The 'Centre de Recherches en Physique des Plasmas' (CRPP) of the EPFL participates to EURATOM scientific and technological projects in magnetic confinement physics, through an experimental contribution (the Variable Configuration Tokamak, TCV) and theoretical studies. Thanks to the large flexibility of the TCV design and operation modus, plasmas of different shapes can be created and controlled, what is a very useful option to verify numerical simulation results. Besides, the injection of millimetre waves allows directing the injected power according to specific profiles. A configuration of type 'snowflakes' could be created, reducing the power deposition at the edge of the plasma. Theoretical studies on turbulence have improved the plasma stability in the TCV. For the first time in the world, TCV could reach a stable plasma, the plasma current being generated using the so-called 'bootstrap' phenomenon. Besides turbulence, studies were focused on heat and particle transport in tokamaks, on an analysis of the equilibrium and magneto-hydrodynamic stability of tokamaks and stellarators, on the application of radiofrequency waves and on the optimization of new confinement configurations. Experiments in the JET facility confirmed the numerical results of theoretical simulations. The TORPEX facility, which is simpler than TCV, allows high space-temporal resolution measurements for the study of turbulences and plasma threads ('blobs'). At the Paul Scherrer Institute (PSI), research topics include superconductivity and materials. The Fusion

  8. Research programme on controlled thermonuclear fusion. Synthesis report 2011

    International Nuclear Information System (INIS)

    Vaucher, C.; Tran, M. Q.; Villard, L.; Marot, L.

    2012-01-01

    Since 1978, research on thermonuclear fusion in Switzerland is closely related to the research programme of the European Atomic Energy Community (EURATOM). The Swiss projects tackle aspects of plasma physics and fusion technology. Switzerland participates to the construction and operation of the Joint European Torus (JET), which started operation again in 2011. The International Thermonuclear Experimental Reactor (ITER) is the last step before DEMO, a prototype fusion reactor able to deliver electricity and demonstrate the economic viability of fusion energy. The 'Centre de Recherches en Physique des Plasmas' (CRPP) of the EPFL went on with its participation to the scientific and technological programme of EURATOM. Researches are carried out essentially on 2 sites: (i) at EPFL, where topics dealt with include the physics of magnetic confinement studied using the Variable Configuration Tokamak (TCV), the basic experiment TORPEX, theory and numerical modelling, and the technology of plasma heating and current generation by hyper-frequency waves; (ii) at the Paul Scherrer Institute (PSI), where activities are devoted to superconductivity and structure materials. Thanks to the large flexibility of the TCV design and operation modus, plasmas of different shapes can be created and controlled, what is a very useful option to verify numerical simulation results. Besides, the injection of millimetre waves allows directing the injected power according to specific profiles. In the TCV it could be demonstrated for the first time that the injection of Electronic Cyclotronic Heating (ECH) waves is able to double the frequency of so-called 'Edge Localized Modes' (ELM), reducing by a factor of 2 the energy expelled by each ELM. In particular, it was possible to considerably reduce the statistical dispersion of the repetition frequency of ELM, and to avoid the appearance of gigantic ELM that are particularly harmful for reactor operation. The effect of plasma internal relaxation

  9. Effects of ion and electron screening on thermonuclear reaction rates

    International Nuclear Information System (INIS)

    Brady, L.R. Jr.

    1977-01-01

    The effects of screening by ions and electrons on thermonuclear reaction rates in stellar plasmas are considered. The enhancement of the reaction rate ranges from negligible to extremely large (on the order of 10 26 or greater). In order to calculate these effects, the potential about a given reacting nucleus is determined. First, Boltzmann-Vlasov and Poisson-Boltzmann equations are solved to yield a Yukawa potential. A suitable approximation to this potential is integrated in the action integral to give the barrier penetration. The screened reaction rate is then found by the saddle-point method. In developing a general formalism to calculate the screened reaction rate and the screening factor, effects due to the finite size of the nucleus are considered and found to be negligible. An expression for the screening factor for resonant reaction rates is also derived. A different and relatively simple approach, based on work of Stewart and Pyatt (1966), is used to find the barrier penetration from the action integral in two approximations: a modified Coulomb potential and a constant-shift potential. Screening factors are calculated for carbon burning at T 6 = 100 and T 6 = 400 for a wide range of densities and also for several examples in late stellar evolution. These screening factors are, for the most part, greater than those given by most others by a few percent at low density to 4 or more orders of magnitude at T 6 = 100 and rho = 10 10 g/cm 3 . Near the edge of the crystalline lattice region, however, they are significantly lower than those of some others. The increase in reaction rates for carbon burning indicates that carbon ignition may occur at lower densities than previously thought and may affect the density at which a supernova shock may occur

  10. Design considerations for ITER [International Thermonuclear Experimental Reactor] magnet systems

    International Nuclear Information System (INIS)

    Henning, C.D.; Miller, J.R.

    1988-01-01

    The International Thermonuclear Experimental Reactor (ITER) is now completing a definition phase as a beginning of a three-year design effort. Preliminary parameters for the superconducting magnet system have been established to guide further and more detailed design work. Radiation tolerance of the superconductors and insulators has been of prime importance, since it sets requirements for the neutron-shield dimension and sensitively influences reactor size. The major levels of mechanical stress in the structure appear in the cases of the inboard legs of the toroidal-field (TF) coils. The cases of the poloidal-field (PF) coils must be made thin or segmented to minimize eddy current heating during inductive plasma operation. As a result, the winding packs of both the TF and PF coils includes significant fractions of steel. The TF winding pack provides support against in-plane separating loads but offers little support against out-of-plane loads, unless shear-bonding of the conductors can be maintained. The removal of heat due to nuclear and ac loads has not been a fundamental limit to design, but certainly has non-negligible economic consequences. We present here preliminary ITER magnetic systems design parameters taken from trade studies, designs, and analyses performed by the Home Teams of the four ITER participants, by the ITER Magnet Design Unit in Garching, and by other participants at workshops organized by the Magnet Design Unit. The work presented here reflects the efforts of many, but the responsibility for the opinions expressed is the authors'. 4 refs., 3 figs., 4 tabs

  11. Epidemiology of a thermonuclear bomb-burst over Nashville, Tennessee: a theoretic study

    International Nuclear Information System (INIS)

    Quinn, R.W.

    1983-01-01

    A thermonuclear bomb explosion over any city in the world would have a devastating effect on the population and environment. For those who survive, with or without injuries, life would become primitive with little or no uncontaminated food or water, and with inadequate housing, fuel, and medical care, resulting in a breakdown of family and interpersonal relationships. This theoretic study of the potential outcome of a thermonuclear bomb-burst over Nashville, Tennessee, discusses epidemiologically the wide range of medical and psychologic effects from the direct trauma of blast and fire, widespread epidemics of otherwise controlled disease, long-term chronic illness, genetic damage, and catastrophic environmental havoc

  12. Italy, EURATOM and Early Research on Controlled Thermonuclear Fusion (1957-1962)

    International Nuclear Information System (INIS)

    Curli, Barbara

    2017-01-01

    This chapter traces the early origins of European collaboration in controlled thermonuclear fusion research, within the larger picture of Cold War nuclear policy in the late 1950s-early 1960s, and as a consequence of the signing of the EURATOM treaty in 1957. It then presents some preliminary findings on the Association contract which was signed in 1960 between EURATOM and Italy, in order to carry out research in controlled thermonuclear fusion at the then newly created 'Laboratori nazionali di Frascati', near Rome, within the framework of the Comitato Nazionale Energia Nucleare (CNEN), the Italian civilian nuclear energy agency.

  13. Investigation of the stationary-thermonuclear-reaction realization possibility in a tokamak device

    International Nuclear Information System (INIS)

    Kolesnichenko, Ya.I.; Reznik, S.N.; Fursa, A.D.

    1976-01-01

    The stationary (quasistationary) selfsustaining thermonuclear D-T reaction is shown to be possible in a toroidal device such as 'Tokamak' with large enough plasma radius. The stationary temperature of the plasma can be quite high. Thus when the transport processes are assumed to be neoclassical the temperature of the central part of a plasma colomn of radius approximately 10-200 cm in the stationary state is 70 keV.The stationary temperature distribution is reached spontaneously as a result of the thermal instability development if plasma is preheated to 10 keV. The stationary thermonuclear burning is also possible at lower temperatures if plasma energy balance is controlled

  14. Some safety considerations in laser-controlled thermonuclear reactors. Final report

    International Nuclear Information System (INIS)

    Botts, T.E.; Breton, D.; Chan, C.K.; Levy, S.I.; Sehnert, M.; Ullman, A.Z.

    1978-07-01

    A major objective of this study was to identify potential safety questions for laser controlled thermonuclear reactors. From the safety viewpoint, it does not appear that the actual laser controlled thermonuclear reactor conceptual designs present hazards very different than those of magnetically confined fusion reactors. Some aspects seem beneficial, such as small lithium inventories, and the absence of cryogenic devices, while other aspects are new, for example the explosion of pressure vessels and laser hazards themselves. Major aspects considered in this report include: (a) general safety considerations, (b) tritium inventories, (c) system behavior during loss of flow accidents, and (d) safety considerations of laser related penetrations

  15. A method for carrying out radiolysis and chemical reactions by means of the radiations resulting from a thermonuclear reaction

    International Nuclear Information System (INIS)

    Gomberg, H.J.

    1974-01-01

    The invention relates to the use of the radiations resulting from thermonuclear reactions. It deals with a method comprising a combination of thermo-chemical and radiolytic reactions for treating a molecule having a high absorption rate, by the radiations of a thermonuclear reaction. This is applicable to the dissociation of water into oxygen and hydrogen [fr

  16. Theses of the reports of the XXXI Zvenigorod conference on the plasma physics and controlled thermonuclear synthesis

    International Nuclear Information System (INIS)

    Kovrizhnykh, L.M.; Ivanov, V.A.; Nagaeva, M.L.; Aleksandrov, A.F.; Vorob'ev, V.S.; Ivanenkov, G.V.; Meshcheryakov, A.I.

    2004-01-01

    Theses of the reports of the 31th Zvenigorod Conference on the physics and controlled thermonuclear synthesis, presented by Russian and foreign scientists, are published. The total number of reports is 258, namely, summarizing ones 16, magnetic confinement of high temperature plasma - 98, inertial thermonuclear synthesis - 44, physical processes in low temperature plasma - 58, physical bases of plasma and beam technologies - 42 [ru

  17. Radiation damages of material surfaces by plasma emission in thermonuclear devices. Methods of study of surface phenomena and simulation effect of thermonuclear plasma

    International Nuclear Information System (INIS)

    Rybalko, V.F.

    1978-01-01

    Phenomena that can introduce a controlling contribution into the erosion of the first wall surface in thermonuclear reactor are reviewed. Considered are the main characteristics of the physical disintegration: dependence of the disintegration coefficient upon the energy and the incidence angle of the bombarding particles, upon the atomic number of the material of the target and the type of bombarding particles. Stressed is the lack of reliable data on the disintegration of materials by light ions, which are of a maximum interest in relation to the controlled thermonuclear synthesis. The chemical disintegration and some regularities of it for the carbon-hydrogen and carbon-oxygen systems are discussed briefly. Listed are the main properties of blistering and its contribution to the erosion of crystalline surfaces

  18. (RS-Efonidipine acetone hemisolvate

    Directory of Open Access Journals (Sweden)

    Yu-Heng Liu

    2016-09-01

    Full Text Available The asymmetric unit of the title compound, C34H38N3O7P·0.5C3H6O {systematic name: (RS-2-[phenyl(phenylmethylamino]ethyl 5-(5,5-dimethyl-2-oxo-1,3-dioxa-2λ5-phosphacyclohex-2-yl-2,6-dimethyl-4-(3-nitrophenyl-1,4-dihydropyridine-3-carboxylate acetone hemisolvate}, contains one R-efonidipine molecule, one S-efonidipine molecule and half of a solvate acetone molecule. In both efonidipine molecules, the six-membered rings of the dioxaphosphinanyl moieties display a chair conformation and the dihydropyridine rings display a flattened boat conformation. In the crystal, N—H...O, C—H...O hydrogen bonds and weak C—H...π interactions link the molecules into a three-dimensional supramolecular structure. A solvent-accessible void of 199 Å3 is found in the structure; the contribution of the heavily disordered solvate molecule was suppressed by use of the SQUEEZE routine in PLATON [Spek (2015. Acta Cryst. C71, 9–18].

  19. RS CV sub n binary systems

    International Nuclear Information System (INIS)

    Linsky, J.L.

    1984-01-01

    An attempt is made to place in context the vast amount of data obtained as a result of X-ray, ultraviolet, optical, and microwave observations of RS CVn and similar spectroscopic binary systems. Emphasis is on the RS CVn systems and their long period analogs. The following questions are considered: (1) are the original defining characteristics still valid and still adequate; (2) what is the evidence for discrete active regions; (3) have any meaningful physical properties for the atmospheres of RS CVn systems been derived; (4) what do the flare observations tell about magnetic fields in RS CVn systems; (5) is there evidence for systematic trends in RS CVn systems with spectral type

  20. Research programme on controlled thermonuclear fusion - Synthesis report 2008

    International Nuclear Information System (INIS)

    Werthmueller, A.

    2009-06-01

    Switzerland is associated to the International Thermonuclear Experimental Reactor (ITER) project carried out in the framework of the European Atomic Energy Community (EURATOM). The current stage includes on-site civil engineering works. The Variable Configuration Tokamak (TCV) of the 'Centre de Recherches en Physique des Plasmas' (CRPP) of the EPFL will remain an important recognized research facility until the start of the ITER operation foreseen in 2018. At the European level, the whole fusion research is coordinated and partly financed by the Joint Undertaking Fusion for Energy (JU F4E). The large flexibility of the TCV design and operation modus allow the creation and control of plasmas of various shapes, what is a very useful option to verify the results of numerical simulations. Besides, the hyper-frequency power density injected into the plasma is the highest ever recorded in the world. Research topics studied with the TCV include the stationary regimes in the tokamaks; a plasma current of more than 70 kA could be maintained, what represents an improvement by a factor of 3 to 4 of the confinement quality. For the first time in the world a configuration of the 'snowflake' type could be created and the power density on the wall of the vacuum chamber could be reduced accordingly. Numerical models allowed the analysis of turbulence and heat transport, of the magneto-hydrodynamic stability of the tokamaks and stellarators as well as the optimization of the magnetic confinement. Results concerning the so-called 'saw teeth' instability were experimentally confirmed on the Joint European Torus (JET). Theoretical researches were carried out on the fluctuations, turbulence and transport phenomena in the magnetized toric plasmas. At the Paul Scherrer Institute (PSI) the effect of the fast neutrons emitted by the fusion reactions on the walls of the fusion reactors was investigated. Irradiation simulations were carried out by means of the Swiss Spallation Neutron Source

  1. Association of ITPA polymorphisms rs6051702/rs1127354 instead of rs7270101/rs1127354 as predictor of ribavirin-associated anemia in chronic hepatitis C treated patients.

    Science.gov (United States)

    D'Avolio, Antonio; De Nicolò, Amedeo; Cusato, Jessica; Ciancio, Alessia; Boglione, Lucio; Strona, Silvia; Cariti, Giuseppe; Troshina, Giulia; Caviglia, Gian Paolo; Smedile, Antonina; Rizzetto, Mario; Di Perri, Giovanni

    2013-10-01

    Functional variants rs7270101 and rs1127354 of inosine triphosphatase (ITPA) were recently found to protect against ribavirin (RBV)-induced hemolytic anemia. However, no definitive data are yet available on the role of no functional rs6051702 polymorphism. Since a simultaneous evaluation of the three ITPA SNPs for hemolytic anemia has not yet been investigated, we aimed to understand the contribution of each SNPs and its potential clinical use to predict anemia in HCV treated patients. A retrospective analysis included 379 HCV treated patients. The ITPA variants rs6051702, rs7270101 and rs1127354 were genotyped and tested for association with achieving anemia at week 4. We also investigated, using multivariate logistic regression, the impact of each single and paired associated polymorphism on anemia onset. All SNPs were associated with Hb decrease. The carrier of at least one variant allele in the functional ITPA SNPs was associated with a lower decrement of Hb, as compared to patients without a variant allele. In multivariate logistic regression analyses the carrier of a variant allele in the rs6051702/rs1127354 association (OR=0.11, p=1.75×10(-5)) and Hb at baseline (OR=1.51, p=1.21×10(-4)) were independently associated with protection against clinically significant anemia at week 4. All ITPA polymorphisms considered were shown to be significantly associated with anemia onset. A multivariate regression model based on ITPA genetic polymorphisms was developed for predicting the risk of anemia. Considering the characterization of pre-therapy anemia predictors, rs6051702 SNP in association to rs1127354 is more informative in order to avoid this relevant adverse event. Copyright © 2013 Elsevier B.V. All rights reserved.

  2. Controlled thermonuclear fusion in TOKAMAK type reactors, the European example: Joint European Torus (JET)

    International Nuclear Information System (INIS)

    Paris, P.J.; Yassen, F.; Assis, A.S. de; Raposo, C.

    1988-07-01

    The development of controlled thermonuclear reaction in TOKAMAK type reactors, and the main projects in the world are presented. The main characteristics of the JET (Joint European Torus) program, the perspectives for energy production, and the international cooperation for viable use of the TOKAMAK are analysed. (M.C.K.) [pt

  3. Thermonuclear plasma physic: inertial confinement fusion; Physique des plasmas thermonucleaires: la fusion par confinement inertiel

    Energy Technology Data Exchange (ETDEWEB)

    Bayer, Ch.; Juraszek, D

    2001-07-01

    Inertial Confinement Fusion (ICF) is an approach to thermonuclear fusion in which the fuel contained in a spherical capsule is strongly compressed and heated to achieve ignition and burn. The released thermonuclear energy can be much higher than the driver energy, making energetic applications attractive. Many complex physical phenomena are involved by the compression process, but it is possible to use simple analytical models to analyze the main critical points. We first determine the conditions to obtain fuel ignition. High thermonuclear gains are achieved if only a small fraction of the fuel called hot spot is used to trigger burn in the main fuel compressed on a low isentrope. A simple hot spot model will be described. The high pressure needed to drive the capsule compression are obtained by the ablation process. A simple Rocket model describe the main features of the implosion phase. Several parameters have to be controlled during the compression: irradiation symmetry, hydrodynamical stability and when the driver is a laser, the problems arising from interaction of the EM wave with the plasma. Two different schemes are examined: Indirect Drive which uses X-ray generated in a cavity to drive the implosion and the Fast Ignitor concept using a ultra intense laser beam to create the hot spot. At the end we present the Laser Megajoule (LMJ) project. LMJ is scaled to a thermonuclear gain of the order of ten. (authors)

  4. Complex workplace radiation fields at European high-energy accelerators and thermonuclear fusion facilities

    CERN Document Server

    Bilski, P; D'Errico, F; Esposito, A; Fehrenbacher, G; Fernàndez, F; Fuchs, A; Golnik, N; Lacoste, V; Leuschner, A; Sandri, S; Silari, M; Spurny, F; Wiegel, B; Wright, P

    2006-01-01

    This report outlines the research needs and research activities within Europe to develop new and improved methods and techniques for the characterization of complex radiation fields at workplaces around high-energy accelerators and the next generation of thermonuclear fusion facilities under the auspices of the COordinated Network for RAdiation Dosimetry (CONRAD) project funded by the European Commission.

  5. Transient temperature variations during the self-heating of a plasma by thermonuclear reactions

    Energy Technology Data Exchange (ETDEWEB)

    Greyber, Howard D [University of California Radiation Laboratory, Livermore, CA (United States)

    1958-07-01

    The motivation for this work arose from an observation by Rosenbluth that in a different but related physical situation, the electron temperature) could exceed ion temperature, during transient heating. We have undertaken to trace the transient temperatures to be expected in an idealized physical situation that still bears some resemblance to what one envisions for the Controlled Thermonuclear Reactor.

  6. International Thermonuclear Experimental Reactor (ITER). Engineering Design Activities (EDA). Agreement and protocol 1

    International Nuclear Information System (INIS)

    1992-01-01

    This document contains protocol 1 to the agreement among the European Atomic Energy Community, the government of Japan, the Government of the Russian Federation, and the Government of the United States of America on cooperation in the engineering design activities for the International Thermonuclear Experimental Reactor, which activities shall be conducted under the auspices of the International Atomic Energy Agency

  7. MINBAR: A comprehensive study of 6000+ thermonuclear shell flashes from neutron stars

    DEFF Research Database (Denmark)

    Galloway, Duncan; in't Zand, J.J.M.; Chenevez, Jérôme

    2014-01-01

    Thermonuclear (type-I) X-ray bursts have been observed from accreting neutron stars since the early 1970s. These events serve as a valuable diagnostic tool to constrain the source distance; accretion rate; accreted fuel composition, and hence evolutionary status of the donor; and even the neutron...

  8. Antenna design for fast ion collective Thomson scattering diagnostic for the international thermonuclear experimental reactor

    DEFF Research Database (Denmark)

    Leipold, Frank; Furtula, Vedran; Salewski, Mirko

    2009-01-01

    Fast ion physics will play an important role for the international thermonuclear experimental reactor (ITER), where confined alpha particles will affect and be affected by plasma dynamics and thereby have impacts on the overall confinement. A fast ion collective Thomson scattering (CTS) diagnostic...

  9. Use of code DTF-4 for determining the coefficient of back-reflection of the neutron within the thermonuclear plasma of a thermonuclear reactor controlled by the rate of the fission reactions. Pt. 1

    International Nuclear Information System (INIS)

    Cristea, G.

    1975-01-01

    The neutron problems are discussed of the thermonuclear reactor controlled by the rate of the fission reactions. The results obtained by rolling the DTF-4 program in a spherical geometry in the case of an ''external source'' problem permit to draw conclusions concerning the problems of the neutronics system of this thermonuclear reactor type. A relation is deduced for estimating the coefficient of back-reflection of the neutrons within the thermonuclear plasma and the focussion system is discussed of the neutronics of this reactor type

  10. Role of redoximiRs in fibrogenesis.

    Science.gov (United States)

    Fierro-Fernández, Marta; Miguel, Verónica; Lamas, Santiago

    2016-04-01

    Fibrosis can be defined as an excessive accumulation of extracellular matrix (ECM) components, ultimately leading to stiffness, scarring and devitalized tissue. MicroRNAs (miRNAs) are short, 19-25 nucleotides (nt), non-coding RNAs involved in the post-transcriptional regulation of gene expression. Recently, miRNAs have also emerged as powerful regulators of fibrotic processes and have been termed "fibromiRs". Oxidative stress represents a self-perpetuating mechanism in fibrogenesis. MiRNAs can also influence the expression of genes responsible for the generation of reactive oxygen species (ROS) and antioxidant defence and are termed "redoximiRs". Here, we review the current knowledge of mechanisms by which "redoximiRs" regulate fibrogenesis. This new set of miRNAs may be called "redoxifibromiRs". Copyright © 2015 The Authors. Published by Elsevier B.V. All rights reserved.

  11. Simulation of the dynamics of sausage development in a z pinch with a high rate of thermonuclear heat production

    International Nuclear Information System (INIS)

    Vikhrev, V.V.; Rozanova, G.A.

    1993-01-01

    The development of the sausage instability in a z pinch is accompanied by the formulation of a high-temperature plasma. This high-temperature region initiates a wave of thermonuclear burning propagating along the pinch. A numerical solution of the MHD equations has been carried out, taking into account plasma energy losses through radiation and thermonuclear heating. Results of calculations on the growth of the sausage instability are presented for ρr = 0.23 g/cm 2 . It is accompanied by the development of a stable wave of thermonuclear burning. 12 refs., 4 figs

  12. Cross sections and thermonuclear reaction rates of proton-induced reactions on 37Cl

    International Nuclear Information System (INIS)

    Weber, R.O.; Tingwell, C.I.W.; Mitchell, L.W.; Sevior, M.E.; Sargood, D.G.

    1984-01-01

    The yields of γ-rays from the reactions of 37 Cl(p,γ) 38 Ar and 37 Cl(p,αγ) 34 S have been measured as a of bombarding energy over the ranges 0.65 - 2.15 MeV and 1.25 -2.15 MeV respectively, and the yield of neutrons from 37 Cl(p,n) 37 Ar from threshold to 2.50 MeV. The results are compared with global statistical-model calculations and thermonuclear reaction rates are calculated for the temperature range 5 x 10 8 - 10 10 K. The significance of these thermonuclear reaction rates for stellar nucleosynthesis calculations is discussed

  13. Oscillations During Thermonuclear X-ray Bursts: A New Probe of Neutron Stars

    Science.gov (United States)

    Strohmayer, Tod E.; White, Nicholas E. (Technical Monitor)

    2002-01-01

    Observations of thermonuclear (also called Type 1) X-ray bursts from neutron stars in low mass X-ray binaries (LMXB) with the Rossi X-ray Timing Explorer (RXTE) have revealed large amplitude, high coherence X-ray brightness oscillations with frequencies in the 300 - 600 Hz range. Substantial spectral and timing evidence point to rotational modulation of the X-ray burst flux as the cause of these oscillations, and it is likely that they reveal the spin frequencies of neutron stars in LMXB from which they are detected. Here we review the status of our knowledge of these oscillations and describe how they can be used to constrain the masses and radii of neutron stars as well as the physics of thermonuclear burning on accreting neutron stars.

  14. Controlled thermonuclear fusion and the latest progress on China's HT-7 superconducting tokamak

    International Nuclear Information System (INIS)

    Li Jiangang; Yang Yu

    2003-01-01

    After 50 years of research on controlled thermonuclear fusion, a new stage will be reached in 2003, when a site for the International Thermonuclear Experimental Reactor project will be chosen to start the construction. Scientists hope that this project could herald a new era in which the energy problem will be solved completely. The great progress made on the HT-7 superconducting tokamak in China has provided positive and powerful support for fusion research. The HT-7 is one of the only two superconducting tokamaks in the world that can carry out minute-scale high temperature plasma research, and has achieved a duration of 63.95s for the hot plasma discharge. This is a major step towards real steady-state operation of the tokamak configuration. We present an overview of the latest progress on the tokamak experiments in the Institute of Plasma Physics, Chinese Academy of Sciences

  15. MILLIHERTZ QUASI-PERIODIC OSCILLATIONS AND THERMONUCLEAR BURSTS FROM TERZAN 5: A SHOWCASE OF BURNING REGIMES

    Energy Technology Data Exchange (ETDEWEB)

    Linares, M.; Chakrabarty, D. [Massachusetts Institute of Technology, Kavli Institute for Astrophysics and Space Research, Cambridge, MA 02139 (United States); Altamirano, D. [Astronomical Institute ' Anton Pannekoek' , University of Amsterdam and Center for High-Energy Astrophysics, P.O. BOX 94249, 1090 GE Amsterdam (Netherlands); Cumming, A. [Department of Physics, McGill University, 3600 Rue University, Montreal, QC H3A 2T8 (Canada); Keek, L. [School of Physics and Astronomy, University of Minnesota, 116 Church Street SE, Minneapolis, MN 55455 (United States)

    2012-04-01

    We present a comprehensive study of the thermonuclear bursts and millihertz quasi-periodic oscillations (mHz QPOs) from the neutron star (NS) transient and 11 Hz X-ray pulsar IGR J17480-2446, located in the globular cluster Terzan 5. The increase in burst rate that we found during its 2010 outburst, when persistent luminosity rose from 0.1 to 0.5 times the Eddington limit, is in qualitative agreement with thermonuclear burning theory yet contrary to all previous observations of thermonuclear bursts. Thermonuclear bursts gradually evolved into a mHz QPO when the accretion rate increased, and vice versa. The mHz QPOs from IGR J17480-2446 resemble those previously observed in other accreting NSs, yet they feature lower frequencies (by a factor {approx}3) and occur when the persistent luminosity is higher (by a factor 4-25). We find four distinct bursting regimes and a steep (close to inverse cubic) decrease of the burst recurrence time with increasing persistent luminosity. We compare these findings to nuclear burning models and find evidence for a transition between the pure helium and mixed hydrogen/helium ignition regimes when the persistent luminosity was about 0.3 times the Eddington limit. We also point out important discrepancies between the observed bursts and theory, which predicts brighter and less frequent bursts, and suggest that an additional source of heat in the NS envelope is required to reconcile the observed and expected burst properties. We discuss the impact of NS magnetic field and spin on the expected nuclear burning regimes, in the context of this particular pulsar.

  16. Spiral Disk Instability Can Drive Thermonuclear Explosions in Binary White Dwarf Mergers

    OpenAIRE

    Kashyap, Rahul; Fisher, Robert; García-Berro, Enrique; Aznar-Siguán, Gabriela; Ji, Suoqing; Lorén-Aguilar, Pablo

    2015-01-01

    Thermonuclear, or Type Ia supernovae (SNe Ia), originate from the explosion of carbon-oxygen white dwarfs, and serve as standardizable cosmological candles. However, despite their importance, the nature of the progenitor systems that give rise to SNe Ia has not been hitherto elucidated. Observational evidence favors the double-degenerate channel in which merging white dwarf binaries lead to SNe Ia. Furthermore, significant discrepancies exist between observations and theory, and to date, ther...

  17. Evidence for a link between atmospheric thermonuclear detonations and nitric acid

    International Nuclear Information System (INIS)

    Holdsworth, G.

    1986-01-01

    Data are presented for an ice core, which show that during the era of intense atmospheric thermonuclear weapons testing, a significant part of the nitrate content in the snow was modulated by the intensity of the nuclear detonations. The fixation of nitrogen by nuclear fireballs leads to NOsub(x) gases in the atmosphere and ultimately to nitric acid in precipitation. At certain concentrations, these gases and the associated aerosols may perturb the climate. (author)

  18. Hydrodynamic simulations of a combined hydrogen, helium thermonuclear runaway on a 10-km neutron star

    International Nuclear Information System (INIS)

    Starrfield, S.; Kenyon, S.; Truran, J.W.; Sparks, W.M.

    1983-01-01

    We have used a Lagrangian, hydrodynamic stellar-evolution computer code to evolve a thermonuclear runaway in the accreted hydrogen rich envelope of a 1.0M, 10-km neutron star. Our simulation produced an outburst which lasted about 2000 sec and peak effective temperature was 3 keV. The peak luminosity exceeded 2 x 10 5 L. A shock wave caused a precursor in the light curve which lasted 10 -5 sec

  19. The historical record for Sirius - Evidence for a white-dwarf thermonuclear runaway?

    Science.gov (United States)

    Bruhweiler, Frederick C.; Kondo, Yoji; Sion, Edward M.

    1986-01-01

    Evidence was recently presented that in medieval times Sirius was a bright red star, rather than the present bluish-white star. Here, the results of attempts to detect possible planetary nebula ejecta toward Sirius using data obtained by the IUE are presented. Based on these results and in the light of recent advances in understanding white-dwarf evolution, it is proposed that Sirius B underwent a recent thermonuclear runaway event triggered by a diffusion-induced CN reaction.

  20. Neutronics and mass transport in a chemical reactor associated with controlled thermonuclear fusion reactor

    International Nuclear Information System (INIS)

    Dang, V.D.; Steinberg, M.; Lazareth, O.W.; Powell, J.R.

    1976-05-01

    The formation of ozone from oxygen and the dissociation carbon dioxide to carbon monoxide and oxygen is studied in a gamma-neutron chemical process blanket associated with a controlled thermonuclear reactor. Materials used for reactor tube wall will affect the efficiency of the energy absorption by the reactants and consequently the yield of reaction products. Three kinds of materials, aluminum, stainless steel and fiber (Al 2 O 3 )-aluminium are investigated for the tube wall material in the study

  1. Role of thermonuclear instabilities of recent models of nova-stars

    Energy Technology Data Exchange (ETDEWEB)

    Secco, L [Padua Univ. (Italy). Ist. di Astronomia

    1981-10-11

    In this paper, a review models of nova-star explosion based on the original suggestion by Kraft and developed during about ten years (from 1967) is presented. The aim is to summarize the most salient results of those theoretical models and to point out the many aspects of the problems that are still unsettled. In particular, thermonuclear instabilities both in perfect and electron-degenerate gas are analyzed, since they seem to be at the base of the nova explosion phenomena.

  2. Frontiers in propulsion research: Laser, matter-antimatter, excited helium, energy exchange thermonuclear fusion

    Science.gov (United States)

    Papailiou, D. D. (Editor)

    1975-01-01

    Concepts are described that presently appear to have the potential for propulsion applications in the post-1990 era of space technology. The studies are still in progress, and only the current status of investigation is presented. The topics for possible propulsion application are lasers, nuclear fusion, matter-antimatter annihilation, electronically excited helium, energy exchange through the interaction of various fields, laser propagation, and thermonuclear fusion technology.

  3. Critical density and disruptions in α-heated thermonuclear Tokamak discharges

    International Nuclear Information System (INIS)

    Cotsaftis, M.; Firestone, M.; Wang, P.K.C.

    1985-02-01

    The study of existence of a critical density limit has been extended to the case of thermonuclear α-particle heated regime. To proceed, a 0-D model including sources and sinks affecting the evolution of ion and electron temperatures and of electron and α-particle densities with auxiliary neutral injected power has been developed. It is mainly shown when considering a Tokamak machine adapted for thermonuclear performances that, like in previous case, there is a critical density above which no other equilibrium point than 0 does exist. Temperatures then drop down the 0 past this critical value, leading to disruption. Analytic expression for critical density is given in terme of auxiliary projected power Psup(N). For Psup(N)=0, critical density value is low, but it increases fast enough for small Psup(N) to give a large safety margin once Psup(N) is moderate, much below the power required for reaching thermonuclear regime. So it is only at shutdown power periods that critical density can be crossed. But in this case, the heat content of particles in the discharge can significantly contribute to smooth out the temperature drop off. This typically operates up to the point where, due to change in magnetic islands configuration resulting from profile modification due to energy release at critical density crossing, heat transport doubles. Then on a fast thermal diffusion time scale, temperature drops now to a new equilibrium value, which can be made above the limiting value for which position control system of the plasma cannot forbid the plasma current to drop off itself, which is the important phenomenon of disruption. So on top of controls previously discussed, it is possible to use the α-particles themselves as a new preventive control against disruptions, making this phenomenon less dangerous for thermonuclear regime operation

  4. Investigation of possibilities of ignition of target plasma in conditions of inertial thermonuclear synthesis

    International Nuclear Information System (INIS)

    Andreev, A.A.; Gus'kov, S.Yu.; Rozanov, V.B.; Il'in, D.V.; Levkovskij, A.A.; Sherman, V.E.

    2001-01-01

    On the basis of mathematical simulation of thermonuclear burning of DT-plasma of laser targets one calculated G factors of thermonuclear intensification for a space and a spark ignitions at various parameters of target plasma and igniters (both isobaric and isochoric). One calculated the critical parameters of igniters upon reaching of which the efficient thermonuclear burst with G ∼ 100 took place. It is shown that further increase of temperature and of dimensions of igniters does not practically affect the efficiency of DT-fuel burnup and independently of the way of ignition G value may be estimated using a simple asymptotic expression. At the same time the values of the critical parameters of igniters depend essentially on the way of ignition and on target parameters. One studied in detail the spark ignition with isochoric igniter. Thermal energy generated at absorption of supershort additional laser pulse is shown to be the key critical parameter for the optimal isochoric igniters. Critical parameters of this energy are calculated [ru

  5. The NC3Rs gateway: Accelerating scientific discoveries with new 3Rs models and technologies.

    Science.gov (United States)

    Percie du Sert, Nathalie; Robinson, Vicky

    2018-01-01

    This editorial introduces the NC3Rs gateway, which publishes articles and reviews on new models and technologies emerging from NC3Rs-funded research. The aim is to raise awareness about these approaches, increase confidence in their capability, and provide sufficient information to facilitate their uptake by others.

  6. Soft-decision decoding of RS codes

    DEFF Research Database (Denmark)

    Justesen, Jørn

    2005-01-01

    By introducing a few simplifying assumptions we derive a simple condition for successful decoding using the Koetter-Vardy algorithm for soft-decision decoding of RS codes. We show that the algorithm has a significant advantage over hard decision decoding when the code rate is low, when two or more...

  7. Association between ACE (rs4646994), FABP2 (rs1799883), MTHFR (rs1801133), FTO (rs9939609) Genes Polymorphism and Type 2 Diabetes with Dyslipidemia.

    Science.gov (United States)

    Raza, Syed Tasleem; Abbas, Shania; Siddiqi, Zeba; Mahdi, Farzana

    2017-01-01

    Diabetic dyslipidemia is one of the leading causes of coronary artery disease (CAD) death. Genetic and environmental factors play an important role in the development of type 2 diabetes mellitus (T2DM) and dyslipidemia. The present study was aimed to investigate the association of ACE (rs4646994), FABP2 (rs1799883), MTHFR (rs1801133) and FTO (rs9939609) genes polymorphism in T2DM with dyslipidemia. Totally, 559 subjects including 221 T2DM cases with dyslipidemia, 158 T2DM without dyslipidemia and 180 controls were enrolled. ACE genes polymorphism was evaluated by polymerase chain reaction (PCR), while MTHFR , FABP2 , FTO genes polymorphisms were evaluated by PCR and restriction fragment length polymorphism (RFLP). Significant association of ACE and MTHFR genes polymorphisms were found in both group of cases [T2DM with dyslipidemia (Pgenes polymorphisms were significantly associated with T2DM without dyslipidemia (P=0.038, and P= 0.019, respectively). This study concludes that ACE , FABP2 , FTO and MTHFR genes are associated with T2DM. Additionally, it also seems that ACE and MTHFR genes might be further associated with the development of dyslipidemia in T2DM cases.

  8. Quantitative evaluation of pairs and RS steganalysis

    Science.gov (United States)

    Ker, Andrew D.

    2004-06-01

    We give initial results from a new project which performs statistically accurate evaluation of the reliability of image steganalysis algorithms. The focus here is on the Pairs and RS methods, for detection of simple LSB steganography in grayscale bitmaps, due to Fridrich et al. Using libraries totalling around 30,000 images we have measured the performance of these methods and suggest changes which lead to significant improvements. Particular results from the project presented here include notes on the distribution of the RS statistic, the relative merits of different "masks" used in the RS algorithm, the effect on reliability when previously compressed cover images are used, and the effect of repeating steganalysis on the transposed image. We also discuss improvements to the Pairs algorithm, restricting it to spatially close pairs of pixels, which leads to a substantial performance improvement, even to the extent of surpassing the RS statistic which was previously thought superior for grayscale images. We also describe some of the questions for a general methodology of evaluation of steganalysis, and potential pitfalls caused by the differences between uncompressed, compressed, and resampled cover images.

  9. The origin of the RS CVn binaries

    International Nuclear Information System (INIS)

    Biermann, P.

    1976-01-01

    Six possible origins for the RS CVn binaries are considered based on the following possibilities. RS CVn binaries might now be either pre-main-sequence or post-main-sequence. A pre-main-sequence binary might not always have been a binary but might have resulted from fission of a rapidly rotating single pre-main-sequence star. The main-sequence counterparts might be either single stars or binaries. To decide which of the six origins is possible, the following observed data for the RS CVn binaries are considered: total mass, total angular momentum, lack of observed connection with regions of star formation, large space density, kinematical age, and the visual companion of WW Dra. In addition lifetimes and space densities of single stars and other types of binaries are considered. The only origin possible is that the RS CVn binaries are in a thermal phase following fission of a main-sequence single star. In this explanation the single star had a rapidly rotating core which became unstable due to the core contraction which made it begin to evolve off the main sequence. The present Be stars might be examples of such parent single stars. (Auth.)

  10. The extraordinarily beautiful physical principle of thermonuclear charge design (on the occasion of the 50th anniversary of the test of RDS-37 - the first Soviet two-stage thermonuclear charge)

    International Nuclear Information System (INIS)

    Goncharov, German A

    2005-01-01

    On 22 November 1955, the Semipalatinsk test site saw the test of the first domestic two-stage thermonuclear RDS-37 charge. The charge operation was based on the principle of radiation implosion. The kernel of the principle consists in the radiation generated in a primary A-bomb explosion and confined by the radiation-opaque casing propagating throughout the interior casing volume and flowing around the secondary thermonuclear unit. The secondary unit experiences a strong compression under the irradiation, with a resulting nuclear and thermonuclear explosion. The RDS-37 explosion was the strongest of all those ever realized at the Semipalatinsk test site. It produced an indelible impression on the participants in the test. This document-based paper describes the genesis of the ideas underlying the RDS-37 design and reflects the critical moments in its development. The advent of RDS-37 was an outstanding accomplishment of the scientists and engineers of our country. (from the history of physics)

  11. FROM THE HISTORY OF PHYSICS: The extraordinarily beautiful physical principle of thermonuclear charge design (on the occasion of the 50th anniversary of the test of RDS-37 — the first Soviet two-stage thermonuclear charge)

    Science.gov (United States)

    Goncharov, German A.

    2005-11-01

    On 22 November 1955, the Semipalatinsk test site saw the test of the first domestic two-stage thermonuclear RDS-37 charge. The charge operation was based on the principle of radiation implosion. The kernel of the principle consists in the radiation generated in a primary A-bomb explosion and confined by the radiation-opaque casing propagating throughout the interior casing volume and flowing around the secondary thermonuclear unit. The secondary unit experiences a strong compression under the irradiation, with a resulting nuclear and thermonuclear explosion. The RDS-37 explosion was the strongest of all those ever realized at the Semipalatinsk test site. It produced an indelible impression on the participants in the test. This document-based paper describes the genesis of the ideas underlying the RDS-37 design and reflects the critical moments in its development. The advent of RDS-37 was an outstanding accomplishment of the scientists and engineers of our country.

  12. The extraordinarily beautiful physical principle of thermonuclear charge design (on the occasion of the 50th anniversary of the test of RDS-37 - the first Soviet two-stage thermonuclear charge)

    Energy Technology Data Exchange (ETDEWEB)

    Goncharov, German A [Russian Federal Nuclear Center ' All-Russian Scientific Research Institute of Experimental Physics' , Sarov, Nizhnii Novgorod Region (Russian Federation)

    2005-11-30

    On 22 November 1955, the Semipalatinsk test site saw the test of the first domestic two-stage thermonuclear RDS-37 charge. The charge operation was based on the principle of radiation implosion. The kernel of the principle consists in the radiation generated in a primary A-bomb explosion and confined by the radiation-opaque casing propagating throughout the interior casing volume and flowing around the secondary thermonuclear unit. The secondary unit experiences a strong compression under the irradiation, with a resulting nuclear and thermonuclear explosion. The RDS-37 explosion was the strongest of all those ever realized at the Semipalatinsk test site. It produced an indelible impression on the participants in the test. This document-based paper describes the genesis of the ideas underlying the RDS-37 design and reflects the critical moments in its development. The advent of RDS-37 was an outstanding accomplishment of the scientists and engineers of our country. (from the history of physics)

  13. Charged-particle thermonuclear reaction rates: IV. Comparison to previous work

    International Nuclear Information System (INIS)

    Iliadis, C.; Longland, R.; Champagne, A.E.; Coc, A.

    2010-01-01

    We compare our Monte Carlo reaction rates (see Paper II of this issue) to previous results that were obtained by using the classical method of computing thermonuclear reaction rates. For each reaction, the comparison is presented using two types of graphs: the first shows the change in reaction rate uncertainties, while the second displays our new results normalized to the previously recommended reaction rate. We find that the rates have changed significantly for almost all reactions considered here. The changes are caused by (i) our new Monte Carlo method of computing reaction rates (see Paper I of this issue), and (ii) newly available nuclear physics information (see Paper III of this issue).

  14. The international thermonuclear experimental reactor and the future of nuclear fusion energy

    International Nuclear Information System (INIS)

    Pan Chuanhong

    2010-01-01

    Energy shortage and environmental problems are now the two largest challenges for human beings. Magnetic confinement nuclear fusion, which has achieved great progress since the 1990's, is anticipated to be a way to realize an ideal source of energy in the future because of its abundance, environmental compatibility, and zero carbon release. Exemplified by the construction of the International Thermonuclear Experimental Reactor (ITER), the development of nuclear fusion energy is now in its engineering phase, and should be realized by the middle of this century if all objectives of the ITER project are met. (author)

  15. Effect of plasma physics on choices of first wall materials and structures for a thermonuclear reactor

    International Nuclear Information System (INIS)

    Meade, D.M.

    1975-01-01

    Impurity ions adversely affect the behavior of present-day tokamaks, and control of impurities is expected to be a key element in determining the feasibility of thermonuclear fusion reactors. The plasma-surface interactions for tokamaks and several techniques for controlling impurities are described. The plasma-surface problem of next generation devices PLT, PDX, DIII and TFTR is expected to be similar to those encountered in a reactor. For these devices calculations indicate that most of the particle energy efflux will be in the 1 keV region. Ironically this energy region has not yet been investigated thoroughly by the surface physicists

  16. A method and apparatus for the manufacture of glass microspheres adapted to contain a thermonuclear fuel

    International Nuclear Information System (INIS)

    Budrick, R.G.; Nolen, R.L. Jr.; Solomon, D.E.; King, F.T.

    1975-01-01

    The invention relates to the manufacture of glass microspheres. It refers to a method according to which a sintered glass-powder, whose particles are calibrated, is introduced into a blow-pipe adapted to project said glass-powder particles into a heated flue, said sintered glass-powder containing a pore-forming agent adapted to expand the glass particles into microspheres which are collected in a chamber situated abode said flue. The method can be applied to the manufacture of microspheres adapted to contain a thermonuclear fuel [fr

  17. Thermonuclear-driven fast magnetosonic-wave heating in tokamak plasmas

    International Nuclear Information System (INIS)

    Sutton, W.R. III.

    1982-01-01

    A thermonuclear driven fast magnetosonic wave instability is investigated in tokamak plasmas for propagation transverse to the external magnetic field at frequencies of several times the alpha particle gyro rate: ω approx. = L Ω/sub α/ = k/sub perpendicular/ v/sub A/, L approx. 4 to 8, k/sub parallel/ << k/sub perpendicular/. The 2-D differential quasi-linear diffusion equation is derived in circular cylindrical, v/sub perpendicular/-v/sub parallel/ geometry. We perform an expansion in the small parameter k/sub parallel/k/sub perpendicucular/ of the quasi-linear diffusion coefficients

  18. Infrared observations of RS CVn stars

    International Nuclear Information System (INIS)

    Berriman, G.; De Campli, W.M.; Werner, M.W.; Hatchett, S.P.

    1983-01-01

    Infrared photometry is presented of the RS CVn binary stars AR Lac (1.2-10 μm) and MM Her (1.2-3.5 μm) as they egressed from their primary and secondary eclipses; of the eclipsing systems RS CVn and Z Her at maximum light (1.2-10 μm) and of the non-eclipsing systems UX Ari and HR 1099 (1.2-10 μm). An analysis of these and published V data based on flux ratio diagrams (linear analogues of colour-colour diagrams) shows that G and K stars supply the infrared light of these systems. None of these systems shows infrared emission from circumstellar matter. (author)

  19. Thermonuclear device

    International Nuclear Information System (INIS)

    Tanaka, Yoshikazu.

    1978-01-01

    Purpose: To uniformly bake the bellows provided for thermal expansion absorption in a toroidal vacuum vessel with no hinderance to the bellows' deformation. Constitution: The outer circumference of bellows is covered with a flexible heat insulation material that does not hinder the bellows from deformation and a heater for supplementing heat radiated from the bellows upon baking is provided in the heat insulating material. The heat insulation material employed is a cotton like material such as asbestos, or glass wool. Baking for the bellows is conducted by way of heat conduction from a heater provided other than in the bellows and the heater provided in the bellows is utilized for supplementing the amount of heat dissipated from the bellows. (Ikeda, J.)

  20. Thermonuclear blankets

    International Nuclear Information System (INIS)

    Kubota, Tadashi.

    1986-01-01

    Purpose: To increase the effective thermal conductivity between lithium ceramic spheres and a metal container. Constitution: The surface of lithium ceramic spheres is coated with a nickel metal, which is further coated with a thin copper layer. Then, copper spheres with a diameter smaller than that of the lithium ceramic spheres are packed in admixture together with the lithium ceramic spheres in an appropriate volume ratio. Since, copper as a relatively soft metal is coated on the surface of the lithium ceramic spheres and the copper spheres are charged to the gaps between each of the lithium ceramic spheres, the area of contact between the lithium ceramic spheres to each other and that between the lithium ceramic spheres and the metal container are easily increased to improve the effective thermal conductivity, by which the heat removing performance of the plant can be improved. (Yoshino, Y.)

  1. Thermonuclear device

    International Nuclear Information System (INIS)

    Furuyama, Masayuki.

    1979-01-01

    Purpose: To provide the subject device wherein a conductive short-circuiting ring is installed in the vicinity of the bonded part of bellows and thick portion of vacuum vessel in the small circumferential direction of torus, thereby to reduce the electromagnetic force generated at the bellows. Constitution: A conductive short-circuiting ring is provided in the vicinity of the connected part of a thick portion and bellows portion. By this organization, a saddle type current generated at the thick portion by a vertical magnetic field flows through the short-circuiting ring because the resistance at a part where the short-circuiting ring is provided is reduced, and the current flowing through the bellows is remarkably reduced. For this reason, the electromagnetic force generated at the bellows is reduced thereby to prevent the bellows from being destroyed by the electromagnetic force. (Yoshihara, H.)

  2. Thermonuclear device

    International Nuclear Information System (INIS)

    Matsuyoshi, Hiroshi; Kiuchi, Teruo.

    1981-01-01

    Purpose: To effectively receive the large hoop force acting in a toroidal magnet coil conductor in a limited space by burying an electrical insulator spacer between confronting coil side surfaces. Constitution: Holes are opened at the confronting portions in space between magnet coil conductors each covered with confronting layer electrical insulators, an electrical insulator spacer is so inserted into the holes as to be partly buried, and the entirety is covered with earth insulators and hardened. Thus, the inner space between the coil conductors can be effectively utilized, the spacer plugs the holes, and when the spacer is independently mechanically machined, it can be engaged within the holes of the coil conductors with high accuracy, so that hoop force produced in the coil conductors can be reliably received by utilizing the space between the coil conductors. (Yoshino, Y.)

  3. Thermonuclear device

    International Nuclear Information System (INIS)

    Kuriyama, Masaaki; Yamamoto, Masahiro; Furuyama, Masayuki; Saito, Ryusei.

    1981-01-01

    Purpose: To enable the efficient and rapid cooling of a vacuum vessel by cooling with gas when the temperature of the vacuum vessel is higher than the boiling point of water and cooling with water when the temperature is lower than the boiling point of water. Constitution: A cooling pipe is provided through an insulating pipe on the outer periphery of a vacuum vessel. The cooling pipe communicates through a cooling gas valve and a coolant valve with a cooling gas supply device and a coolant supply device, and a heat exchanger is disposed at the pipe. When the vessel is higher than the boiling point of the coolant the coolant valve is closed and the cooling gas valve is opened and gas is supplied to cool the vessel. The gas is recoverd through a heat exchanger. On the other hand, when the temperature of vessel is lower than the boiling point of the coolant, the gas valve is closed, the coolant valve is opened, and the vessel is cooled with coolant. The vacuum vessel can be cooled for short time employing both the gas and the coolant together. (Yoshino, Y.)

  4. Generation of thermonuclear fusion neutrons by means of a pure explosion. Part 2. Experimental results

    International Nuclear Information System (INIS)

    Derentowicz, H.; Kaliski, S.; Wolski, J.; Ziolkowski, Z.

    1977-01-01

    This paper presents the experimental results of the generation of a thermonuclear fusion neutrons by means of explosion. The experimental set is based on a quasi-spherical experiment in which a polyethylene layer is shot into a conic region hollowed out in a golden target and filled with deuterium gas. The speeding-up system is based on shooting the conic liner onto the surface of the Cu cone in which the Mach wave is generated and propagates along the cone axis leading to an implosion velocity of the polyethylene layer of the order of (4 - 5).10 6 cm/s. This affords a 10 3 -multiple compression of the D 2 gas (p 0 approximately 1.2 atm) and a neutron emission of the order of 3.10 7 from a mass of about 10 -7 g. This result is in full agreement with theoretical estimates. This is the first published and documented experiment in which a neutron stream of thermonuclear fusion was obtained by means of a pure explosion. (author)

  5. Stabilization of burn conditions in a thermonuclear reactor using artificial neural networks

    Science.gov (United States)

    Vitela, Javier E.; Martinell, Julio J.

    1998-02-01

    In this work we develop an artificial neural network (ANN) for the feedback stabilization of a thermonuclear reactor at nearly ignited burn conditions. A volume-averaged zero-dimensional nonlinear model is used to represent the time evolution of the electron density, the relative density of alpha particles and the temperature of the plasma, where a particular scaling law for the energy confinement time previously used by other authors, was adopted. The control actions include the concurrent modulation of the D-T refuelling rate, the injection of a neutral He-4 beam and an auxiliary heating power modulation, which are constrained to take values within a maximum and minimum levels. For this purpose a feedforward multilayer artificial neural network with sigmoidal activation function is trained using a back-propagation through-time technique. Numerical examples are used to illustrate the behaviour of the resulting ANN-dynamical system configuration. It is concluded that the resulting ANN can successfully stabilize the nonlinear model of the thermonuclear reactor at nearly ignited conditions for temperature and density departures significantly far from their nominal operating values. The NN-dynamical system configuration is shown to be robust with respect to the thermalization time of the alpha particles for perturbations within the region used to train the NN.

  6. Stabilization of burn conditions in a thermonuclear reactor using artificial neural networks

    International Nuclear Information System (INIS)

    Vitela, J.E.; Martinell, J.J.

    1998-01-01

    In this work we develop an artificial neural network (ANN) for the feedback stabilization of a thermonuclear reactor at nearly ignited burn conditions. A volume-averaged zero-dimensional nonlinear model is used to represent the time evolution of the electron density, the relative density of alpha particles and the temperature of the plasma, where a particular scaling law for the energy confinement time previously used by other authors, was adopted. The control actions include the concurrent modulation of the D-T refuelling rate, the injection of a neutral He-4 beam and an auxiliary heating power modulation, which are constrained to take values within a maximum and minimum levels. For this purpose a feedforward multilayer artificial neural network with sigmoidal activation function is trained using a back-propagation through-time technique. Numerical examples are used to illustrate the behaviour of the resulting ANN-dynamical system configuration. It is concluded that the resulting ANN can successfully stabilize the nonlinear model of the thermonuclear reactor at nearly ignited conditions for temperature and density departures significantly far from their nominal operating values. The NN-dynamical system configuration is shown to be robust with respect to the thermalization time of the alpha particles for perturbations within the region used to train the NN. (author)

  7. High-energy, twelve-channel laser facility (DEFIN) for spherical irradiation of thermonuclear targets

    International Nuclear Information System (INIS)

    Basov, N.G.; Danilov, A.E.; Krokhin, O.N.; Kruglov, B.V.; Mikhailov, Yu.A.; Sklizkov, G.V.; Fedotov, S.I.; Fedorov, A.N.

    This paper describes a high-energy, twelve-channel laser facility (DELFIN) intended for high-temperature heating of thermonuclear targets with spherical symmetry. The facility includes a neodymium-glass laser with the ultimate radiation energy of 10 kJ, a pulse length of approximately 10 -10 to 10 -9 s, beam divergence of 5 x 10 -4 radians, a vacuum chamber in which laser radiation interacts with the plasma, and a system of diagnostic instrumentation for the observation of laser beam and plasma parameters. Described are the optical scheme and construction details of the laser facility. Presented is an analysis of focusing schemes for target irradiation and described is the focusing scheme of the DELFIN facility, which is capable of attaining a high degree of spherical symmetry in irradiating targets with maximum beam intensity at the target surface of approximately 10 15 W/cm 2 . This paper examines the most important problems connected with the physical investigations of thermonuclear laser plasma and the basic diagnostic problems involved in their solution

  8. Matching of experimental and statistical-model thermonuclear reaction rates at high temperatures

    International Nuclear Information System (INIS)

    Newton, J. R.; Longland, R.; Iliadis, C.

    2008-01-01

    We address the problem of extrapolating experimental thermonuclear reaction rates toward high stellar temperatures (T>1 GK) by using statistical model (Hauser-Feshbach) results. Reliable reaction rates at such temperatures are required for studies of advanced stellar burning stages, supernovae, and x-ray bursts. Generally accepted methods are based on the concept of a Gamow peak. We follow recent ideas that emphasized the fundamental shortcomings of the Gamow peak concept for narrow resonances at high stellar temperatures. Our new method defines the effective thermonuclear energy range (ETER) by using the 8th, 50th, and 92nd percentiles of the cumulative distribution of fractional resonant reaction rate contributions. This definition is unambiguous and has a straightforward probability interpretation. The ETER is used to define a temperature at which Hauser-Feshbach rates can be matched to experimental rates. This matching temperature is usually much higher compared to previous estimates that employed the Gamow peak concept. We suggest that an increased matching temperature provides more reliable extrapolated reaction rates since Hauser-Feshbach results are more trustwhorthy the higher the temperature. Our ideas are applied to 21 (p,γ), (p,α), and (α,γ) reactions on A=20-40 target nuclei. For many of the cases studied here, our extrapolated reaction rates at high temperatures differ significantly from those obtained using the Gamow peak concept

  9. Gamma-ray emission spectrum from thermonuclear fusion reactions without intrinsic broadening

    DEFF Research Database (Denmark)

    Nocente, M.; Källne, J.; Salewski, Mirko

    2015-01-01

    First principle calculations of the gamma-ray energy spectrum arising from thermonuclear reactions without intrinsic broadening in fusion plasmas are presented, extending the theoretical framework needed to interpret measurements up to the accuracy level enabled by modern high resolution instrume......First principle calculations of the gamma-ray energy spectrum arising from thermonuclear reactions without intrinsic broadening in fusion plasmas are presented, extending the theoretical framework needed to interpret measurements up to the accuracy level enabled by modern high resolution...... instruments. An analytical formula for the spectrum from Maxwellian plasmas, which extends to higher temperatures than the results previously available in the literature, has been derived and used to discuss the assumptions and limitations of earlier models. In case of radio-frequency injection, numerical...... results based on a Monte Carlo method are provided, focusing in particular on improved relations between the peak shift and width from the reaction and the temperature of protons accelerated by radio-frequency heating.The results presented in this paper significantly improve the accuracy of diagnostic...

  10. Nuclear-reaction rates in the thermonuclear runaway phase of accreting neutron stars

    International Nuclear Information System (INIS)

    Wiescher, M.; Barnard, V.; Goerres, J.; Fisker, J.L.; Martinez-Pinedo, G.; Langanke, K.; Rembges, F.; Thielemann, F.K.; Schatz, H.

    2002-01-01

    The rp-process has been suggested as the dominant nucleosynthesis process in explosive hydrogen burning at high temperature and density conditions. The process is characterized by a sequence of fast proton capture reactions and subsequent β-decays. The reaction path of the rp-process runs along the drip line up to Z∼50. Most of the charged-particle reaction rates for the reaction path are presently based on statistical Hauser-Feshbach calculations. While these rates are supposed to be reliable within a factor of two for conditions of high density in the compound nuclei, discrepancies may occur for nuclei near closed shells or near the proton drip line where the Q-values of proton capture processes are typically very small. It has been argued that the thermonuclear runaway is less sensitive to the reaction rates because of the rapid time-scale of the event. However, since these processes may operate at the same time-scale as fast mixing and convection processes, a change in reaction rates indeed may have a significant impact. In this paper we present two examples, the break-out from the hot CNO cycles, and the thermonuclear runaway in X-ray bursts itself, where changes in reaction rates have a direct impact on time-scale, energy generation and nucleosynthesis predictions for the explosive event. (orig.)

  11. International research co-operation in the field of controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    2004-01-01

    This 26th report by the Swiss Federal Office for Education and Science presents a review of work done in Swiss institutes in 2003 as part of international research into thermonuclear fusion. A broad outline of the project and of its significance within the wider field of thermonuclear fusion research is given. This is followed by a review of the significant events in the world of fusion research, with emphasis placed on ITER and on the EURATOM fusion programme. A further chapter summarises events in Switzerland in 2003 and the report closes with a list of contacts for more information. Three annexes provide information on the current situation in fusion research, as well as scientific and technical highlights of the work performed in 2003 at the Plasma Physics Research Centre CRPP at the Federal Institute of Technology EPFL in Lausanne, Switzerland. Annex 3 reports on results obtained at the Physics Institute of the University of Basle. The annexes are for the benefit of the technically and scientifically versed reader, and brief summaries of them are given in the main body of the report

  12. The TDF System for Thermonuclear Plasma Reaction Rates, Mean Energies and Two-Body Final State Particle Spectra

    International Nuclear Information System (INIS)

    Warshaw, S I

    2001-01-01

    The rate of thermonuclear reactions in hot plasmas as a function of local plasma temperature determines the way in which thermonuclear ignition and burning proceeds in the plasma. The conventional model approach to calculating these rates is to assume that the reacting nuclei in the plasma are in Maxwellian equilibrium at some well-defined plasma temperature, over which the statistical average of the reaction rate quantity σv is calculated, where σ is the cross-section for the reaction to proceed at the relative velocity v between the reacting particles. This approach is well-understood and is the basis for much nuclear fusion and astrophysical nuclear reaction rate data. The Thermonuclear Data File (TDF) system developed at the Lawrence Livermore National Laboratory (Warshaw 1991), which is the topic of this report, contains data on the Maxwellian-averaged thermonuclear reaction rates for various light nuclear reactions and the correspondingly Maxwellian-averaged energy spectra of the particles in the final state of those reactions as well. This spectral information closely models the output particle and energy distributions in a burning plasma, and therefore leads to more accurate computational treatments of thermonuclear burn, output particle energy deposition and diagnostics, in various contexts. In this report we review and derive the theoretical basis for calculating Maxwellian-averaged thermonuclear reaction rates, mean particle energies, and output particle spectral energy distributions for these reactions in the TDF system. The treatment of the kinematics is non-relativistic. The current version of the TDF system provides exit particle energy spectrum distributions for two-body final state reactions only. In a future report we will discuss and describe how output particle energy spectra for three- and four-body final states can be developed for the TDF system. We also include in this report a description of the algorithmic implementation of the TDF

  13. Physics of thermo-nuclear fusion and the ITER project; La physique de la fusion thermonucleaire et le projet ITER

    Energy Technology Data Exchange (ETDEWEB)

    Garin, P [CEA Cadarache, Dept. de Recherches sur la Fusion Controlee - DRFC, 13 - Saint-Paul-lez-Durance (France)

    2003-01-01

    This document gathers the slides of the 6 contributions to the workshop 'the physics of thermo-nuclear fusion and the ITER project': 1) the feasibility of magnetic confinement and the issue of heat recovery, 2) heating and current generation in tokamaks, 3) the physics of wall-plasma interaction, 4) recent results at JET, 5) inertial confinement and fast ignition, and 6) the technology of fusion machines based on magnetic confinement. This document presents the principles of thermo-nuclear fusion machines and gives a lot of technical information about JET, Tore-Supra and ITER.

  14. Puzzling thermonuclear burst behaviour from the transient low-mass X-ray binary IGR J17473-2721

    DEFF Research Database (Denmark)

    Chenevez, Jérôme

    2010-01-01

    We investigate the thermonuclear bursting behaviour of IGR J17473-2721, an X-ray transient that in 2008 underwent a six month long outburst, starting (unusually) with an X-ray burst. We detected a total of 57 thermonuclear bursts throughout the outburst with AGILE, Swift, RXTE, and INTEGRAL...... it dropped (at a persistent flux corresponding to 15%of m˙ Edd) a few days before the outburst peak, after which bursts were not detected for a month. As the persistent emission subsequently decreased, the bursting activity resumed at a much lower rate than during the outburst rise. This hysteresis may arise...... produced a similar quenching of burst activity....

  15. Reaching to a featured formula to deduce the energy of the heaviest particles producing from the controlled thermonuclear fusion reactions

    Science.gov (United States)

    Majeed, Raad H.; Oudah, Osamah N.

    2018-05-01

    Thermonuclear fusion reaction plays an important role in developing and construction any power plant system. Studying the physical behavior for the possible mechanism governed energies released by the fusion products to precise understanding the related kinematics. In this work a theoretical formula controlled the general applied thermonuclear fusion reactions is achieved to calculating the fusion products energy depending upon the reactants physical properties and therefore, one can calculate other parameters governed a given reaction. By using this formula, the energy spectrum of 4He produced from T-3He fusion reaction has been sketched with respect to reaction angle and incident energy ranged from (0.08-0.6) MeV.

  16. Association between vitamin D concentration and levels of sex hormones in an elderly Polish population with different genotypes of VDR polymorphisms (rs10735810, rs1544410, rs7975232, rs731236).

    Science.gov (United States)

    Laczmanski, Lukasz; Lwow, Felicja; Mossakowska, Malgorzata; Puzianowska-Kuznicka, Monika; Szwed, Małgorzata; Kolackov, Katarzyna; Krzyzanowska-Swiniarska, Barbara; Bar-Andziak, Ewa; Chudek, Jerzy; Sloka, Natalia; Milewicz, Andrzej

    2015-03-15

    Vitamin D co-regulates the synthesis of sex hormones in part by interaction with its nuclear receptor. The aim of this study was to determine whether there is an association of vitamin D concentration vs the level of sex hormones in elderly Polish individuals with different genotypes of the vitamin D receptor (VDR) gene. Rs10735810, rs1544410, rs7975232, and rs731236 polymorphisms of VDR, the serum sex hormone level, free estrogen index (FEI) and free androgen index (FAI) as well as vitamin D, were evaluated in 766 persons (362 women and 404 men) selected from 5695 Polish population, aged 65-90years from the PolSenior survey. We observed that women with GG (rs731236), TT (rs7975232), BB (rs1544410) and FF (rs10735810) genotypes were characterized by a significant correlation between vitamin D vs testosterone concentration and FAI value. We found a significant correlation between testosterone level and FAI vs vitamin D concentration in men with heterozygote AG in the rs731236 polymorphism and in the GG (rs7975232), the BB (rs1544410), and the Ff (rs10735810) genotypes. In elderly selected Polish population with different genotypes of VDR polymorphisms, a statistically significant relationship between vitamin D concentration vs testosterone level was observed. Copyright © 2015 Elsevier B.V. All rights reserved.

  17. "Special Case" Stellar Blast Teaching Astronomers New Lessons About Cosmic Explosions

    Science.gov (United States)

    2006-07-01

    A powerful thermonuclear explosion on a dense white-dwarf star last February has given astronomers their best look yet at the early stages of such explosions, called novae, and also is giving them tantalizing new clues about the workings of bigger explosions, called supernovae, that are used to measure the Universe. RS Ophiuchi Expansion RS Ophiuchi Expansion CREDIT: Rupen, Mioduszewski & Sokoloski, NRAO/AUI/NSF (Click on image for full-sized image and detailed caption) Using the National Science Foundation's Very Long Baseline Array (VLBA) and other telescopes, "We have seen structure in the blast earlier than in any other stellar explosion," said Tim O'Brien of the University of Manchester's Jodrell Bank Observatory in the U.K. "We see evidence that the explosion may be ejecting material in jets, contrary to theoretical models that assumed a spherical shell of ejected material," O'Brien added. The explosion occurred in a star system called RS Ophiuchi, in the constellation Ophiuchus. RS Ophiuchi consists of a dense white dwarf star with a red giant companion whose prolific stellar wind dumps material onto the surface of the white dwarf. When enough of this material has accumulated, theorists say, a gigantic thermonuclear explosion, similar to a hydrogen bomb but much larger, occurs. Systems such as RS Ophiuchi may eventually produce a vastly more powerful explosion -- a supernova -- when the white dwarf accumulates enough mass to cause it to collapse and explode violently. Because such supernova explosions (called Type 1a supernovae by astronomers) all are triggered as the white dwarf reaches the same mass, they are thought to be identical in their intrinsic brightness. This makes them extremely valuable as "standard candles" for measuring distances in the Universe. "We think the white dwarf in RS Ophiuchi is about as massive as a white dwarf can get, and so is close to the point when it will become a supernova," said Jennifer Sokoloski, of the Harvard

  18. 40 CFR 180.1114 - Pseudomonas fluorescens A506, Pseudomonas fluorescens 1629RS, and Pseudomonas syringae 742RS...

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 23 2010-07-01 2010-07-01 false Pseudomonas fluorescens A506, Pseudomonas fluorescens 1629RS, and Pseudomonas syringae 742RS; exemptions from the requirement of a tolerance... Tolerances § 180.1114 Pseudomonas fluorescens A506, Pseudomonas fluorescens 1629RS, and Pseudomonas syringae...

  19. COX-2 rs689466, rs5275, and rs20417 polymorphisms and risk of head and neck squamous cell carcinoma: a meta-analysis of adjusted and unadjusted data

    International Nuclear Information System (INIS)

    Leng, Wei-Dong; Wen, Xiu-Jie; Kwong, Joey S. W.; Huang, Wei; Chen, Jian-Gang; Zeng, Xian-Tao

    2016-01-01

    Numerous case–control studies have been performed to investigate the association between three cyclooxygenase-2 (COX-2) polymorphisms (rs20417 (−765G > C), rs689466 (−1195G > A), and rs5275 (8473 T > C)) and the risk of head and neck squamous cell carcinoma (HNSCC). However, the results were inconsistent. Therefore, we conducted this meta-analysis to investigate the association. We searched in PubMed, Embase, and Web of Science up to January 20, 2015 (last updated on May 12, 2016). Two independent reviewers extracted the data. Odds ratios (ORs) with their 95 % confidence intervals (CIs) were used to assess the association. All statistical analyses were performed using the Review Manager (RevMan) 5.2 software. Finally 8 case–control studies were included in this meta-analysis. For unadjusted data, an association with increased risk was observed in three genetic models in COX-2 rs689466 polymorphism; however, COX-2 rs5275 and rs20417 polymorphisms were not related to HNSCC risk in this study. The pooled results from adjusted data all revealed non-significant association between these three polymorphisms and risk of HNSCC. We also found a similar result in the subgroup analyses, based on both unadjusted data and adjusted data. Current results suggest that COX-2 rs689466, rs5275, and rs20417 polymorphisms are not associated with HNSCC. Further large and well-designed studies are necessary to validate this association

  20. Mass and Reliability System (MaRS)

    Science.gov (United States)

    Barnes, Sarah

    2016-01-01

    The Safety and Mission Assurance (S&MA) Directorate is responsible for mitigating risk, providing system safety, and lowering risk for space programs from ground to space. The S&MA is divided into 4 divisions: The Space Exploration Division (NC), the International Space Station Division (NE), the Safety & Test Operations Division (NS), and the Quality and Flight Equipment Division (NT). The interns, myself and Arun Aruljothi, will be working with the Risk & Reliability Analysis Branch under the NC Division's. The mission of this division is to identify, characterize, diminish, and communicate risk by implementing an efficient and effective assurance model. The team utilizes Reliability and Maintainability (R&M) and Probabilistic Risk Assessment (PRA) to ensure decisions concerning risks are informed, vehicles are safe and reliable, and program/project requirements are realistic and realized. This project pertains to the Orion mission, so it is geared toward a long duration Human Space Flight Program(s). For space missions, payload is a critical concept; balancing what hardware can be replaced by components verse by Orbital Replacement Units (ORU) or subassemblies is key. For this effort a database was created that combines mass and reliability data, called Mass and Reliability System or MaRS. The U.S. International Space Station (ISS) components are used as reference parts in the MaRS database. Using ISS components as a platform is beneficial because of the historical context and the environment similarities to a space flight mission. MaRS uses a combination of systems: International Space Station PART for failure data, Vehicle Master Database (VMDB) for ORU & components, Maintenance & Analysis Data Set (MADS) for operation hours and other pertinent data, & Hardware History Retrieval System (HHRS) for unit weights. MaRS is populated using a Visual Basic Application. Once populated, the excel spreadsheet is comprised of information on ISS components including

  1. Lack of association between rheumatoid arthritis and genetic variants rs10889677, rs11209026 and rs2201841 of IL-23R gene.

    Science.gov (United States)

    Paradowska-Gorycka, Agnieszka; Malinowski, Damian; Haladyj, Ewa; Olesinska, Marzena; Safranow, Krzysztof; Pawlik, Andrzej

    2018-01-19

    Rheumatoid arthritis (RA) is an autoimmune diseases, where different genetic variants in cytokine genes may play a pathogenic role. A GWAS in autoimmune diseases highlighted the IL-23R gene as a one of the susceptibility factors. We examined three candidate single nucleotide polymorphisms (SNPs) rs10889677, rs11209026 and rs2201841 of the IL-23R gene, as well as determined their possible association with RA in a Polish population. The IL-23R gene polymorphisms were genotyped for 422 RA patients and 348 healthy individuals using TaqMan SNP genotyping assay. The genotypes frequency did not deviate from HWE in each examined group. A comparison of the allele as well as genotype frequencies of the IL-23R polymorphisms under codominant, dominant and recessive genetic model revealed no significant differences between RA patients and healthy subjects. We also demonstrated that IL-23R rs2201841 and rs11209026 as well as rs11209026 and rs10889677 were in complete linkage disequilibrium (D'=1.0). Our genotype-phenotype analysis demonstrated that in carriers of rs10889677C and/or rs2201841A allele the RF, extra-articular manifestations and erosion were more frequent present than in patients with rs10889677A and/or rs2201841A allele, although this association was not significant. Present findings indicated that the autoimmune disease-associated genetic variants in IL-23R gene are not associated with RA in the Polish population. Copyright © 2017 Elsevier España, S.L.U. All rights reserved.

  2. 2001 activity report of the development and research line in controlled thermonuclear fusion of the Plasma Associated Laboratory

    International Nuclear Information System (INIS)

    Ludwig, Gerson Otto

    2002-01-01

    The year 2001 activities of the controlled thermonuclear fusion research line of the Plasma Associated Laboratory at the National Institute for Space Research - Brazil are reported. The report approaches the staff, participation in congresses, goals for the year 2002 and papers on Tokamak plasmas, plasma diagnostic, bootstraps, plasma equilibrium and diagnostic

  3. Cooling device for thermonuclear reactor and modular packing block for the wall realization of a such device

    International Nuclear Information System (INIS)

    Archer, J.; Stalport, G.; Besson, D.; Faron, R.; Coulon, M.

    1988-01-01

    The cooling device for a thermonuclear reactor wall is made by modular thermally conductive heat-resistant blocks (graphite by example), a prismatic head on one face of each block, the opposite face bearing against cooling tubes, a base to each block with an aperture and rods passing through the apertures reversibly fixing each row of blocks to a support [fr

  4. 2003 activity report of the development and research line in controlled thermonuclear fusion of the Plasma Associated Laboratory

    International Nuclear Information System (INIS)

    Ludwig, Gerson Otto

    2004-01-01

    This document represents the 2003 activity report of the development and research line in controlled thermonuclear fusion of the Plasma Associated Laboratory - Brazil, approaching the areas of toroidal systems for magnetic confinement, plasma heating, current generation and high temperature plasma diagnostic

  5. An analysis of the impact of the thermonuclear pilot project ITER on industry and research in Austria

    International Nuclear Information System (INIS)

    Hangel, G.

    2007-03-01

    An analysis of the influence of the thermonuclear pilot project ITER on Austrian research and industrial activities is presented in terms of the following subjects: fusion research history, ITER technique, security, nuclear fusion, ITER (reactor, project specifications for quotations), possibilities for Austrian companies and fusion research in Austria. (nevyjel)

  6. Infrared observations of RS CVn stars

    Science.gov (United States)

    Berriman, G.; De Campli, W. M.; Werner, M. W.; Hatchett, S. P.

    1983-01-01

    The paper presents infrared photometry of the RS CVn binary stars AR Lac (1.2-10 microns) and MM Her (1.2-3.5 microns) as they egressed from their primary and secondary eclipses; of the eclipsing systems RS CVn and Z Her at maximum light (1.2-10 microns) and of the non-eclipsing systems UX Ari and HR 1099 (1.2-10 microns). An analysis of these and published V data based on flux ratio diagrams (linear analogues of color-color diagrams) shows that G and K stars supply the infrared light of these systems. In AR Lac, the combined light of a G5-K0 subgiant and either a late F dwarf or an early F subgiant can account for the observed visual and infrared light curves. None of these systems shows infrared emission from circumstellar matter. This result is simply understood: dust grains would not be expected to form in the physical conditions surrounding the subgiant, and the corona and chromosphere (whose properties have been deduced from spectroscopic X-ray observations) should not produce appreciable infrared emission.

  7. High-Speed RaPToRS

    Science.gov (United States)

    Henchen, Robert; Esham, Benjamin; Becker, William; Pogozelski, Edward; Padalino, Stephen; Sangster, Thomas; Glebov, Vladimir

    2008-11-01

    The High-Speed Rapid Pneumatic Transport of Radioactive Samples (HS-RaPToRS) system, designed to quickly and safely move radioactive materials, was assembled and tested at the Mercury facility of the Naval Research Laboratory (NRL) in Washington D.C. A sample, which is placed inside a four-inch-diameter carrier, is activated before being transported through a PVC tube via airflow. The carrier travels from the reaction chamber to the end station where it pneumatically brakes prior to the gate. A magnetic latch releases the gate when the carrier arrives and comes to rest. The airflow, optical carrier-monitoring devices, and end gate are controlled manually or automatically with LabView software. The installation and testing of the RaPToRS system at NRL was successfully completed with transport times of less than 3 seconds. The speed of the carrier averaged 16 m/s. Prospective facilities for similar systems include the Laboratory for Laser Energetics and the National Ignition Facility.

  8. ( pear cu (SSR) m ultivar marke rs and rs are select effect tions ive for r

    African Journals Online (AJOL)

    SAM

    the most su ers selected tter matrices y. the most im s pyrifolia, Py he terms of the can Journ rs are select. Vilela Res esquita Filho”. PR, Brazil. FLA, Lavras M. 015 in the sout ... Nations Food and. Agricultire Organization (2014), approximately 210 000 ..... Lorenzo S (2011). Genetic variability and diversification process in.

  9. SPIRAL INSTABILITY CAN DRIVE THERMONUCLEAR EXPLOSIONS IN BINARY WHITE DWARF MERGERS

    Energy Technology Data Exchange (ETDEWEB)

    Kashyap, Rahul; Fisher, Robert [Department of Physics, University of Massachusetts Dartmouth, 285 Old Westport Road, North Dartmouth, MA 02740 (United States); García-Berro, Enrique; Aznar-Siguán, Gabriela [Departament de Física Aplicada, Universitat Politècnica de Catalunya, c/Esteve Terrades, 5, E-08860 Castelldefels (Spain); Ji, Suoqing [Department of Physics, Broida Hall, University of California Santa Barbara, Santa Barbara, CA 93106–9530 (United States); Lorén-Aguilar, Pablo [School of Physics, University of Exeter, Stocker Road, Exeter EX4 4QL (United Kingdom)

    2015-02-10

    Thermonuclear, or Type Ia supernovae (SNe Ia), originate from the explosion of carbon–oxygen white dwarfs, and serve as standardizable cosmological candles. However, despite their importance, the nature of the progenitor systems that give rise to SNe Ia has not been hitherto elucidated. Observational evidence favors the double-degenerate channel in which merging white dwarf binaries lead to SNe Ia. Furthermore, significant discrepancies exist between observations and theory, and to date, there has been no self-consistent merger model that yields a SNe Ia. Here we show that a spiral mode instability in the accretion disk formed during a binary white dwarf merger leads to a detonation on a dynamical timescale. This mechanism sheds light on how white dwarf mergers may frequently yield SNe Ia.

  10. The impact of confinement scaling on ITER [International Thermonuclear Experimental Reactor] parameters

    International Nuclear Information System (INIS)

    Reid, R.L.; Galambos, J.D.; Peng, Y.K.M.

    1988-09-01

    Energy confinement scaling is a major concern in the design of the International Thermonuclear Experimental Reactor (ITER). The existing database for tokamaks can be fitted with a number of different confinement scaling expressions that have similar degrees of approximation. These scaling laws predict confinement times for ITER that vary by over an order of magnitude. The uncertainties in the form and magnitude of these scaling laws must be substantially reduced before the plasma performance of ITER can be predicted with adequate reliability. The TETRA systems code is used to calculate the dependence of major ITER parameters on the scaling laws currently in use. Design constraints of interest in the present phase of ITER consideration are used, and the minimum-cost devices arising from these constraints are reviewed. 9 refs., 13 figs., 4 tabs

  11. SPIRAL INSTABILITY CAN DRIVE THERMONUCLEAR EXPLOSIONS IN BINARY WHITE DWARF MERGERS

    International Nuclear Information System (INIS)

    Kashyap, Rahul; Fisher, Robert; García-Berro, Enrique; Aznar-Siguán, Gabriela; Ji, Suoqing; Lorén-Aguilar, Pablo

    2015-01-01

    Thermonuclear, or Type Ia supernovae (SNe Ia), originate from the explosion of carbon–oxygen white dwarfs, and serve as standardizable cosmological candles. However, despite their importance, the nature of the progenitor systems that give rise to SNe Ia has not been hitherto elucidated. Observational evidence favors the double-degenerate channel in which merging white dwarf binaries lead to SNe Ia. Furthermore, significant discrepancies exist between observations and theory, and to date, there has been no self-consistent merger model that yields a SNe Ia. Here we show that a spiral mode instability in the accretion disk formed during a binary white dwarf merger leads to a detonation on a dynamical timescale. This mechanism sheds light on how white dwarf mergers may frequently yield SNe Ia

  12. Simple model for taking into account the effects of plasma screening in thermonuclear reactions

    International Nuclear Information System (INIS)

    Shalybkov, D.A.; Yakovlev, D.G.

    1988-01-01

    In the Thomas-Fermi model of high-density matter analytic calculation is made of the factor by which the rate of the thermonuclear reactions is enhanced by the effects of plasma screening in a degenerate weakly non-ideal electron gas and a strongly nonideal two-component ion liquid with large charge of the ions. The regions of densities and temperatures in which screening due to compressibility of the electron gas plays an important part are found. It is noted that the screening due to this compressibility may be influenced by strong magnetic fields B /approximately/ 10 12 -10 13 G, which quantize the motion of the electrons and change the electron charge screening length in the plasma. The results can be used for the degenerate cores of white dwarfs and shells of neutron stars

  13. Review of the International Thermonuclear Experimental Reactor (ITER) detailed design report

    International Nuclear Information System (INIS)

    1997-01-01

    Dr. Martha Krebs, Director, Office of Energy Research at the US Department of Energy (DOE), wrote to the Fusion Energy Sciences Advisory Committee (FESAC), in letters dated September 23 and November 6, 1996, requesting that FESAC review the International Thermonuclear Experimental Reactor (ITER) Detailed Design Report (DDR) and provide its view of the adequacy of the DDR as part of the basis for the United States decision to enter negotiations with the other interested Parties regarding the terms and conditions for an agreement for the construction, operations, exploitation and decommissioning of ITER. The letter from Dr. Krebs, referred to as the Charge Letter, provided context for the review and a set of questions of specific interest

  14. Evidence for a link between atmospheric thermonuclear detonations and nitric acid.

    Science.gov (United States)

    Holdsworth, G

    1986-12-11

    Suitably located glacier cores, obtained from high-altitude, low-temperature sites, can reveal detailed information about atmospheric air chemistry at sub-annual resolution 1 . Such data may provide input to climate-change models, the study of acid precipitation patterns and many other phenomena. Here I present data from an ice core which show that during the era of intense atmospheric thermonuclear weapons testing (ATWT) a significant part of the nitrate content in the snow was modulated by the intensity of the nuclear detonations. The fixation of nitrogen by nuclear fireballs leads to NO x gases in the atmosphere 2 and ultimately to nitric acid in precipitation. At certain concentrations, these gases and the associated aerosols may perturb the climate 3,4 .

  15. The development of beryllium plasma spray technology for the International Thermonuclear Experimental Reactor (ITER)

    International Nuclear Information System (INIS)

    Castro, R.G.; Elliott, K.E.; Hollis, K.J.; Watson, R.D.

    1999-01-01

    Over the past five years, four international parties, which include the European Communities, Japan, the Russian Federation and the United States, have been collaborating on the design and development of the International Thermonuclear Experimental Reactor (ITER), the next generation magnetic fusion energy device. During the ITER Engineering Design Activity (EDA), beryllium plasma spray technology was investigated by Los Alamos National Laboratory as a method for fabricating and repairing and the beryllium first wall surface of the ITER tokamak. Significant progress has been made in developing beryllium plasma spraying technology for this application. Information will be presented on the research performed to improve the thermal properties of plasma sprayed beryllium coatings and a method that was developed for cleaning and preparing the surface of beryllium prior to depositing plasma sprayed beryllium coatings. Results of high heat flux testing of the beryllium coatings using electron beam simulated ITER conditions will also be presented

  16. 8 GHz, high power, microwave system for heating of thermonuclear plasmas

    International Nuclear Information System (INIS)

    Di Giovenale, S.; Fortunato, T.; Mirizzi, F.; Roccon, M.; Sassi, M.; Tuccillo, A.A.; Maffia, G.; Baldi, L.

    1993-01-01

    The Frascati Tokamak Upgrade (FTU) is a machine included in the European Thermonuclear Fusion Program aimed at investigating high density plasmas in the presence of powerful additional RF heating systems. The Lower Hybrid Resonant Heating (LHRH) system, based on 9 independent modules, works at 8 GHz, and will generate, at full performances, a total amount of 9 MW, in the pulsed regime (pulse length = 1 s, duty cycle = 1/600). The microwave power source is a gyrotron oscillator, developed by Thomson Tubes Electroniques (France) for this specific application, and capable of producing up to 1 MW. An overmoded, low loss, circular waveguide transmits the RF power toward the plasma; an array of 12x4 rectangular waveguides (the 'grill') launches this power into the plasma. The paper describes the LHRH system for FTU and analyses both its main performances and experimental results

  17. ITER [International Thermonuclear Experimental Reactor] shield and blanket work package report

    International Nuclear Information System (INIS)

    1988-06-01

    This report summarizes nuclear-related work in support of the US effort for the International Thermonuclear Experimental Reactor (ITER) Study. The purpose of this work was to prepare for the first international ITER workshop devoted to defining a basic ITER concept that will serve as a basis for an indepth conceptual design activity over the next 2-1/2 years. Primary tasks carried out during the past year included: design improvements of the inboard shield developed for the TIBER concept, scoping studies of a variety of tritium breeding blanket options, development of necessary design guidelines and evaluation criteria for the blanket options, further safety considerations related to nuclear components and issues regarding structural materials for an ITER device. 44 refs., 31 figs., 29 tabs

  18. Reflectometry and transport in thermonuclear plasmas in the Joint European Torus

    International Nuclear Information System (INIS)

    Sips, A.C.C.

    1991-01-01

    The subjects of this thesis are the study of microwave reflectometry as a method to measure electron density profiles, and the study of particle and energy transport in thermonuclear plasmas. In the transport studies data of a 12-channel reflectometer system are used to analyze the propagation of electron density perturbations in the plasma. The measurements described in this thesis are performed in the plasmas in the Joint European Torus (JET). The main points of study described are based on microwave reflectometry, the principles of which are given. Two modes of operation of a reflectometer are described. Firstly, electro-magnetic waves with constant frequencies may be launched into the plasma to measure variations in the electron density profile. Secondly, the absolute density profile can be measured with a reflectometer, when the source frequencies are swept. (author). 56 refs.; 41 figs.; 5 tabs

  19. A high-recycle divertor for ITER [International Thermonuclear Experimental Reactor

    International Nuclear Information System (INIS)

    Werley, K.A.; Bathke, C.G.

    1988-01-01

    A coupled one-dimensional (axial/radial) edge-plasma model (SOLAR) has been used to investigate tradeoffs between collector-plate and edge-plasma conditions in a doublenull, open, high-recycle divertor (HRD) for a preliminary International Thermonuclear Experimental Reactor (ITER) design. A steady-state HRD produces in attractive high-density edge plasma (5 /times/ 10 19 m/sup /minus/3/) with sufficiently low plasma temperature (10-20eV) at a tungsten plat that the sheath-accelerated ions are below sputtering threshold energies. Manageable plate heat fluxes (3-6 MW/m 2 ) are achieved by positioning the plate poloidal cross section at a minimum angle of 15-30/degree/ with respect to flux surfaces. 6 refs., 9 figs

  20. Review of the International Thermonuclear Experimental Reactor (ITER) detailed design report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-18

    Dr. Martha Krebs, Director, Office of Energy Research at the US Department of Energy (DOE), wrote to the Fusion Energy Sciences Advisory Committee (FESAC), in letters dated September 23 and November 6, 1996, requesting that FESAC review the International Thermonuclear Experimental Reactor (ITER) Detailed Design Report (DDR) and provide its view of the adequacy of the DDR as part of the basis for the United States decision to enter negotiations with the other interested Parties regarding the terms and conditions for an agreement for the construction, operations, exploitation and decommissioning of ITER. The letter from Dr. Krebs, referred to as the Charge Letter, provided context for the review and a set of questions of specific interest.

  1. Organization of the ITER [International Thermonuclear Experimental Reactor] Project - Sharing of information and procurements

    International Nuclear Information System (INIS)

    Shannon, T.E.

    1990-01-01

    The International Thermonuclear Experimental Reactor (ITER) project is expected to fully confirm the scientific feasibility and to address the technological feasibility of fusion power. Consequently, the machine must be designed for controlled ignition and extended burn of deuterium-tritium plasma. It must also demonstrate and perform integrated testing of components required to utilize fusion power for practical purposes. Cooperation among four countries/organizations (United States, Soviet Union, Japan, and EURATOM) to build a single experimental reactor will reduce the cost for each country and provide an international pool of scientific and engineering resources. This paper describes ITER organization for conceptual design activity, schedule for conceptual design activities, ITER operating parameters, conceptual project schedule and cost, future plans, basic principles and problems related to task sharing, and basic principles in handling of intellectual property

  2. Structural characteristics of proposed ITER [International Thermonuclear Experimental Reactor] TF [toroidal field] coil conductor

    International Nuclear Information System (INIS)

    Gibson, C.R.; Miller, J.R.

    1988-01-01

    This paper analyzes the effect of transverse loading on a cable-in-conduit conductor which has been proposed for the toroidal field coils of the International Thermonuclear Experimental Reactor. The primary components of this conductor are a loose cable of superconducting wires, a thin-wall tube for helium containment, and a U-shaped structural channel. A method is given where the geometry of this conductor can be optimized for a given set of operating conditions. It is shown, using finite-element modeling, that the structural channel is effective in supporting loads due to transverse forces and internal pressure. In addition, it is shown that the superconducting cable is effectively shielded from external transverse loads that might otherwise degrade its current carrying capacity. 10 refs., 10 figs., 3 tabs

  3. International research co-operation in the field of controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    Conscience, J.-F.

    2003-01-01

    This final report for the Swiss Federal Office of Education and Science presents a review of activities carried out in 2002 within the framework of the International Experimental Thermonuclear Reactor (ITER) project that involves contributions from Canada, Japan, the Russian Federation and the European Union. Further agreements on the development of a fusion reactor with other countries, including Switzerland, the USA and China, are mentioned. The first chapter describes the current state of research on electricity production using nuclear fusion and discusses feasibility, safety, environmental, fuel supply and economic aspects. A second chapter reviews global efforts in the fusion area, including ITER and EURATOM projects and the activities running under the European Fusion Development Agreement EFDA and the JET Implementing Agreement. Finally, a third chapter deals with fusion research activities in Switzerland and the contributions made to international research by Swiss universities and institutes

  4. Annual report of the Summit Members' Working Group on Controlled Thermonuclear Fusion (Fusin Working Group (FWG))

    International Nuclear Information System (INIS)

    1987-04-01

    The Summit Members' Working Group on Controlled Thermonuclear Fusion [Fusion Working Group (FWG)] was established in 1983 in response to the Declaration of the Heads of State and Government at the Versailles Economic Summit meeting of 1982, and in response to the subsequent report of the Working Group in Technology, Growth and Employment (TGE) as endorsed at the Williamsburg Summit meeting, 1983. This document contains the complete written record of each of the three FWG meetings which include the minutes, lists of attendees, agendas, statements, and summary conclusions as well as the full reports of the Technical Working Party. In addition, there is a pertinent exchange of correspondence between FWG members on the role of the Technical Working Party and a requested background paper on the modalities associated with a possible future ETR project

  5. Application of the partitive analytical forecasting (PAF) technique to the United States controlled thermonuclear research effort

    International Nuclear Information System (INIS)

    Nichols, S.P.

    1975-01-01

    The Partitive Analytical Forecasting (PAF) technique is applied to the overall long-term program plans for the Division of Controlled Thermonuclear Research (DCTR) of the United States Energy Research and Development Administration (ERDA). As part of the PAF technique, the Graphical Evaluation and Review Technique (GERTS) IIIZ computer code is used to perform simulations on a logic network describing the DCTR long-term program plan. Logic networks describing the tokamak, mirror, and theta-pinch developments are simulated individually and then together to form an overall DCTR program network. The results of the simulation of the overall network using various funding schemes and strategies are presented. An economic sensitivity analysis is provided for the tokamak logic networks. An analysis is also performed of the fusion-fission hybrid concept in the context of the present DCTR goals. The results mentioned above as well as the PAF technique itself are evaluated, and recommendations for further research are discussed

  6. International Thermonuclear Experimental Reactor: Physics issues, capabilities and physics program plans

    International Nuclear Information System (INIS)

    Wesley, J.C.

    1997-01-01

    Present status and understanding of the principal plasma-performance determining physics issues that affect the physics design and operational capabilities of the International Thermonuclear Experimental Reactor (ITER) [ITER EDA Agreement and Protocol 2 (International Atomic Energy Agency, Vienna, 1994)] are presented. Emphasis is placed on the five major physics-basis issues emdash energy confinement, beta limit, density limit, impurity dilution and radiation loss, and the feasibility of obtaining partial-detached divertor operation emdash that directly affect projections of ITER fusion power and burn duration performance. A summary of these projections is presented and the effect of uncertainties in the physics-basis issues is examined. ITER capabilities for experimental flexibility and plasma-performance optimization are also described, and how these capabilities may enter into the ITER physics program plan is discussed. copyright 1997 American Institute of Physics

  7. Thermonuclear Reaction Rate Libraries and Software Tools for Nuclear Astrophysics Research

    International Nuclear Information System (INIS)

    Smith, Michael S.; Cyburt, Richard; Schatz, Hendrik; Smith, Karl; Warren, Scott; Ferguson, Ryan; Wiescher, Michael; Lingerfelt, Eric; Buckner, Kim; Nesaraja, Caroline D.

    2008-01-01

    Thermonuclear reaction rates are a crucial input for simulating a wide variety of astrophysical environments. A new collaboration has been formed to ensure that astrophysical modelers have access to reaction rates based on the most recent experimental and theoretical nuclear physics information. To reach this goal, a new version of the REACLIB library has been created by the Joint Institute for Nuclear Astrophysics (JINA), now available online at http://www.nscl.msu.edu/~nero/db. A complementary effort is the development of software tools in the Computational Infrastructure for Nuclear Astrophysics, online at nucastrodata.org, to streamline, manage, and access the workflow of the reaction evaluations from their initiation to peer review to incorporation into the library. Details of these new projects will be described

  8. Use of liquid metals in nuclear and thermonuclear engineering, and in other innovative technologies

    Science.gov (United States)

    Rachkov, V. I.; Arnol'dov, M. N.; Efanov, A. D.; Kalyakin, S. G.; Kozlov, F. A.; Loginov, N. I.; Orlov, Yu. I.; Sorokin, A. P.

    2014-05-01

    By now, a good deal of experience has been gained with using liquid metals as coolants in nuclear power installations; extensive knowledge has been gained about the physical, thermophysical, and physicochemical properties of these coolants; and the scientific principles and a set of methods and means for handling liquid metals as coolants for nuclear power installations have been elaborated. Prototype and commercialgrade sodium-cooled NPP power units have been developed, including the BOR-60, BN-350, and BN-600 power units (the Soviet Union); the Rapsodie, Phenix, and Superphenix power units (France), the EBR-II power unit (the United States); and the PFR power unit (the United Kingdom). In Russia, dedicated nuclear power installations have been constructed, including those with a lead-bismuth coolant for nuclear submarines and with sodium-potassium alloy for spacecraft (the Buk and Topol installations), which have no analogs around the world. Liquid metals (primarily lithium and its alloy with lead) hold promise for use in thermonuclear power engineering, where they can serve not only as a coolant, but also as tritium-producing medium. In this article, the physicochemical properties of liquid metal coolants, as well as practical experience gained from using them in nuclear and thermonuclear power engineering and in innovative technologies are considered, and the lines of further research works are formulated. New results obtained from investigations carried out on the Pb-Bi and Pb for the SVBR and BREST fast-neutron reactors (referred to henceforth as fast reactors) and for controlled accelerator systems are described.

  9. First implosion experiments with cryogenic thermonuclear fuel on the National Ignition Facility

    International Nuclear Information System (INIS)

    Glenzer, Siegfried H; Spears, Brian K; Edwards, M John; Berger, Richard L; Bleuel, Darren L; Bradley, David K; Caggiano, Joseph A; Callahan, Debra A; Castro, Carlos; Choate, Christine; Clark, Daniel S; Cerjan, Charles J; Collins, Gilbert W; Dewald, Eduard L; Di Nicola, Jean-Michel G; Di Nicola, Pascale; Divol, Laurent; Dixit, Shamasundar N; Alger, Ethan T; Casey, Daniel T

    2012-01-01

    Non-burning thermonuclear fuel implosion experiments have been fielded on the National Ignition Facility to assess progress toward ignition by indirect drive inertial confinement fusion. These experiments use cryogenic fuel ice layers, consisting of mixtures of tritium and deuterium with large amounts of hydrogen to control the neutron yield and to allow fielding of an extensive suite of optical, x-ray and nuclear diagnostics. The thermonuclear fuel layer is contained in a spherical plastic capsule that is fielded in the center of a cylindrical gold hohlraum. Heating the hohlraum with 1.3 MJ of energy delivered by 192 laser beams produces a soft x-ray drive spectrum with a radiation temperature of 300 eV. The radiation field produces an ablation pressure of 100 Mbar which compresses the capsule to a spherical dense fuel shell that contains a hot plasma core 80 µm in diameter. The implosion core is observed with x-ray imaging diagnostics that provide size, shape, the absolute x-ray emission along with bangtime and hot plasma lifetime. Nuclear measurements provide the 14.1 MeV neutron yield from fusion of deuterium and tritium nuclei along with down-scattered neutrons at energies of 10–12 MeV due to energy loss by scattering in the dense fuel that surrounds the central hot-spot plasma. Neutron time-of-flight spectra allow the inference of the ion temperature while gamma-ray measurements provide the duration of nuclear activity. The fusion yield from deuterium–tritium reactions scales with ion temperature, which is in agreement with modeling over more than one order of magnitude to a neutron yield in excess of 10 14 neutrons, indicating large confinement parameters on these first experiments. (paper)

  10. Temperature measurements in thermonuclear plasmas; Mesures des temperatures dans les plasmas thermonucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Breton, D [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The temperatures needed to produce thermonuclear reactions are of the order of several million degrees Kelvin. Devising methods for measuring such temperatures has been the subject of research in many countries. In order to present the problem clearly and to demonstrate its importance, the author reviews the various conditions which must be fulfilled in order that reactions may be qualified as thermonuclear. The relationship between the temperature and the cross-section of the reactions is studied, and it is shown that the notion of temperature in the plasmas is complex, which leads to a consideration of the temperature of the ions and that of the electrons. None of the methods for the temperature measurements is completely satisfactory because of the hypotheses which must be made, and which are seldom fulfilled during high-intensity discharges in the plasmas. In practice it is necessary to use several methods simultaneously. (author) [French] Les temperatures necessaires pour produire des reactions thermonucleaires sont de l'ordre de plusieurs millions de degres Kelvin. Les methodes envisagees pour mesurer ces temperatures font l'objet de recherches dans de nombreux pays. Afin de preciser le probleme et de montrer son importance, l'auteur rappelle les conditions qui doivent etre reunies pour que des reactions puissent etre qualifiees thermonucleaires. Il etudie la relation entre la temperature et la section efficace des reactions et montre que la notion de temperature dans les plasmas est complexe, ce qui amene a considerer la temperature des ions et celle des electrons. Aucune des methodes de mesure des temperatures n'est completement satisfaisante en raison des hypotheses qu'elles exigent et qui sont rarement realisees lors des decharges a haute intensite dans les plasmas. En pratique, il est necessaire d'utiliser plusieurs methodes simultanement. (auteur)

  11. RaPToRS Sample Delivery System

    Science.gov (United States)

    Henchen, Robert; Shibata, Kye; Krieger, Michael; Pogozelski, Edward; Padalino, Stephen; Glebov, Vladimir; Sangster, Craig

    2010-11-01

    At various labs (NIF, LLE, NRL), activated material samples are used to measure reaction properties. The Rapid Pneumatic Transport of Radioactive Samples (RaPToRS) system quickly and safely moves these radioactive samples through a closed PVC tube via airflow. The carrier travels from the reaction chamber to the control and analysis station, pneumatically braking at the outlet. A reversible multiplexer routes samples from various locations near the shot chamber to the analysis station. Also, the multiplexer allows users to remotely load unactivated samples without manually approaching the reaction chamber. All elements of the system (pneumatic drivers, flow control valves, optical position sensors, multiplexers, Geiger counters, and release gates at the analysis station) can be controlled manually or automatically using a custom LabVIEW interface. A prototype is currently operating at NRL in Washington DC. Prospective facilities for Raptors systems include LLE and NIF.

  12. ARIES-RS safety design and analysis

    International Nuclear Information System (INIS)

    Steiner, D.; El-Guebaly, L.; Herring, S.; Khater, H.; Mogahed, E.; Thayer, R.; Tillack, M.S.

    1997-01-01

    The ARIES-RS safety design and analysis focused on achieving two objectives: (1) The avoidance of sheltering or evacuation in the event of an accident; and (2) the generation of only low-level waste, no greater than Class C. The ARIES-RS baseline design employs V-4Cr-4Ti as the blanket structural material and a low activation ferritic steel in the reflector and shield. In the event of a LOCA, the baseline design first wall maximum temperature falls in the range of 1100-1200 C. For this temperature range, the hazard assessment indicates that the dose at the site boundary will be less than 1 rem per year. Thus, no sheltering or evacuation would be required in the event of a LOCA. Although the baseline design satisfies the first safety objective noted above, a first wall maximum temperature of ∝1100-1200 C would likely compromise the integrity of the vanadium blanket structure and would require blanket replacement following such a temperature excursion. To avoid this situation, a modified blanket design incorporating supplemental heat removal is also proposed. Preliminary analysis of this modified design suggests that the first wall maximum temperature can be kept below the temperature range of concern, ∝1000-1100 C, in the event of a LOCA. When the ferritic steel used in the reflector and shield is one reduced in Ir and Ag impurities, all in-vessel components qualify for near-surface shallow land burial as Class C low-level waste. (orig.)

  13. Design Report for Isolated RS-485 Bus Node

    Science.gov (United States)

    2016-07-01

    TERMS Android , RS-485, isolated, USB, smartphone 16. SECURITY CLASSIFICATION OF: 17. LIMITATION OF ABSTRACT UU 18. NUMBER...controlled wired RS-485 network. The Android -based smartphone or tablet is used in conjunction with a USB to serial bridge to operate as the bus master in...the system. The Android device operates in USB Host mode and communicates to the RS-485 bus as if a single peripheral on the USB bus. 15. SUBJECT

  14. Association of PTPN22 (rs2476601) and STAT4 (rs7574865) polymorphisms with Rheumatoid Arthritis in the Western Algerian population.

    Science.gov (United States)

    Fodil, M; Benzaoui, A; Zemani-Fodil, F; Aberkane, M; Boughrara, W; Saidi-Mehtar, N; Petit-Teixeira, E; Boudjema, A

    2015-01-01

    The aim of the present study was to replicate the association of five risk gene polymorphisms (PTPN22-rs2476601, STAT4-rs7574865, 6q23-rs6927172, IRF5-rs2004640 and TRAF1/C5-rs10818488) with RA in a specific population of the Western Algeria. The study group comprised 110 patients with RA and 197 ethnically matched healthy control subjects. All polymorphisms were genotyped using predesigned TaqMan® assays. Allele and genotype frequencies in patients and control subjects were compared by chi-square test and odds ratios with 95% confidence intervals. Correction for multiple testing was carried out using the Bonferroni adjustment. Statistically significant associations with RA were detected. The strongest signal was obtained for PTPN22-rs2476601 with an allelic Pvalue 3.32 x 10(-11) (OR = 9.83, 95% CI [4.28 - 22.56]). A second significant association was obtained with STAT4-rs7574865 (allelic Pvalue = 4 x 10(-3); OR = 1.75, 95% CI [1.16 - 2.63]). The third SNP, 6q23-rs6927172, showed a significant result of association with RA, but missed our criteria for significance at allelic level after Bonferroni's correction (allelic Pvalue = 0.027; OR = 0.64, 95% CI [0.42 - 0.97]). Finally, IRF5-rs2004640 and TRAF1/C5-rs10818488 showed a significant association only at genotypic level (Pvalues: 3 x 10(-4) and 2.9 x 10(-3) respectively) but did not reach statistical significance when comparing allele frequencies (Pvalues: 0.96 and 0.21 respectively). From this initial study, we can conclude that PTPN22-rs2476601 and STAT4-rs7574865 polymorphisms are clearly associated with the risk of RA in the Western Algerian population.

  15. Association of PTPN22 (rs2476601 and STAT4 (rs7574865 polymorphisms with Rheumatoid Arthritis in the Western Algerian population

    Directory of Open Access Journals (Sweden)

    Mostefa FODIL

    2015-01-01

    Full Text Available Aim: The aim of the present study was to replicate the association of five risk gene polymorphisms (PTPN22-rs2476601, STAT4-rs7574865, 6q23-rs6927172, IRF5-rs2004640 and TRAF1/C5-rs10818488 with RA in a specific population of the Western Algeria. Material and methods: The study group comprised 110 patients with RA and 197 ethnically matched healthy control subjects. All polymorphisms were genotyped using predesigned TaqMan® assays. Allele and genotype frequencies in patients and control subjects were compared by chi-square test and odds ratios with 95% confidence intervals. Correction for multiple testing was carried out using the Bonferroni adjustment. Results: Statistically significant associations with RA were detected. The strongest signal was obtained for PTPN22-rs2476601 with an allelic Pvalue 3.32 x 10-11 (OR = 9.83, 95% CI [4.28 – 22.56]. A second significant association was obtained with STAT4-rs7574865 (allelic Pvalue = 4 x 10-3; OR = 1.75, 95% CI [1.16 – 2.63]. The third SNP, 6q23-rs6927172, showed a significant result of association with RA, but missed our criteria for significance at allelic level after Bonferroni’s correction (allelic Pvalue = 0.027; OR = 0.64, 95% CI [0.42 – 0.97]. Finally, IRF5-rs2004640 and TRAF1/C5-rs10818488 showed a significant association only at genotypic level (Pvalues: 3 x 10-4 and 2.9 x 10-3 respectively but did not reach statistical significance when comparing allele frequencies (Pvalues: 0.96 and 0.21 respectively. Conclusions: From this initial study, we can conclude that PTPN22-rs2476601 and STAT4-rs7574865 polymorphisms are clearly associated with the risk of RA in the Western Algerian population.

  16. Towards a new generation of control and data acquisition systems for thermonuclear fusion research

    International Nuclear Information System (INIS)

    Van Haren, P.C.

    1993-01-01

    Because of the complexity of thermonuclear fusion test reactors, control systems are indispensable. The physical properties of the reactor medium, i.e. the plasma, are still not well understood. Therefore, many diagnostic techniques are applied to investigate the plasma and to discover its properties. As a consequence, data acquisition systems play an important role in thermonuclear fusion research. This thesis reports on three projects that were carried out in the field of control and data acquisition. The target experiment is the Rijnhuizen Tokamak Project (RTP), a medium-sized experiment dedicated to studies of transport in the reactor medium. One of the projects is aimed at the development of a new Plasma Position and Current Control feedback System (PPCCS). This system evaluates signals of a large (about 20) number of sensors, computes the actual state of the plasma from these signals and generates command signals for the power supplies that govern the plasma position. The most ambitious project described in this thesis is the development of a data acquisition system, called TRAMP (Transient Recorders and Amoeba Multi Processor), that aims to be a testbed for smart data acquisition strategies. TRAMP attempts to acquire and store temporarily all possible data at a high sampling frequency from a single RTP pulse, and accommodates for a resampling in software prior to transferring the data to a mass storage facility. The software resampling frequency can be tuned by analysis of the acquired data and, in that way, only interesting data will be stored. In the course of the development of both the above-mentioned systems it turned out that the existing database format applied for managing experimental data provided many hurdles in the realization of efficient solutions. Consequently, a new database format was developed together with software to deal with it. This new database, called DOM4 (Data Organization and Management), is now applied at all data acquisition

  17. Igniting the Light Elements: The Los Alamos Thermonuclear Weapon Project, 1942-1952

    Energy Technology Data Exchange (ETDEWEB)

    Fitzpatrick, Anne C. [Virginia Polytechnic Inst. and State Univ. (Virginia Tech), Blacksburg, VA (United States)

    1999-07-01

    The American system of nuclear weapons research and development was conceived and developed not as a result of technological determinism, but by a number of individual architects who promoted the growth of this large technologically-based complex. While some of the technological artifacts of this system, such as the fission weapons used in World War II, have been the subject of many historical studies, their technical successors--fusion (or hydrogen) devices--are representative of the largely unstudied highly secret realms of nuclear weapons science and engineering. In the postwar period a small number of Los Alamos Scientific Laboratory's staff and affiliates were responsible for theoretical work on fusion weapons, yet the program was subject to both the provisions and constraints of the US Atomic Energy Commission, of which Los Alamos was a part. The Commission leadership's struggle to establish a mission for its network of laboratories, least of all to keep them operating, affected Los Alamos's leaders' decisions as to the course of weapons design and development projects. Adapting Thomas P. Hughes's ''large technological systems'' thesis, I focus on the technical, social, political, and human problems that nuclear weapons scientists faced while pursuing the thermonuclear project, demonstrating why the early American thermonuclear bomb project was an immensely complicated scientific and technological undertaking. I concentrate mainly on Los Alamos Scientific Laboratory's Theoretical, or T, Division, and its members' attempts to complete an accurate mathematical treatment of the ''Super''--the most difficult problem in physics in the postwar period--and other fusion weapon theories. Although tackling a theoretical problem, theoreticians had to address technical and engineering issues as well. I demonstrate the relative value and importance of H-bomb research over time in the postwar era to

  18. Chemically ignited thermonuclear reactions: A near-term means for a high specific impulse - High thrust propulsion system

    International Nuclear Information System (INIS)

    Winterberg, F.

    1982-01-01

    A proposal for the fissionless ignition of small thermonuclear reactions is made which involves the combination of the magnetic booster target inertial fusion concept with the chemical implosion of metallic shells. The magnetic booster employs a very dense and magnetically confined low yield thermonuclear plasma to trigger an inertially confined high yield plasma. Fissionless ignition permits smaller yields than with fission- or fusion-induced fusion bombs, yields that are appropriate for use in a spacecraft propulsion system. Each bomb would release about 10 to the 18th erg or 100 tons of TNT, and with one explosion per second, an average thrust of 10 to the third tons and a specific impulse of about 3000 seconds can be expected

  19. Configuration control plan for the ports NCS IBM RS/6000

    International Nuclear Information System (INIS)

    Brown, A.S.

    1996-01-01

    This document describes the actions and responsibilities for maintaining the quality and integrity of the NS software resident on the IBM RS/6000 workstation managed by the Nuclear Criticality Safety group at the Portsmouth Gaseous Diffusion Plant. This document does not address the validation of NS software packages for the RS/6000

  20. USB and RS232 voltage datalogger

    Directory of Open Access Journals (Sweden)

    Lorenzo Hernández Tabares

    2011-01-01

    Full Text Available Normal 0 21 false false false MicrosoftInternetExplorer4 st1:*{behavior:url(#ieooui } /* Style Definitions */ table.MsoNormalTable {mso-style-name:"Tabla normal"; mso-tstyle-rowband-size:0; mso-tstyle-colband-size:0; mso-style-noshow:yes; mso-style-parent:""; mso-padding-alt:0cm 5.4pt 0cm 5.4pt; mso-para-margin:0cm; mso-para-margin-bottom:.0001pt; mso-pagination:widow-orphan; font-size:10.0pt; font-family:"Times New Roman"; mso-ansi-language:#0400; mso-fareast-language:#0400; mso-bidi-language:#0400;} The design and construction of a PIC microcontroller based datalogger with USB 2.0 and RS232 interfaces is presented. The datalogger has one 0 to +10VDC analogue input, 10bits ADC, Real Time Clock, 4k sample room on the microcontroller’s program flash memory and an external DC power supply. This paper proposes a cheap variant to construct such device widely used in meteorological and environmental instrumentation among others. The prototype was attached to an Ultraviolet Photometric O3 Analyzer for recording the environmental (tropospheric ozone concentration in a control station at the Havana city. Key words: datalogger, USB, enviromental ozone

  1. Participation of the Instituto de Pesquisas Espaciais in the national program for plasma physics and controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    1990-01-01

    This is a report concerning the participation of the Instituto de Pesquisas Espaciais in the national program for plasma physics and controlled thermonuclear fusion. The report lists all the personnel enroled in research activities, both theoretical and experimental. The research subjects are the following: relativistic electron beams; plasma produced by laser; plasma theory; quiescent plasma; plasma centrifugal; ionic propulsion. (A.C.A.S.) [pt

  2. Modeling of secondary emission processes in the negative ion based electrostatic accelerator of the International Thermonuclear Experimental Reactor

    OpenAIRE

    G. Fubiani; H. P. L. de Esch; A. Simonin; R. S. Hemsworth

    2008-01-01

    The negative ion electrostatic accelerator for the neutral beam injector of the International Thermonuclear Experimental Reactor (ITER) is designed to deliver a negative deuterium current of 40 A at 1 MeV. Inside the accelerator there are several types of interactions that may create secondary particles. The dominating process originates from the single and double stripping of the accelerated negative ion by collision with the residual molecular deuterium gas (≃29% losses). The resulting seco...

  3. Thermonuclear fusion: from fundamental research to energy production? Science and technology report No. 26

    International Nuclear Information System (INIS)

    Laval, Guy; Blanzat, Bernard; Aspect, Alain; Aymar, Robert; Bielak, Bogdan; Decroisette, Michel; Martin, Georges; Andre, Michel; Schirmann, Daniel; Garbet, Xavier; Jacquinot, Jean; Laviron, Clement; Migus, Arnold; Moreau, Rene; Pironneau, Olivier; Quere, Yves; Vallee, Alain; Dercourt, Jean; Bayer, Charles; Juraszek, Denis; Deutsch, Claude; Le Garrec, Bruno; Hennequin, Pascale; Peysson, Yves; Rax, Jean-Marcel; Pesme, Denis; Bauche, Jacques; Monier-Garbet, Pascale; Stamm, Roland; Zerah, Gilles; Ghendrih, Philippe; Layet, Roland; Grosman, Andre; Alamo, Ana; Giancarli, Luciano; Poitevin, Yves; Rigal, Emmanuel; Chieze, Jean-Pierre

    2007-01-01

    This work has been commissioned by the French ministry of Education, Sciences and Research, its aim is to provide a reliable account of the state of development of thermonuclear fusion. This report makes a point on the scientific knowledge accumulated on the topic and highlights the research programs that are necessary to overcome the technological difficulties and draws the necessary steps before an industrial application to electricity production. This report is divided into 10 chapters: 1) tokamak technology and ITER, 2) inertial fusion, 3) magnetized hot plasmas, 4) laser-plasma interaction and peta-watt lasers, 5) atomic physics and fusion, 6) computer simulation, 7) plasma-wall interaction, 8) materials for fusion reactors, 9) safety analysis, and 10) inertial fusion and astrophysics. This report has been written by a large panel of experts gathered by the French Academy of Sciences. The comments on the issue by the 3 French organizations: Cea, Cnrs and SFP (French Society of Physics) follow the last chapter

  4. Reaction rate and composition dependence of the stability of thermonuclear burning on accreting neutron stars

    International Nuclear Information System (INIS)

    Keek, L.; Cyburt, R. H.; Heger, A.

    2014-01-01

    The stability of thermonuclear burning of hydrogen and helium accreted onto neutron stars is strongly dependent on the mass accretion rate. The burning behavior is observed to change from Type I X-ray bursts to stable burning, with oscillatory burning occurring at the transition. Simulations predict the transition at a 10 times higher mass accretion rate than observed. Using numerical models we investigate how the transition depends on the hydrogen, helium, and CNO mass fractions of the accreted material, as well as on the nuclear reaction rates of 3α and the hot-CNO breakout reactions 15 O(α, γ) 19 Ne and 18 Ne(α, p) 21 Na. For a lower hydrogen content the transition is at higher accretion rates. Furthermore, most experimentally allowed reaction rate variations change the transition accretion rate by at most 10%. A factor 10 decrease of the 15 O(α, γ) 19 Ne rate, however, produces an increase of the transition accretion rate of 35%. None of our models reproduce the transition at the observed rate, and depending on the true 15 O(α, γ) 19 Ne reaction rate, the actual discrepancy may be substantially larger. We find that the width of the interval of accretion rates with marginally stable burning depends strongly on both composition and reaction rates. Furthermore, close to the stability transition, our models predict that X-ray bursts have extended tails where freshly accreted fuel prolongs nuclear burning.

  5. Thermonuclear generation program: risks and safety; Programa de geracao termonuclear: seus riscos e segurancas

    Energy Technology Data Exchange (ETDEWEB)

    Goes, Alexandre Gromann de Araujo

    1999-07-01

    This work deals with the fundamental concepts of risk and safety related to nuclear power generation. In the first chapter, a general evaluation of the various systems for energy generation and their environmental impacts is made. Some definitions for safety and risk are suggested, based on the already existing regulatory processes and also on the current tendencies of risk management. Aspects regarding the safety culture are commented. The International Nuclear Event Scale (INES), a coherent and clear mechanism of communication between nuclear specialists and the general public, is analyzed. The second chapter examines the thermonuclear generation program in Brazil and the role of the National Nuclear Energy Commission. The third chapter presents national and international scenarios in terms of safety and risks, available policies and the main obstacles for future development of nuclear energy and nuclear engineering, and strategies are proposed. In the last chapter, comments about possible trends and recommendations related to practical risk management procedures, taking into account rational criteria for resources distribution and risk reduction are made, envisaging a closer integration between nuclear specialists and the society as a whole, thus decreasing the conflicts in a democratic decision-making process.

  6. Audit of United States portion of the International Thermonuclear Experimental Reactor project

    International Nuclear Information System (INIS)

    1993-01-01

    Worldwide efforts in fusion energy research are designed to develop fusion power as a safe, environmentally sound, and economically competitive source of energy. The International Thermonuclear Experimental Reactor (ITER) project is a worldwide effort to demonstrate the scientific and technological feasibility of fusion power. The European Community, Japan, the Russian Federation, and the United States are collaborating on ITER, with each of the four parties expected to equally share costs and benefits. Shared costs for the current engineering design phase of the project are estimated at $1 billion in 1989 dollars, excluding certain management and support costs to be absorbed by each partner, with an early estimate of $6 billion, also in 1989 dollars, for construction of the reactor. Engineering design formally began in July 1992, and this phase is in its formative stages. The US had already spent about $100 million since 1987 on ITER conceptual design activities and other preparatory activities in advance of the engineering design phase. Because of its cost significance, the importance of ITER to the US fusion energy program, and the project's unique aspects which may provide a framework for future international endeavors, we initiated an audit of the ITER project. The purpose of the audit was to evaluate management controls over the US portion of the ITER project. Our objectives was to determine whether key front-end controls were in place to ensure that the project could be managed in an efficient and effective manner

  7. Thermonuclear targets for direct-drive ignition by a megajoule laser pulse

    Energy Technology Data Exchange (ETDEWEB)

    Bel’kov, S. A.; Bondarenko, S. V. [Russian Federal Nuclear Center, All-Russia Research Institute of Experimental Physics (Russian Federation); Vergunova, G. A. [Russian Academy of Sciences, Lebedev Physical Institute (Russian Federation); Garanin, S. G. [Russian Federal Nuclear Center, All-Russia Research Institute of Experimental Physics (Russian Federation); Gus’kov, S. Yu., E-mail: guskov@sci.lebedev.ru; Demchenko, N. N.; Doskoch, I. Ya.; Kuchugov, P. A. [Russian Academy of Sciences, Lebedev Physical Institute (Russian Federation); Zmitrenko, N. V. [Russian Academy of Sciences, Keldysh Institute of Applied Mathematics (Russian Federation); Rozanov, V. B.; Stepanov, R. V.; Yakhin, R. A. [Russian Academy of Sciences, Lebedev Physical Institute (Russian Federation)

    2015-10-15

    Central ignition of a thin two-layer-shell fusion target that is directly driven by a 2-MJ profiled pulse of Nd laser second-harmonic radiation has been studied. The parameters of the target were selected so as to provide effective acceleration of the shell toward the center, which was sufficient for the onset of ignition under conditions of increased hydrodynamic stability of the ablator acceleration and compression. The aspect ratio of the inner deuterium-tritium layer of the shell does not exceed 15, provided that a major part (above 75%) of the outer layer (plastic ablator) is evaporated by the instant of maximum compression. The investigation is based on two series of numerical calculations that were performed using one-dimensional (1D) hydrodynamic codes. The first 1D code was used to calculate the absorption of the profiled laser-radiation pulse (including calculation of the total absorption coefficient with allowance for the inverse bremsstrahlung and resonance mechanisms) and the spatial distribution of target heating for a real geometry of irradiation using 192 laser beams in a scheme of focusing with a cubo-octahedral symmetry. The second 1D code was used for simulating the total cycle of target evolution under the action of absorbed laser radiation and for determining the thermonuclear gain that was achieved with a given target.

  8. A conceptual design of the International Thermonuclear Experimental Reactor for the Central Solenoid

    International Nuclear Information System (INIS)

    Heim, J.R.; Parker, J.M.

    1990-01-01

    Conceptual design of the International Thermonuclear Experimental Reactor (ITER) superconducting magnet system is nearing completion by the ITER Design Team, and one of the Central Solenoid (CS) designs is presented. The CS part of this magnet system will be a vertical stack of eight modules, approximately 16 m high, each having a approximate dimensions of: 4.1-m o.d., 2.8-m i.d., 1.9-m h. The peak field at the bore is approximately 13.5 T. Cable-in-conduit conductor with Nb 3 Sn composite wire will be used to wind the coils. The overall coil fabrication will use the insulate-wind-react-impregnate method. Coil modules will be fabricated using double-pancake coils with all splice joints located in the low-field region on the outside of the coils. All coils will be structurally graded with high-strength steel reinforcement which is co-wound with the conductor. We describe details of the CS coil design and analysis

  9. Design of the ITER (International Thermonuclear Experimental Reactor) neutral beam system beamline, United States concept

    International Nuclear Information System (INIS)

    Purgalis, P.; Anderson, O.A.; Cooper, W.S.; DeVries, G.E.; Lietzke, A.F.; Kunkel, W.B.; Kwan, J.W.; Matuk, C.A.; Nakai, T.; Stearns, J.W.; Soroka, L.; Wells, R.P.; Lindquist, W.B.; Neef, W.S.; Reginato, L.L.; Sedgley, D.W.; Brook, J.W.; Luzzi, T.E.; Myers, T.J.

    1989-01-01

    Design of a neutral beamline for ITER (International Thermonuclear Experimental Reactor) is described. The design incorporates a barium surface conversion D - source feeding a linear array of accelerator channels. The system uses a dc accelerator with electrostatic quadrupoles for strong focusing. A high voltage power supply that is integrated with the accelerator is presented as an attractive option. A gas neutralizer is used and residual ions exiting the neutralizer are deflected to watercooled dumps. Cryopanels are located at the accelerator exit to pump excess gas from the source and the neutralizer, and in the ion dump cavity to pump re-neutralized ions and neutralizer gas. All the above components are packaged in compact identical, independent modules that can be removed for remote maintenance. The neutral beam system delivers 75 MW of D degree into three ports with a total of nine modules arranged in stacks of three modules per port. To increase reliability each module is designed to deliver up to 10 MW at 1.3 MeV; this allows eight modules operating at partial capacity to deliver the required power in the event one module is removed from service. Radiation protection is provided by shielding and by locating critical components in the source and accelerator 35 m from the port into the torus. Neutron shielding in the drift duct provides the added feature of limiting conductance and thus reducing gas flow to and from the torus. Alternative component choices are also discussed for the evolving design. 8 refs., 4 figs., 1 tab

  10. Theory of the energy development in a thermonuclear plasma of deuterium and of deuterium-tritium

    Energy Technology Data Exchange (ETDEWEB)

    Magnac-Valette, D; Lacombe, E; Cuer, P [Particle Physics Laboratory, Strasbourg (France)

    1958-07-01

    We have studied the evolution of a thermonuclear mixture for concentrations of 10{sup 18} and 10{sup 17} ions per cm{sup 3} and for temperatures of (116 and 1160) x 10{sup 6}K, taking into account the contribution from secondary reactions. It is assumed that no deuterium or tritium are supplied during the evolution time. The temperature is assumed constant and the pinching of the charged species perfect. Neutrons leave the mixture without causing any secondary reactions because of their long mean free path. Integration of the differential equations describing the evolution of the mixture yields the total nuclear power in the plasma, and the power carried off by the neutrons. The calculations were made with the aid of an electronic computer. The initial concentration is unimportant since a scaling of the concentrations changes nothing if the inverse scaling is carried out on the time variable. It is assumed, moreover, that the thermalizing time is negligible in comparison with the mean life of the particles. The calculations were performed using a successive approximation method in which the mesh size was selected such that the error was always less than 10{sup -6}. The results are presented in the paper.

  11. Conception of thermonuclear reactor with a shielding layer of the first wall

    International Nuclear Information System (INIS)

    Marin, S.V.

    1979-01-01

    Considered is the way of the shielding of the first wall of a thermonuclear reactor by the layer of ISSEC (Internal spectral shifter and Energy Converter). It is a constructive non-power element placed between a plasma and the first wall, and intended for the softening of the spectrum and intensity reduction of particle fluxes falling on the first wall. Results of neutron-physical calculations of the UWMAK-type reactor blanket (in the S 4 -P 3 approximation) are presented. While comparing five materials (C, Mo, Nb, V,W) by the rate of radiation damage formation, gas production, radioactivity level and energy output in the blanket with the 316 stainless steel first wall, it is obvious that the conception of ISSEC permits to prolong the service period of the first wall. Construction elements should be then in the same irradiation conditions as those in fast reactors. Molybdenum has been taken as the best ISSEC material. It reduces the number of displaced atoms of the first wall by 20% and decreases helium production by about 100%, increases energy output in the blanket by 15-18%. However, graphite is advantageous, while comparing it to molybdenum in values of residual energy output, radioactivity level, costs and manufacture simplicity. One problem stays unsolved, which is connected with chemical sputtering of graphite at the formation of C 2 H 2 in the high temperature range. So it is hard to prefer any material now

  12. Requirements for US regulatory approval of the International Thermonuclear Experimental Reactor (ITER)

    International Nuclear Information System (INIS)

    Petti, D.A.; Haire, J.C.

    1993-12-01

    The International Thermonuclear Experimental Reactor (ITER) is the first fusion machine that will have sufficient decay heat and activation product inventory to pose potential nuclear safety concerns. As a result, nuclear safety and environmental issues will be much more important in the approval process for the design, siting, construction, and operation of ITER in the United States than previous fusion devices, such as the Tokamak Fusion Test Reactor. The purpose of this report is (a) to provide an overview of the regulatory approval process for a Department of Energy (DOE) nuclear facility; (b) to present the dose limits used by DOE to protect workers, the public, and the environment from the risks of exposure to radiation and hazardous materials; (c) to discuss some key nuclear safety-related issues that must be addressed early in the Engineering Design Activities (EDA) to obtain regulatory approval; and (d) to provide general guidelines to the ITER Joint Central Team (JCT) concerning the development of a regulatory framework for the ITER project

  13. Cleaning and air conditioning device for atmosphere in thermonuclear reactor chamber

    International Nuclear Information System (INIS)

    Ishida, Seiji.

    1993-01-01

    The device of the present invention removes tritium efficiently and attains ventilation and conditioning of a great amount of air flow. That is, there are disposed a humidity separator, a filter, a heater, a catalyst filled layer, a water jetting type humidifying heat insulation cooler and a cooler in this order from an inlet side (upstream) of contaminated room atmospheric gases. The catalyst filled layer, etc. are incorporated integrally into the ventilation air conditioning facility for ventilating air in the chamber of the thermonuclear reactor, to clean a tritium atmosphere at the same time. Accordingly, the device is made compact as a whole. A limit for the air flow rate owing to the use of the conventional catalyst tower and adsorbing tower is eliminated. Then a ventilating air conditioning for a great flow rate can be attained. Tritium is removed by cooling and dehumidification without using any adsorbent. Accordingly, an adsorbing tower is no more necessary and conventional regeneration operation is not required. As a result, space for installation is reduced, the system is simplified and the cost for construction and facility can be reduced. (I.S.)

  14. The Canadian initiative to bring the international thermonuclear experimental reactor to Canada

    International Nuclear Information System (INIS)

    James, R.A.

    1996-01-01

    The International Thermonuclear Experimental Reactor (ITER) is the next step in fusion research. It is expected to be the last major experimental facility, before the construction of a prototype commercial reactor. The Engineering Design Activities (EDA) of ITER are being funded by the USA, Japan, the Russian Federation, and the European Union, with each of the major parties contributing about 25% of the cost. Canada participates as part of the European coalition. The EDA is due to be completed in 1998, and the major funding partners are preparing for the decision on the siting and construction of ITER. The Canadian Fusion Fuels Technology Project (CFFTP) formed a Canadian ITER Siting Task Group to study siting ITER in Canada. The study indicated that hosting ITER would provide significant benefits, both technological and economic, to Canada. We have also confirmed that there would be substantial benefits to the ITER Project. CFFTP then formed a Canadian ITER Siting Board, with representation from a broad range of stakeholders, to champion, 'Canada as Host'. This paper briefly outlines the ITER Project, and the benefits to both Canada and the Project of a Canadian site. With this as background, the paper discusses the international scene and assesses Canada's prospects of being chosen to host ITER. (author)

  15. Thermonuclear Bursts with Short Recurrence Times from Neutron Stars Explained by Opacity-driven Convection

    Energy Technology Data Exchange (ETDEWEB)

    Keek, L. [X-ray Astrophysics Laboratory, Astrophysics Science Division, NASA/GSFC, Greenbelt, MD 20771 (United States); Heger, A., E-mail: laurens.keek@nasa.gov [Monash Center for Astrophysics, School of Physics and Astronomy, Monash University, Victoria, 3800 (Australia)

    2017-06-20

    Thermonuclear flashes of hydrogen and helium accreted onto neutron stars produce the frequently observed Type I X-ray bursts. It is the current paradigm that almost all material burns in a burst, after which it takes hours to accumulate fresh fuel for the next burst. In rare cases, however, bursts are observed with recurrence times as short as minutes. We present the first one-dimensional multi-zone simulations that reproduce this phenomenon. Bursts that ignite in a relatively hot neutron star envelope leave a substantial fraction of the fuel unburned at shallow depths. In the wake of the burst, convective mixing events driven by opacity bring this fuel down to the ignition depth on the observed timescale of minutes. There, unburned hydrogen mixes with the metal-rich ashes, igniting to produce a subsequent burst. We find burst pairs and triplets, similar to the observed instances. Our simulations reproduce the observed fraction of bursts with short waiting times of ∼30%, and demonstrate that short recurrence time bursts are typically less bright and of shorter duration.

  16. Dust processing device for inside of vacuum vessel of thermonuclear reactor

    International Nuclear Information System (INIS)

    Okumura, Atsushi; Tsujimura, Seiichi; Takahashi, Kenji; Ueda, Yasutoshi; Kuwata, Masayasu; Onozuka, Masaki.

    1995-01-01

    The device of the present invention can occasionally recover dusts in a vacuum vessel of a thermonuclear reactor. In addition, fine powdery dusts are never scattered to the vacuum vessel. Namely, a processing device main body comprises a locally sealed space in the vacuum vessel. A blow-up device blows up and floats dusts accumulated in the vacuum vessel to the processing device main body. A discharge plate electrically charges the floating dusts by discharge. An electrode collects the charged dusts. Collected dusts are recovered together with a pressurized gas through a dust recovering port to the outside of the processing device. With such a constitution, it is not necessary to release the vacuum vessel to the atmosphere and evacuate after the completion of the collection of the dusts on every time when the dusts are generated as in the prior art. It is no more necessary for an operator to enter into the vacuum vessel and recover the dusts. Since fine powdery dusts are never scattered in the vacuum vessel, no undesired effects are given to exhaustion facilities and instruments of the vacuum vessel. (I.S.)

  17. Heating and cooling device for use in the vacuum container of a thermonuclear device

    International Nuclear Information System (INIS)

    Morita, Hiroaki; Onozuka, Masanori; Fukui, Hiroshi.

    1986-01-01

    Purpose: To prevent the generation of great temperature difference within a hollow doughnuts-shaped space of the torus vacuum container of a tokamak type thermonuclear reactor, as well as effectively eliminate the local injection of heat to the vacuum container. Constitution: A hollow doughnuts-like space is formed between the inner wall and the double outer wall of a vacuum container main body, which is divided into a plurality of regions by partition plates extended in the toroidal direction. An input/output header is disposed in adjacent with each of the partition plates for inputting/outputting heat medium. Further, heat medium inlet/outlets are disposed to define two flow channels on every one-half circumference. This enables to reduce the temperature difference of the heat medium between the inlet and the outlet by the shortening of the flow channel length and heating or cooling can be performed without causing unevenness in the temperature distribution of the vacuum container. (Horiuchi, T.)

  18. Vulnerability assessment of a space based weapon platform electronic system exposed to a thermonuclear weapon detonation

    Science.gov (United States)

    Perez, C. L.; Johnson, J. O.

    Rapidly changing world events, the increased number of nations with inter-continental ballistic missile capability, and the proliferation of nuclear weapon technology will increase the number of nuclear threats facing the world today. Monitoring these nation's activities and providing an early warning and/or intercept system via reconnaissance and surveillance satellites and space based weapon platforms is a viable deterrent against a surprise nuclear attack. However, the deployment of satellite and weapon platform assets in space will subject the sensitive electronic equipment to a variety of natural and man-made radiation environments. These include Van Allen Belt protons and electrons; galactic and solar flare protons; and neutrons, gamma rays, and x-rays from intentionally detonated fission and fusion weapons. In this paper, the MASH vl.0 code system is used to estimate the dose to the critical electronics components of an idealized space based weapon platform from neutron and gamma-ray radiation emitted from a thermonuclear weapon detonation in space. Fluence and dose assessments were performed for the platform fully loaded, and in several stages representing limited engagement scenarios. The results indicate vulnerabilities to the Command, Control, and Communication bay instruments from radiation damage for a nuclear weapon detonation for certain source/platform orientations. The distance at which damage occurs will depend on the weapon yield (n,(gamma)/kiloton) and size (kilotons).

  19. Advanced 3-dimensional electron kinetic calculations for the current drive problem in magnetically confined thermonuclear plasmas

    International Nuclear Information System (INIS)

    Peysson, Y.; Decker, J.; Bers, A.; Ram, A.; Harvey, R.

    2004-01-01

    Accurate and fast electron kinetic calculations is a challenging issue for realistic simulations of thermonuclear tokamak plasmas. Relativistic corrections and electron trajectory effects must be fully taken into account for high temperature burning plasmas, while codes should also consistently describe wave-particle resonant interactions in presence of locally large gradients close to internal transport barrier. In that case, neoclassical effects may come into play and self-consistent evaluation of both the radio-frequency and bootstrap currents must be performed. In addition, a complex interplay between momentum and radial electron dynamics may take place, in presence of a possible energy dependent radial transport. Besides the physics needs, there are considerable numerical issues to solve, in order to reduce computer time consumption and memory requirements at an acceptable level, so that kinetic calculations may be valuably incorporated in a chain of codes which determines plasma equilibrium and wave propagation. So far, fully implicit 3-dimensional calculations based on a finite difference scheme and an incomplete L and U matrices factorization have been found to be so most effective method to reach this goal. A review of the present status in this active field of physics is presented, with an emphasis on possible future improvements. (authors)

  20. Ohmic heating coil power supply using thyristor circuit breaker in a thermonuclear fusion device

    International Nuclear Information System (INIS)

    Tani, Keiji; Shimada, Ryuichi; Tamura, Sanae; Yabuno, Kohei; Koseki, Shoichiro.

    1982-01-01

    In a large scale Tokamak thermonuclear fusion device such as the critical plasma testing facility (JT60) presently under construction, mechanical breakers such as vacuum and air breakers are mostly used for interrupting DC heavy current which is supplied to the ohmic heating coils of inductive energy accumulation method. The practical use of the DC breakers employing thyristors has just been started because the history of thyristor development is short and thristors are still expensive, in spite of the advantages. In this paper, the circuit is investigated in which the excellent high speed controllability of thyristors is fully utilized, while the economy is taken into accout, and the experiment carried out with a unit model is described. It was found that a thyristor switch, which was constructed by connecting the high speed thyristors of peak off-state voltage rating 2,000 V and mean current rating 500 A in direct parallel, was able to interrupt 12.7 kA current in the power supply circuit of ohmic heating coils developed this time. In addition, the switch configuration was able to be greatly simplified. When the multistage raising of plasma current is required, the raise can be performed with a single thyristor breaker because it can make high speed control. Therefore, the capacity of the breaker can be doubly and drastically reduced. Also, if current unbalance might occur between thyristor switch units, it gives no problem since the time of reverse voltage after current interruption dispersed smaller as current increased. (Wakatsuki, Y.)

  1. Dust processing device for inside of vacuum vessel of thermonuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Okumura, Atsushi; Tsujimura, Seiichi; Takahashi, Kenji; Ueda, Yasutoshi; Kuwata, Masayasu; Onozuka, Masaki

    1995-05-02

    The device of the present invention can occasionally recover dusts in a vacuum vessel of a thermonuclear reactor. In addition, fine powdery dusts are never scattered to the vacuum vessel. Namely, a processing device main body comprises a locally sealed space in the vacuum vessel. A blow-up device blows up and floats dusts accumulated in the vacuum vessel to the processing device main body. A discharge plate electrically charges the floating dusts by discharge. An electrode collects the charged dusts. Collected dusts are recovered together with a pressurized gas through a dust recovering port to the outside of the processing device. With such a constitution, it is not necessary to release the vacuum vessel to the atmosphere and evacuate after the completion of the collection of the dusts on every time when the dusts are generated as in the prior art. It is no more necessary for an operator to enter into the vacuum vessel and recover the dusts. Since fine powdery dusts are never scattered in the vacuum vessel, no undesired effects are given to exhaustion facilities and instruments of the vacuum vessel. (I.S.).

  2. Economic impacts on the United States of siting decisions for the international thermonuclear experimental reactor

    International Nuclear Information System (INIS)

    Peerenboom, J.P.; Hanson, M.E.; Huddleston, J.R.

    1996-08-01

    This report presents the results of a study that examines and compares the probable short-term economic impacts of the International Thermonuclear Experimental Reactor (ITER) on the United States (U.S.) if (1) ITER were to be sited in the U.S., or (2) ITER were to be sited in one of the other countries that, along with the U.S., is currently participating in the ITER program. Life-cycle costs associated with ITER construction, operation, and decommissioning are analyzed to assess their economic impact. A number of possible U.S. host and U.S. non-host technology and cost-sharing arrangements with the other ITER Parties are examined, although cost-sharing arrangements and the process by which the Parties will select a host country and an ITER site remain open issues. Both national and local/regional economic impacts, as measured by gross domestic product, regional output, employment, net exports, and income, are considered. These impacts represent a portion of the complex, interrelated set of economic considerations that characterize U.S. host and U.S. non-host participation in ITER. A number of other potentially important economic and noneconomic considerations are discussed qualitatively

  3. Economic impacts on the United States of siting decisions for the International Thermonuclear Experimental Reactor

    International Nuclear Information System (INIS)

    Peerenboom, J.P.; Wolsko, T.D.; Hanson, M.E.

    1997-01-01

    This paper presents the results of a study that examines and compares the probable short-term economic impacts of the International Thermonuclear Experimental Reactor (ITER) on the United States (U.S.) if (1) ITER were to be sited in the U.S., or (2) ITER were to be sited in one of the other countries that along with the U.S., is currently participating in the ITER program. Life-cycle costs associated with ITER construction, operation, and decommissioning are analyzed to assess their economic impact. A number of possible U.S. host and U.S. non-host technology and cost-sharing arrangements with the other ITER Parties are examined, although cost-sharing arrangements and the process by which the Parties will select a host country and an ITER site remain open issues. Both national and local/regional economic impacts, as measured by gross domestic product, regional output, employment, net exports, and income, are considered. These impacts represent a portion of the complex, interrelated set of economic considerations that characterize U.S. host and U.S. non-host participation in ITER. A number of other potentially important economic and noneconomic considerations are discussed qualitatively

  4. Recommendations for a cryogenic system for ITER [International Thermonuclear Experimental Reactor

    International Nuclear Information System (INIS)

    Slack, D.S.

    1989-01-01

    The International Thermonuclear Experimental Reactor (ITER) is a new tokamak design project with joint participation from Japan, the European Community, the Soviet Union, and the United States. ITER will be a large machine requiring up to 100 kW of refrigeration at 4.5 K to cool its superconducting magnets. Unlike earlier fusion experiments, the ITER cryogenic system must handle pulse loads constituting a large percentage of the total load. These come from neutron heating during a fusion burn and from ac losses during ramping of current in the PF (poloidal field) coils. This paper presents a conceptual design for a cryogenic system that meets ITER requirements. It describes a system with the following features: Only time-proven components are used. The system obtains a high efficiency without use of cold pumps or other developmental components. High reliability is achieved by paralleling compressors and expanders and by using adequate isolation valving. The problem of load fluctuations is solved by a simple load-leveling device. The cryogenic system can be housed in a separate building located at a considerable distance from the ITER core, if desired. The paper also summarizes physical plant size, cost estimates, and means of handling vented helium during magnet quench. 4 refs., 4 figs., 3 tabs

  5. Plasma-materials interaction issues for the International Thermonuclear Experimental Reactor (ITER)

    International Nuclear Information System (INIS)

    Cohen, S.A.; Werley, K.A.

    1992-02-01

    Analysis of proposed operating scenarios for the International Thermonuclear Experimental Reactor has yielded predictions for the power and particle fluxes onto the material surfaces facing the plasma. The particles, mostly deuterium, tritium, and helium ions, would have energies in the range of 50--2000 eV and fluxes up to 5 x 10 23 /m 2 s. Lower fluxes of multi-MeV electrons and alpha particles may also strike the plasma-facing surfaces, primarily during transient events. The peak power fluxes onto the plasma-facing surfaces during normal operation are expected to be 5--100 MW/m 2 , but much higher during transient events. At the extreme conditions expected for steady-state operation, commonly used heat-removal structures are unable to withstand either the high sputter erosion rates or power loads. To reduce the time-averaged power flux, active control of the plasma position is specified to sweep the plasma heat load across larger areas of plasma-facing components. However, the cyclic heat load creates fatigue lifetime problems. Solutions to these lifetime and reliability problems by (1) changes in machine design and operation, (2) redeposition mechanisms, and (3) changes in materials, will be discussed. A proposed accelerated-life test facility for prototype divertor plate development is described

  6. Radiological dose rate calculations for the International Thermonuclear Experimental Reactor (ITER)

    International Nuclear Information System (INIS)

    Khater, H.Y.; Santoro, R.T.

    1996-01-01

    Two-dimensional biological dose rates were calculated at different locations outside the International Thermonuclear Experimental Reactor (ITER) design. An 18 degree sector of the reactor was modeled in r-θ geometry. The calculations were performed for three different pulsing scenarios. This included a single pulse of 1000 s duration, 10 pulses of 1000 s duration with a 50% duty factor, and 9470 pulses of 1000 s duration with a 50% duty factor for a total fluence of 0.3 MW.a/m 2 . The dose rates were calculated as a function of toroidal angle at locations in the space between the toroidal field (TF) coils and cryostat, and in the space between the cryostat and the biological shield. The two-dimensional results clearly showed the toroidal effect, which is dominated by contribution from the activation of the cryostat and the biological shield. After one pulse, full access to the machine is possible within a few hours following shutdown. After 10 pulses, full access is also possible within the first day following shutdown. At the end of the Basic Performance Phase (BPP), full access is possible at any of the locations considered after one week following shutdown. 5 refs., 5 figs., 2 tabs

  7. Thermonuclear process and accretion onto neutron star envelopes: x-ray burst and transient sources

    International Nuclear Information System (INIS)

    Starrfield, S.; Kenyon, S.; Sparks, W.M.; Truran, J.W.; Theoretical Division, Los Alamos National Laboratory)

    1982-01-01

    We have used a Lagrangian, fully implicit, one-dimensional, hydrodynamic computer code to investigate the evolution of thermonuclear runaways in the thick, accreted, hydrogen-rich envelopes of 1.0 M/sub sun/ neutron stars with radii of 10 km and 20 km. Our simulations produce outbursts which range in time scale from about 2000 seconds to longer than 1 day. Peak effective temperature was 3.3 x 10 7 K (kTapprox.2.91 keV), and peak luminosity was 2 x 10 5 L/sub sun/ for the 10 km study. The 20 km neutron star produced a peak effective temperature and luminosity of 5.3 x 10 6 K and 5.9 x 10 2 L/sub sun/, respectively. We also investigated the effects of changes in the rates of the 14 O(α,p) and 15 O(α,ν) reactions on the evolution. Hydrodynamic expansion on the 10 km neutron star produced a precursor lasting about 10 - 6 seconds

  8. Economic impacts on the United States of siting decisions for the international thermonuclear experimental reactor

    Energy Technology Data Exchange (ETDEWEB)

    Peerenboom, J.P.; Hanson, M.E.; Huddleston, J.R. [and others

    1996-08-01

    This report presents the results of a study that examines and compares the probable short-term economic impacts of the International Thermonuclear Experimental Reactor (ITER) on the United States (U.S.) if (1) ITER were to be sited in the U.S., or (2) ITER were to be sited in one of the other countries that, along with the U.S., is currently participating in the ITER program. Life-cycle costs associated with ITER construction, operation, and decommissioning are analyzed to assess their economic impact. A number of possible U.S. host and U.S. non-host technology and cost-sharing arrangements with the other ITER Parties are examined, although cost-sharing arrangements and the process by which the Parties will select a host country and an ITER site remain open issues. Both national and local/regional economic impacts, as measured by gross domestic product, regional output, employment, net exports, and income, are considered. These impacts represent a portion of the complex, interrelated set of economic considerations that characterize U.S. host and U.S. non-host participation in ITER. A number of other potentially important economic and noneconomic considerations are discussed qualitatively.

  9. Design considerations for ITER [International Thermonuclear Experimental Reactor] toroidal field coils

    International Nuclear Information System (INIS)

    Kalsi, S.S.; Lousteau, D.C.; Miller, J.R.

    1987-01-01

    The International Thermonuclear Experimental Reactor (ITER) is a new tokamak design project with joint participation from Europe, Japan, the Union of Soviet Socialist Republics (USSR), and the United States. This paper describes a magnetic and mechanical design methodology for toroidal field (TF) coils that employs Nb/sub 3/Sn superconductor technology. Coil winding is sized by using conductor concepts developed for the US TIBER concept. The nuclear heating generated during operation is removed from the windings by helium flowing through the conductor. The heat in the coil case is removed through a separate cooling circuit operating at approximately 20 K. Manifold concepts are presented for the complete coil cooling system. Also included are concepts for the coil structural arrangement. The effects of in-plane and out-of-plane loads are included in the design considerations for the windings and case. Concepts are presented for reacting these loads with a minimum amount of additional structural material. Concepts discussed in this paper could be considered for the ITER TF coils. 6 refs., 5 figs., 1 tab

  10. Manufacturing device for vacuum vessel of thermonuclear reactor and manufacturing method therefor

    International Nuclear Information System (INIS)

    Yanagi, Hiroshi; Shibui, Masanao; Uchida, Takaho

    1998-01-01

    The present invention provides a method of manufacturing a vacuum vessel of a thermonuclear reactor with no welding deformation. Namely, there are disposed a manufacturing device comprises a welding machine equipped with a plurality of welding torches which can conduct synchronizing welding and a torch positioning mechanism for positioning the plurality of welding torches each at an optional distance. Then, both ends of a splice plate can be welded by the plurality of welding torches under synchronization. Accordingly, joining portions of sectors of a vacuum vessel can be welded in the site with no deviation of beveling at joining portions between an outer wall and an inner wall with the splice plate due to welding deformation. In addition, the welding machine is mounted on a travelling type clamping mechanism stand or a travelling type clamping mechanism. With such a constitution, since the peripheries of the joining portions on the inner wall are clamped with each other by the travelling type clamping mechanism, no angular distortion is caused in any welded portion of the outer wall. (I.S.)

  11. Analysis and evaluation of the hydrogen risk in a thermonuclear fusion reactor

    International Nuclear Information System (INIS)

    Chaudron, V.; Arnould, F.; Latge, C.; Laurent, A.

    2001-01-01

    After a recall of the principle of controlled thermonuclear fusion, the ITER reactor project is briefly described. The integrity of the reactor must be preserved in the case of a potential explosion of the hydrogen generated inside the reactor, in order to avoid any dispersion radioactive, chemical or toxic materials in the environment. The fundamental principles of safety developed to fulfill these objectives, in particular the defense-in-depth concept, are presented. The main potential source of hydrogen production is the oxidation of beryllium, which is used as protection material in the first wall of the torus, and the accidental presence of water, as reported in several scenarios. The confinement strategy is then described with the qualification of the role of the different barriers. Finally, the hydrogen explosion risk is analyzed and evaluated with respect to the sources, to the reference envelope scenarios and to the location of hydrogen inside the ITER reactor. It appears, at the engineering stage, that the vacuum toric vessel, the discharge reservoir and the exchanger compartments are the most worrying parts. (J.S.)

  12. Investigations in the area of thermonuclear structural material science in the Republic of Kazakhstan

    International Nuclear Information System (INIS)

    Tazhibayeva, I.; Shestakov, V.; Cherepnin, Yu.S.

    2001-01-01

    The investigations in the area of structural materials for fusion program initiated within the framework of ITER project in the Republic of Kazakhstan are devoted basically in the following direction: to studying the behaviour of hydrogen isotopes in structural elements of the first wall and the divertor in conditions simulating real conditions of material operation, accident situations arising during steam interaction with the beryllium armour of the first wall during accidental coolant loss, to establish an experimental facility for study aspects of tritium safety of thermonuclear installations, for example, levels of tritium accumulation and release; efficiency of barrier layers and protective coating; influence of brazing and welding zones on tritium permeation. The work on determination of tritium release from lead/lithium eutectic alloy by mass-spectrometry method and the development of permeation barriers has begun. At present, work has begun to create Kazakhstan's own tokamak type reactor for investigation of the behaviour of various first wall materials and divertor plates during normal and accident conditions. The concept of spherical tokamak will be used in the construction of KTM reactor. (author)

  13. STEEP4 code for computation of specific thermonuclear reaction rates from pointwise cross sections

    International Nuclear Information System (INIS)

    Harris, D.R.; Dei, D.E.; Husseiny, A.A.; Sabri, Z.A.; Hale, G.M.

    1976-05-01

    A code module, STEEP4, is developed to calculate the fusion reaction rates in terms of the specific reactivity [sigma v] which is the product of cross section and relative velocity averaged over the actual ion distributions of the interacting particles in the plasma. The module is structured in a way suitable for incorporation in thermonuclear burn codes to provide rapid and yet relatively accurate on-line computation of [sigma v] as a function of plasma parameters. Ion distributions are modified to include slowing-down contributions which are characterized in terms of plasma parameters. Rapid and accurate algorithms are used for integrating [sigma v] from cross sections and spectra. The main program solves for [sigma v] by the method of steepest descent. However, options are provided to use Gauss-Hermite and dense trapezoidal quadrature integration techniques. Options are also provided for rapid calculation of screening effects on specific reaction rates. Although such effects are not significant in cases of plasmas of laboratory interest, the options are included to increase the range of applicability of the code. Gamow penetration form, log-log interpolation, and cubic interpolation routines are included to provide the interpolated values of cross sections

  14. First wall and divertor plate disposed facing to plasma of thermonuclear device

    International Nuclear Information System (INIS)

    Araki, Masanori; Suzuki, Satoshi; Akiba, Masato; Hayata, Yoshiho; Inoue, Taiji; Hayashi, Yukihiro; Kude, Yukinori

    1998-01-01

    In order to make the most of characteristics of each ingredient of carbon fiber-reinforced composite materials, carbon fiber unidirectionally reinforced materials and a carbon fiber three-directionally reinforced material are laminated in the direction of the thickness to form a carbon fiber-reinforced carbon composite material. In this case, the carbon fibers are continuously oriented in the direction of the thickness to constitute the carbon fiber reinforced carbon composite materials integrally. In addition, a carbon fiber-reinforced carbon composite material prepared by bonding a metal on one surface in adjacent with the unidirectional carbon fiber reinforced portion and substantially in perpendicular to the direction of the thickness of the unidirectional carbon fiber reinforced portion is used as a main constitutional material. Further, a metal tube is buried in the carbon fiber three-directionally reinforced carbon composite material. Then, a first wall and a divertor plate excellent in thermal impact resistance to be disposed facing to plasmas of a thermonuclear device can be provided. (N.H.)

  15. Association of 5-HT2C (rs3813929) and UCP3 (rs1800849) gene polymorphisms with type 2 diabetes in obese women candidates for bariatric surgery.

    Science.gov (United States)

    Schnor, Noa Pereira Prada; Verlengia, Rozangela; Novais, Patrícia Fátima Sousa; Crisp, Alex Harley; Leite, Celso Vieira de Souza; Rasera-Junior, Irineu; Oliveira, Maria Rita Marques de

    2017-01-01

    Obesity can cause systemic arterial hypertension (SAH) and type 2 diabetes mellitus (DM2) factor that is also influenced by genetic variability. The present study aims to investigate the association between gene polymorphisms related with obesity on the prevalence of SAH and DM2 in the preoperative period and 1 year after Roux-en-Y gastric bypass surgery. In total, 351 obese women in a Brazilian cohort completed the study. The clinical diagnosis of SAH and DM2 was monitored from medical records. Twelve gene polymorphisms (rs26802; rs572169; rs7799039; rs1137101; rs3813929; rs659366; rs660339; rs1800849; rs7498665; rs35874116; rs9701796; and rs9939609) were determined using real-time polymerase chain reaction and TaqMan assay. In the preoperative period, prevalence of SAH and DM2 was 57% and 22%, respectively. One year postoperatively, 86.8% subjects had remission of DM2 and 99.5% had control of SAH. Subjects with T allele from the serotonin receptor gene (5-HT2C, rs3813929) had five times greater chance of DM2, and the CC genotype from uncoupling protein 3 gene (UCP3, rs1800849) had three times greater chance in the preoperative period. These findings indicate that polymorphisms rs3813929 and rs1800849 from 5-HT2C and UCP3 genes were related to DM2 prevalence among the Brazilian obese women candidates for bariatric surgery.

  16. Nova outburst modeling and its application to the recurrent nova phenomenon

    International Nuclear Information System (INIS)

    Sparks, W.M.; Starrfield, S.; Truran, J.

    1985-12-01

    The thermonuclear runaway (TNR) theory for the cause of the common novae is reviewed. Numerical simulations of this theory were performed using an implicit hydrodynamic Lagrangian computer code. Relevant physical phenomena are explained with the simpler envelope-in-place calculations. Next the models that include accretion are discussed. The calculations agree very well with observations of common novae. The observational differences between common novae and recurrent novae are examined. We propose input parameters to the TNR model which can give the outburst characteristics of RS Ophiuchi and discuss the implications. This review is concluded with a brief discussion of two current topics in novae research: shear mixing on the white dwarf and Neon novae. 36 refs., 4 figs

  17. Association analysis of APOA5 rs662799 and rs3135506 polymorphisms with obesity in Moroccan patients.

    Science.gov (United States)

    Lakbakbi El Yaagoubi, F; Charoute, H; Bakhchane, A; Ajjemami, M; Benrahma, H; Errouagui, A; Kandil, M; Rouba, H; Barakat, A

    2015-12-01

    The aim of the present study is to explore the association between the APOA5 polymorphisms and haplotypes with obesity in Moroccan patients. The study was performed in 459 subjects, Obese (n=164) and non-obese (n=295). All subjects were genotyped for the APOA5 -1131T>C (rs662799) and c.56C>G (rs3135506) polymorphisms. The contribution of APOA5 polymorphisms and haplotypes in the increased risk of obesity were explored using logistic regression analyses. The -1131T>C and c.56C>G polymorphisms were significantly associated with obesity. Both polymorphisms were strongly associated with increased BMI. Analysis of constructed haplotypes showed a significant association between CG haplotype and susceptibility to obesity (OR [95%CI]=3.09 [1.93-4.97]; P<0.001). These results support a potential role for APOA5 common variants and related haplotypes as risk factors for obesity. Copyright © 2015 Elsevier Masson SAS. All rights reserved.

  18. Correlation of Fetuin-A gene rs1071592 and rs2593813 single nucleotide polymorphisms with polycystic ovary syndrome

    Directory of Open Access Journals (Sweden)

    Juan YI

    2016-10-01

    Full Text Available Objective  To investigate the relations of Fetuin-A gene rs1071592 and rs2593813 single nucleotide polymorphisms (SNPs with the affect ability to polycystic ovary syndrome (PCOS and its endocrine and metabolic characteristics in Chongqing Han population. Methods  A case-control study was performed in Chinese Han subjects. The clinical data of 156 cases of normal control and 147 cases of PCOS patients were collected, and their blood glucose, lipids, sex hormone and other biochemical indexes were determined, the SNPs of rs1071592 and rs2593813 were genotyped by TaqMan SNP Genotyping Assay. Hyperinsulinemic-euglycemic clamp was performed in 147 PCOS women and 20 controls. The relative risk of developing PCOS in women with rs1071592 genotype was assessed using a binary logistic regression analysis. Results  The distribution frequency of Fetuin-A gene homozygous rs1071592 AA genotype and A allele was significantly increased in PCOS patients than in controls (Pc0.05. Binary logistic regression analysis showed that the risk of developing PCOS was 4.93 times high in women with AA genotype of rs1071592 (OR=4.933, 95%CI 1.593-15.278, P0.05. Conclusion  People with SNPs variants of rs1071592 in Fetuin-A gene may have an increased genetic susceptibility to PCOS. However, there won't be significant relationship between SNP of rs2593813 at Fetuin-A gene and PCOS. DOI: 10.11855/j.issn.0577-7402.2016.09.07

  19. Evaluation of innovative means of hydrogen risk mitigation in thermonuclear fusion reactors

    International Nuclear Information System (INIS)

    Maruejouls, C.

    2003-01-01

    One of the main accidents in ITER-type thermonuclear fusion reactors is the loss of coolant leading to hydrogen production. Within the framework of the studies on the ITER fusion reactor, a mitigation strategy for this risk must be devised by focusing on a system, which can be placed near the hydrogen source. The uncertainty as to the air content during such a scenario forbids the use of classic methods based on the hydrogen/oxygen reaction such as passive catalytic recombiners. Former studies have proposed a process based on the reduction of metallic oxides and more particularly that of the manganese dioxide enhanced by silver oxide mixture. The reaction studied is H 2 + MnO 2 → MnO + H 2 O (reaction enhanced by Ag 2 O). The purpose is to study the kinetic. The method used consists in comparing the experimental results obtained on the pilot facility CIGNE with those provided by a model. The experimental results were obtained from tests made on a pilot facility with a solid/gas reaction in a fixed bed. These underlined the importance of favoring the solid/gas contact surface. The modeling used in the MITRHY simulation program, coupled to an optimizer helped determine the kinetic parameters and the data on the material and temperature transfers. The kinetic is of first order rate for hydrogen with an activation energy of 29428 J/mol and a kinetic coefficient of 142 m.s -1 . Integrated in the MITRHY program, the kinetic parameters were used to simulate the hydrogen elimination in the accident conditions on the ITER experimental reactor. This study achieved a pre-design basis of the device (bed of about 30 cm with grains of a diameter of less than 5 mm) to be implemented. It also underlined the need to favor the specific surface to improved process efficiency. (author)

  20. Approaches to safety, environment and regulatory approval for the International Thermonuclear Experimental Reactor

    International Nuclear Information System (INIS)

    Saji, G.; Bartels, H.W.; Chuyanov, V.; Holland, D.; Kashirski, A.V.; Morozov, S.I.; Piet, S.J.; Poucet, A.; Raeder, J.; Rebut, P.H.; Topilski, L.N.

    1995-01-01

    International Thermonuclear Experimental Reactor (ITER) Engineering Design Activities (EDA) in safety and environment are approaching the point where conceptual safety design, topic studies and research will give way to project oriented engineering design activities. The Joint Central Team (JCT) is promoting safety design and analysis necessary for siting and regulatory approval. Scoping studies are underway at the general level, in terms of laying out the safety and environmental design framework for ITER. ITER must follow the nuclear regulations of the host country as the future construction site of ITER. That is, regulatory approval is required before construction of ITER. Thus, during the EDA, some preparations are necessary for the future application for regulatory approval. Notwithstanding the future host country's jurisdictional framework of nuclear regulations, the primary responsibility for safety and reliability of ITER rests with the legally responsible body which will operate ITER. Since scientific utilization of ITER and protection of the large investment depends on safe and reliable operation of ITER, we are highly motivated to achieve maximum levels of operability, maintainability, and safety. ITER will be the first fusion facility in which overall 'nuclear safety' provisions need to be integrated into the facility. For example, it will be the first fusion facility with significant decay heat and structural radiational damage. Since ITER is an experimental facility, it is also important that necessary experiments can be performed within some safety design limits without requiring extensive regulatory procedures. ITER will be designed with such a robust safety envelope compatible with the fusion power and the energy inventories. The basic approach to safety will be realized by 'defense-in-depth'. (orig.)

  1. Charged-particle thermonuclear reaction rates: I. Monte Carlo method and statistical distributions

    International Nuclear Information System (INIS)

    Longland, R.; Iliadis, C.; Champagne, A.E.; Newton, J.R.; Ugalde, C.; Coc, A.; Fitzgerald, R.

    2010-01-01

    A method based on Monte Carlo techniques is presented for evaluating thermonuclear reaction rates. We begin by reviewing commonly applied procedures and point out that reaction rates that have been reported up to now in the literature have no rigorous statistical meaning. Subsequently, we associate each nuclear physics quantity entering in the calculation of reaction rates with a specific probability density function, including Gaussian, lognormal and chi-squared distributions. Based on these probability density functions the total reaction rate is randomly sampled many times until the required statistical precision is achieved. This procedure results in a median (Monte Carlo) rate which agrees under certain conditions with the commonly reported recommended 'classical' rate. In addition, we present at each temperature a low rate and a high rate, corresponding to the 0.16 and 0.84 quantiles of the cumulative reaction rate distribution. These quantities are in general different from the statistically meaningless 'minimum' (or 'lower limit') and 'maximum' (or 'upper limit') reaction rates which are commonly reported. Furthermore, we approximate the output reaction rate probability density function by a lognormal distribution and present, at each temperature, the lognormal parameters μ and σ. The values of these quantities will be crucial for future Monte Carlo nucleosynthesis studies. Our new reaction rates, appropriate for bare nuclei in the laboratory, are tabulated in the second paper of this issue (Paper II). The nuclear physics input used to derive our reaction rates is presented in the third paper of this issue (Paper III). In the fourth paper of this issue (Paper IV) we compare our new reaction rates to previous results.

  2. Thermonuclear reaction rate of 17O(p,γ)18F

    International Nuclear Information System (INIS)

    Fox, C.; Iliadis, C.; Champagne, A.E.; Fitzgerald, R.P.; Longland, R.; Newton, J.; Pollanen, J.; Runkle, R.

    2005-01-01

    The 17 O(p,γ) 18 F and 17 O(p,α) 14 N reactions have a profound influence on hydrogen-burning nucleosynthesis in a number of stellar sites, including red giants, asymptotic giant branch (AGB) stars, massive stars, and classical novae. Previously evaluated thermonuclear rates for both reactions carry large uncertainties. We investigated the proton-capture reaction on 17 O in the bombarding energy range of E p lab = 180-540 keV. We observed a previously undiscovered resonance at E R lab = 193.2 ± 0.9 keV. The resonance strength amounts to (ωγ) pγ (1.2±0.2)x10 -6 eV. With this value, the uncertainties of the 17 O(p,γ) 18 F reaction rates are reduced by orders of magnitude in the peak temperature range of classical novae (T=0.1-0.4 GK). We also report on a reevaluation of the 17 O(p,γ) 18 F reaction rates at lower temperatures that are pertinent to red giants, AGB stars, or massive stars. The present work establishes the 17 O(p,γ) 18 F reaction rates over a temperature range of T= 0.01-1.5 GK with statistical uncertainties of 10-50%. The new recommended reaction rates deviate from the previously accepted values by an order of magnitude around T≅0.2 GK and by factors of 2-3 at T < 0.1 GK

  3. Thermonuclear 19F(p, {{\\boldsymbol{\\alpha }}}_{0})16O reaction rate

    Science.gov (United States)

    He, Jian-Jun; Lombardo, Ivano; Dell'Aquila, Daniele; Xu, Yi; Zhang, Li-Yong; Liu, Wei-Ping

    2018-01-01

    The thermonuclear 19F(p, {{{α }}}0)16O reaction rate in the temperature region 0.007-10 GK has been derived by re-evaluating the available experimental data, together with the low-energy theoretical R-matrix extrapolations. Our new rate deviates by up to about 30% compared to the previous results, although all rates are consistent within the uncertainties. At very low temperature (e.g. 0.01 GK) our reaction rate is about 20% lower than the most recently published rate, because of a difference in the low energy extrapolated S-factor and a more accurate estimate of the reduced mass used in the calculation of the reaction rate. At temperatures above ˜1 GK, our rate is lower, for instance, by about 20% around 1.75 GK, because we have re-evaluated the previous data (Isoya et al., Nucl. Phys. 7, 116 (1958)) in a meticulous way. The present interpretation is supported by the direct experimental data. The uncertainties of the present evaluated rate are estimated to be about 20% in the temperature region below 0.2 GK, and are mainly caused by the lack of low-energy experimental data and the large uncertainties in the existing data. Asymptotic giant branch (AGB) stars evolve at temperatures below 0.2 GK, where the 19F(p, {{α }})16O reaction may play a very important role. However, the current accuracy of the reaction rate is insufficient to help to describe, in a careful way, the fluorine over-abundances observed in AGB stars. Precise cross section (or S factor) data in the low energy region are therefore needed for astrophysical nucleosynthesis studies. Supported by National Natural Science Foundation of China (11490562, 11490560, 11675229) and National Key Research and Development Program of China (2016YFA0400503)

  4. Modeling and control simulation of an electromechanical mm-wave launching system for thermonuclear fusion applications

    Energy Technology Data Exchange (ETDEWEB)

    Tsironis, Christos, E-mail: ctsiron@mail.ntua.gr [School of Electrical and Computer Engineering, National Technical University of Athens, 157 73 Athens (Greece); Department of Physics, Aristotle University of Thessaloniki, 54 136 Thessaloniki (Greece); Giannopoulos, Iordanis K.; Vasileiadou, Soultana; Kakogiannos, Ioannis D.; Kalligeropoulos, Dimitrios [Department of Automation, Technological Education Institute of Piraeus, 122 44 Piraeus (Greece)

    2016-11-15

    Highlights: • Open-loop modeling and control simulation of an electromechanical mm-wave launcher. • Simulations of the experiment without employing the real (hardware) system. • Launcher mirror dynamics correspond to a second-order weakly-nonlinear system. • Closed-loop control design in terms of cascade PIDs achieves required performance. - Abstract: Controlled thermonuclear fusion via magnetic confinement, still in experimental stage, has the potential to become a viable and environment-friendly solution to the energy problem, especially for the high-power needs of modern industry. In order to optimize the operation of devices based on the tokamak principle, automatic control systems are envisaged to fulfill the requirements for the magnetic equilibrium and plasma stability, with copper coils, neutral gas injectors and microwave sources used as actuators. In present-day experiments, the implemented control loops are simple and practical, however in future devices like ITER (presently under construction) more sophisticated control design will be required, based on realistic closed-loop simulations with efficient computational tools and real-time diagnosing. For magnetohydrodynamic instability control, the system should include physics/engineering models for the plasma dynamics, the wave actuation and the diagnostic sensors, as well as controllers based on classical or modern principles. In this work, we present a model for a specific design of a controlled electromechanical millimeter-wave launcher, which executes the major part of the wave actuation, and perform numerical simulations of its open-loop dynamics and closed-loop control for scenarios relevant to tearing mode stabilization in medium-sized tokamaks.

  5. High-power explosive magnetic energy sources for thermonuclear and physical applications (overview)

    Energy Technology Data Exchange (ETDEWEB)

    Chernyshev, V K [All-Russian Scientific Institute of Experimental Physics, Sarov (Russian Federation)

    1997-12-31

    High-power energy sources unavailable up to now are needed to carry out any one project on inertially confined controlled thermonuclear fusion (CTF). Considerable advances have been made in the area of explosive magnetic generators (EGG) as for their output characteristics (high power combined with high energy content). To develop the concept of magnetic cumulation proposed by A.D. Sakharov in 1951, two new approaches to increasing EMC fast operation by two orders (from tens of microseconds to tenths of microseconds) and increasing at the same time the current pulse amplitude by more than one order, were proposed at VNIIEF in the early sixties. The concept aimed at solving the CTF problem by target magnetic compression (MACO) under the effect of an fast-increasing field was proposed (1972) based on VNIIEF achievements, discussed (1976) at the USSR Academy of Sciences and published (1979). The key physical questions are analyzed, the problems to be solved are posed and the results achieved in the experiments with fast-operating high-power EMGs, fast-opening switches, transmitting lines and insulation systems are discussed here. The results obtained in experiments on liner acceleration as well as those on preliminary plasma magnetization and heating, carried out at the constructed EMGs, are discussed briefly. The conclusion is reached that the MACO system is the most suitable one to provide the ignition because the designing of high-power energy sources to be used in this system is practically complete and the concept itself does not need any intermediate transformations of one type of energy into another always accompanied by a decrease in total efficiency. (author). 4 tabs., 14 figs., 21 refs.

  6. Enhanced probabilistic decision analysis for radiological confinement barriers of the International Thermonuclear Experimental Reactor

    International Nuclear Information System (INIS)

    Golinescu, R.P.; Kazimi, M.S.

    1998-01-01

    To ensure a defence-in-depth approach, several radiological confinement barriers surrounding a tokamak plant can be employed. A methodology using probabilistic risk assessment (PRA) techniques is a useful tool for evaluating the performance of each confinement barrier within the context of a limited allowable risk of accidental radioactivity releases. Such a methodology was developed and applied to the confinement strategy for the International Thermonuclear Experimental Reactor (ITER). Accident sequence models were constructed for each of the confinement barriers to evaluate the probabilities of events leading to radioactive releases from the corresponding confinement barrier. The current ITER design requirements set radioactive release and dose limits for individual event sequences grouped in categories by frequency. To limit the plant's overall risk and account for event uncertainties in both frequency and consequence, an analytical form for a limit line is derived here as a complementary cumulative frequency (CCF) of radioactive releases to the environment. By comparing the releases from each confinement barrier against the limit line, a decision can be made about the number of barriers required to comply with the design requirements. The first barrier is the vacuum vessel (VV) and the primary heat transfer systems. The second confinement barrier consists of the cryostat vessel (CV) and the heat transfer system vaults. In case the outer building is needed to act as a third barrier for ITER, a decision model using the multi-attribute utility theory was constructed to help the designer choose the best type of tokamak building. The decision model allows for performing sensitivity analysis on relevant parameters and for design features of new options for the ITER tokamak building. (orig.)

  7. Design considerations for ITER [International Thermonuclear Experimental Reactor] magnet systems: Revision 1

    International Nuclear Information System (INIS)

    Henning, C.D.; Miller, J.R.

    1988-01-01

    The International Thermonuclear Experimental Reactor (ITER) is now completing a definition phase as a beginning of a three-year design effort. Preliminary parameters for the superconducting magnet system have been established to guide further and more detailed design work. Radiation tolerance of the superconductors and insulators has been of prime importance, since it sets requirements for the neutron-shield dimension and sensitively influences reactor size. The major levels of mechanical stress in the structure appear in the cases of the inboard legs of the toroidal-field (TF) coils. The cases of the poloidal-field (PF) coils must be made thin or segmented to minimize eddy current heating during inductive plasma operation. As a result, the winding packs of both the TF and PF coils includes significant fractions of steel. The TF winding pack provides support against in-plane separating loads but offers little support against out-of-plane loads, unless shear-bonding of the conductors can be maintained. The removal of heat due to nuclear and ac loads has not been a fundamental limit to design, but certainly has non-negligible economic consequences. We present here preliminary ITER magnet systems design parameters taken from trade studies, designs, and analyses performed by the Home Teams of the four ITER participants, by the ITER Magnet Design Unit in Garching, and by other participants at workshops organized by the Magnet Design Unit. The work presented here reflects the efforts of many, but the responsibility for the opinions expressed is the authors'. 4 refs., 3 figs., 4 tabs

  8. Review of studies for thermonuclear ignition with 1.8 MJ laser (LMJ): theory and experiment

    International Nuclear Information System (INIS)

    Holstein, P.A.; Bastian, J.; Bowen, C.; Casanova, M.; Chaland, F.; Cherfils, C.; Dattolo, E.; Galmiche, D.; Gauthier, P.; Giorla, J.; Laffite, S.; Liberatore, S.; Loiseau, P.; Larroche, O.; Lours, L.; Malinie, G.; Masse, L.; Monteil, M.C.; Morice, O.; Paillard, D.; Poggi, F.; Saillard, Y.; Seytor, P.; Teychenne, D.; Vandenboomgaerde, M.; Wagon, F.; Bonnefille, M.; Hedde, T.; Lefebvre, E.; Riazuelo, G.; Babonneau, D.; Primout, M.; Casner, A.; Depierreux, S.; Girard, F.; Huser, G.; Jadaud, J.P.; Juraszek, D.; Miquel, J.L.; Naudy, M.; Philippe, F.; Rousseaux, C.; Videau, L.

    2008-01-01

    The purpose of the laser Megajoule (LMJ) is the ignition of thermonuclear fusion reactions in a microscopic capsule of cryogenic DT whose implosion is obtained by a laser pulse in the range of 10 -20 ns, delivering a power of 400 - 500 TW. In this report we have tried to gather in one document the main part of the work made from 1995 to 2005 by the teams of Cea/DAM to design the LMJ targets. This report deals with the targets adapted to the laser energy of 1.8 MJ corresponding to 60 laser beams (called quadruplets because of their 4 beamlets), so primarily, with the target called A1040. The targets studied more recently adapted to lower laser energy are too new to appear in it. It concerns all the topics of the physics of target LMJ: laser-plasma interaction, radiative budget of the hohlraum, implosion interaction, hydrodynamic instabilities and robustness of the target to the technological uncertainties. The approach made for the robustness study is original and makes it possible to specify the features of the laser and the targets. This review scans all the aspects of the target design done with numerical simulations of bi-dimensional radiative hydrodynamics but it points out also the main results of the experiments made with the lasers Phebus, Nova and Omega for 20 years. This review also addresses to scientist not specialists in the problems of inertial confinement fusion. It is organized by topics of physics and the experiments appear at the end of each chapter. It does not concern the aspects of target fabrication nor the problems of diagnostic. (authors)

  9. Uncertainties in the production of p nuclides in thermonuclear supernovae determined by Monte Carlo variations

    Science.gov (United States)

    Nishimura, N.; Rauscher, T.; Hirschi, R.; Murphy, A. St J.; Cescutti, G.; Travaglio, C.

    2018-03-01

    Thermonuclear supernovae originating from the explosion of a white dwarf accreting mass from a companion star have been suggested as a site for the production of p nuclides. Such nuclei are produced during the explosion, in layers enriched with seed nuclei coming from prior strong s processing. These seeds are transformed into proton-richer isotopes mainly by photodisintegration reactions. Several thousand trajectories from a 2D explosion model were used in a Monte Carlo approach. Temperature-dependent uncertainties were assigned individually to thousands of rates varied simultaneously in post-processing in an extended nuclear reaction network. The uncertainties in the final nuclear abundances originating from uncertainties in the astrophysical reaction rates were determined. In addition to the 35 classical p nuclides, abundance uncertainties were also determined for the radioactive nuclides 92Nb, 97, 98Tc, 146Sm, and for the abundance ratios Y(92Mo)/Y(94Mo), Y(92Nb)/Y(92Mo), Y(97Tc)/Y(98Ru), Y(98Tc)/Y(98Ru), and Y(146Sm)/Y(144Sm), important for Galactic Chemical Evolution studies. Uncertainties found were generally lower than a factor of 2, although most nucleosynthesis flows mainly involve predicted rates with larger uncertainties. The main contribution to the total uncertainties comes from a group of trajectories with high peak density originating from the interior of the exploding white dwarf. The distinction between low-density and high-density trajectories allows more general conclusions to be drawn, also applicable to other simulations of white dwarf explosions.

  10. Insect nicotinic acetylcholine receptors (nAChRs): Important amino ...

    African Journals Online (AJOL)

    STORAGESEVER

    2008-12-29

    Dec 29, 2008 ... nAChRs within the insect central nervous system has led to the development of insecticides targeting .... binding protein (AChBP), a homopentameric structural and functional homolog of ..... of the honey bee, Apis mellifera.

  11. Assessment of river plan changes in Terengganu River using RS ...

    African Journals Online (AJOL)

    Journal of Fundamental and Applied Sciences ... The database can help in the appropriate understanding of river plan change and know ... The data collected from Geographic Information System (GIS) and Remote Sensing (RS) database.

  12. SparkRS - Spark for Remote Sensing, Phase I

    Data.gov (United States)

    National Aeronautics and Space Administration — The proposed innovation is Spark-RS, an open source software project that enables GPU-accelerated remote sensing workflows in an Apache Spark distributed computing...

  13. RS-485 Bus Design of a Missile Simulation Training System

    Directory of Open Access Journals (Sweden)

    Liu Fang

    2013-07-01

    Full Text Available In a missile simulation training system with one-master and multi-slaves distributed system structure, a universal controller is necessary due to the system composed with several controllers. In this research, the designed controllers communicate with each other and upper control computer through RS-485 field bus. RS-485 bus including interface circuits, transmission protocol, Cyclic Redundancy Check (CRC method and upper control test software is designed and proposed. The universal controller adopting the designed RS-485 interface circuits is connected through twisted-pair and makes the simulation system, then the controller is tested in line. The results show that the RS-485 bus communicates effectively using the protocol and CRC method, data transmission rates reaches 115.2 kbps, and has a good stability.

  14. Four therapeutic cases of RS3PE syndrome

    International Nuclear Information System (INIS)

    Nakajima, Naoya; Fukuda, Yukiko; Yang, Kwang-Seok; Aiba, Miyoji; Tsuda, Hiroshi

    2007-01-01

    RS3PE syndrome (Remitting Seronegative Symmetrical Synovitis with Pitting Edema Syndrome) is one of the disorders which present as polyarthritis. It is important to be aware of RS3PE syndrome when encountering elderly patients with polyarthritis who are negative for rheumatoid factor. We report 4 cases of RS3PE syndrome. All cases shared common clinical findings, such as acute onset, symmetrical polyarthritis, pitting edema of the hands and feet, and being negative for rheumatoid factor in serum. Treatment with corticosteroid was very effective in all cases. However, two patients showed a deteriorated clinical condition during the tapering of corticosteroid. Corticosteroid should be tapered off cautiously in patients with RS3PE syndrome. (author)

  15. Blending the most fundamental Remote-Sensing principles (RS ...

    African Journals Online (AJOL)

    Blending the most fundamental Remote-Sensing principles (RS) with the most functional spatial knowledge (GIS) with the objective of the determination of the accident-prone palms and points (case study: Tehran-Hamadan Highway on Saveh Superhighway)

  16. Parallel data grabbing card based on PCI bus RS422

    International Nuclear Information System (INIS)

    Zhang Zhenghui; Shen Ji; Wei Dongshan; Chen Ziyu

    2005-01-01

    This article briefly introduces the developments of the parallel data grabbing card based on RS422 and PCI bus. It could be applied for grabbing the 14 bits parallel data in high speed, coming from the devices with RS422 interface. The methods of data acquisition which bases on the PCI protocol, the functions and their usages of the chips employed, the ideas and principles of the hardware and software designing are presented. (authors)

  17. The 3Rs principle – mind the ethical gap!

    DEFF Research Database (Denmark)

    Olsson, I. Anna S.; Franco, Nuno H.; Weary, Daniel M.

    2012-01-01

    to believe that full implementation is merely a matter of time, and once the 3Rs are widely implemented, the public will fully support any continued laboratory animal use that is deemed necessary. In this paper, we argue that these conclusions are unlikely to be correct, in part because the 3Rs are rich...... effects of repeated exposure to harmful procedures). We conclude that there is now a need for a more thorough ethical discussion on how to resolve these issues....

  18. Multirate Filter Bank Representations of RS and BCH Codes

    Directory of Open Access Journals (Sweden)

    Van Meerbergen Geert

    2008-01-01

    Full Text Available Abstract This paper addresses the use of multirate filter banks in the context of error-correction coding. An in-depth study of these filter banks is presented, motivated by earlier results and applications based on the filter bank representation of Reed-Solomon (RS codes, such as Soft-In Soft-Out RS-decoding or RS-OFDM. The specific structure of the filter banks (critical subsampling is an important aspect in these applications. The goal of the paper is twofold. First, the filter bank representation of RS codes is now explained based on polynomial descriptions. This approach allows us to gain new insight in the correspondence between RS codes and filter banks. More specifically, it allows us to show that the inherent periodically time-varying character of a critically subsampled filter bank matches remarkably well with the cyclic properties of RS codes. Secondly, an extension of these techniques toward the more general class of BCH codes is presented. It is demonstrated that a BCH code can be decomposed into a sum of critically subsampled filter banks.

  19. Multirate Filter Bank Representations of RS and BCH Codes

    Directory of Open Access Journals (Sweden)

    Marc Moonen

    2009-01-01

    Full Text Available This paper addresses the use of multirate filter banks in the context of error-correction coding. An in-depth study of these filter banks is presented, motivated by earlier results and applications based on the filter bank representation of Reed-Solomon (RS codes, such as Soft-In Soft-Out RS-decoding or RS-OFDM. The specific structure of the filter banks (critical subsampling is an important aspect in these applications. The goal of the paper is twofold. First, the filter bank representation of RS codes is now explained based on polynomial descriptions. This approach allows us to gain new insight in the correspondence between RS codes and filter banks. More specifically, it allows us to show that the inherent periodically time-varying character of a critically subsampled filter bank matches remarkably well with the cyclic properties of RS codes. Secondly, an extension of these techniques toward the more general class of BCH codes is presented. It is demonstrated that a BCH code can be decomposed into a sum of critically subsampled filter banks.

  20. The optimal algorithm for Multi-source RS image fusion.

    Science.gov (United States)

    Fu, Wei; Huang, Shui-Guang; Li, Zeng-Shun; Shen, Hao; Li, Jun-Shuai; Wang, Peng-Yuan

    2016-01-01

    In order to solve the issue which the fusion rules cannot be self-adaptively adjusted by using available fusion methods according to the subsequent processing requirements of Remote Sensing (RS) image, this paper puts forward GSDA (genetic-iterative self-organizing data analysis algorithm) by integrating the merit of genetic arithmetic together with the advantage of iterative self-organizing data analysis algorithm for multi-source RS image fusion. The proposed algorithm considers the wavelet transform of the translation invariance as the model operator, also regards the contrast pyramid conversion as the observed operator. The algorithm then designs the objective function by taking use of the weighted sum of evaluation indices, and optimizes the objective function by employing GSDA so as to get a higher resolution of RS image. As discussed above, the bullet points of the text are summarized as follows.•The contribution proposes the iterative self-organizing data analysis algorithm for multi-source RS image fusion.•This article presents GSDA algorithm for the self-adaptively adjustment of the fusion rules.•This text comes up with the model operator and the observed operator as the fusion scheme of RS image based on GSDA. The proposed algorithm opens up a novel algorithmic pathway for multi-source RS image fusion by means of GSDA.

  1. THE FERMI-GBM X-RAY BURST MONITOR: THERMONUCLEAR BURSTS FROM 4U 0614+09

    International Nuclear Information System (INIS)

    Linares, M.; Chakrabarty, D.; Connaughton, V.; Bhat, P. N.; Briggs, M. S.; Preece, R.; Jenke, P.; Kouveliotou, C.; Wilson-Hodge, C. A.; Van der Horst, A. J.; Camero-Arranz, A.; Finger, M.; Paciesas, W. S.; Beklen, E.; Von Kienlin, A.

    2012-01-01

    Thermonuclear bursts from slowly accreting neutron stars (NSs) have proven difficult to detect, yet they are potential probes of the thermal properties of the NS interior. During the first year of a systematic all-sky search for X-ray bursts using the Gamma-ray Burst Monitor aboard the Fermi Gamma-ray Space Telescope we have detected 15 thermonuclear bursts from the NS low-mass X-ray binary 4U 0614+09 when it was accreting at nearly 1% of the Eddington limit. We measured an average burst recurrence time of 12 ± 3 days (68% confidence interval) between 2010 March and 2011 March, classified all bursts as normal duration bursts and placed a lower limit on the recurrence time of long/intermediate bursts of 62 days (95% confidence level). We discuss how observations of thermonuclear bursts in the hard X-ray band compare to pointed soft X-ray observations and quantify such bandpass effects on measurements of burst radiated energy and duration. We put our results for 4U 0614+09 in the context of other bursters and briefly discuss the constraints on ignition models. Interestingly, we find that the burst energies in 4U 0614+09 are on average between those of normal duration bursts and those measured in long/intermediate bursts. Such a continuous distribution in burst energy provides a new observational link between normal and long/intermediate bursts. We suggest that the apparent bimodal distribution that defined normal and long/intermediate duration bursts during the last decade could be due to an observational bias toward detecting only the longest and most energetic bursts from slowly accreting NSs.

  2. MHD equilibrium methods for ITER [International Thermonuclear Experimental Reactor] PF [poloidal field] coil design and systems analysis

    International Nuclear Information System (INIS)

    Strickler, D.J.; Galambos, J.D.; Peng, Y.K.M.

    1989-03-01

    Two versions of the Fusion Engineering Design Center (FEDC) free-boundary equilibrium code designed to computer the poloidal field (PF) coil current distribution of elongated, magnetically limited tokamak plasmas are demonstrated and applied to the systems analysis of the impact of plasma elongation on the design point of the International Thermonuclear Experimental Reactor (ITER). These notes were presented at the ITER Specialists' Meeting on the PF Coil System and Operational Scenario, held at the Max Planck Institute for Plasma Physics in Garching, Federal Republic of Germany, May 24--27, 1988. 8 refs., 6 figs., 4 tabs

  3. Assessment of the critical neutron number for internal break-even in explosion-induced thermonuclear fusion

    International Nuclear Information System (INIS)

    Kaliski, S.

    1979-01-01

    An analysis is performed of the systems of an explosion-induced thermonuclear microfusion from the angle of attaining an internal break-even. A critical-state meter is defined, i.e. the critical neutron yield Nsub(cr) as the most convenient for characterizing the experimental setups. It is demonstrated that in a number of designed systems of an explosion-induced microfusion, Nsub(cr) is attained. In the experiments actually carried out the N-yield efficiency is of about three orders of magnitude. (author)

  4. Eudragit RS PO nanoparticles for sustained release of pyridostigmine bromide

    International Nuclear Information System (INIS)

    Hoobakht, Fatemeh; Ganji, Fariba; Vasheghani-Farahani, Ebrahim; Mousavi, Seyyed Mohammad

    2013-01-01

    Pyridostigmine bromide (PB) is an inhibitor of cholinesterase, which is used in the treatment of myasthenia gravis and administered for protection against exposure to toxic nerve agents. Tests were done to investigate prolonging the half-life of PB and improving its release behavior. PB was loaded in nanoparticles (NPs) of Eudragit RS PO (Eu-RS) prepared using the technique of quasi emulsion solvent diffusion. Variables of output power of the sonicator, bath temperature and mixing time, were chosen as the optimization factors to obtain the minimum sized NPs. In addition, emulsions were tested at different ratios of drug-to-polymer by dynamic light scattering to determine size and zeta potential of NPs. UV-spectroscopy was used to determine PB content of the NPs. Drug-loaded NPs were characterized by scanning electron microscopy, X-ray diffraction, and Fourier transform infrared spectra. Results determined that mixing time had a significant impact on the size of Eu-RS NPs, but power output of sonicator and bath temperature had no significant effect. The particle size obtained at the optimum condition (power output of 70 W, bath temperature of 33 °C, and mixing time of 7 min) was less than 200 nm (optimum sizes were 138.9 and 179.5 nm for Eu-RS and PB-loaded Eu-RS NPs, respectively). The optimum PB-loaded Eu-RS NPs at the PB to Eu-RS weight ratio of 1–4 and 20 % of loaded PB released from the nanocarriers within 100 h

  5. Eudragit RS PO nanoparticles for sustained release of pyridostigmine bromide

    Energy Technology Data Exchange (ETDEWEB)

    Hoobakht, Fatemeh; Ganji, Fariba, E-mail: fganji@modares.ac.ir; Vasheghani-Farahani, Ebrahim [Tarbiat Modares University, Biomedical Engineering Group, Chemical Engineering Department (Iran, Islamic Republic of); Mousavi, Seyyed Mohammad [Tarbiat Modares University, Biotechnology Group, Chemical Engineering Department (Iran, Islamic Republic of)

    2013-09-15

    Pyridostigmine bromide (PB) is an inhibitor of cholinesterase, which is used in the treatment of myasthenia gravis and administered for protection against exposure to toxic nerve agents. Tests were done to investigate prolonging the half-life of PB and improving its release behavior. PB was loaded in nanoparticles (NPs) of Eudragit RS PO (Eu-RS) prepared using the technique of quasi emulsion solvent diffusion. Variables of output power of the sonicator, bath temperature and mixing time, were chosen as the optimization factors to obtain the minimum sized NPs. In addition, emulsions were tested at different ratios of drug-to-polymer by dynamic light scattering to determine size and zeta potential of NPs. UV-spectroscopy was used to determine PB content of the NPs. Drug-loaded NPs were characterized by scanning electron microscopy, X-ray diffraction, and Fourier transform infrared spectra. Results determined that mixing time had a significant impact on the size of Eu-RS NPs, but power output of sonicator and bath temperature had no significant effect. The particle size obtained at the optimum condition (power output of 70 W, bath temperature of 33 Degree-Sign C, and mixing time of 7 min) was less than 200 nm (optimum sizes were 138.9 and 179.5 nm for Eu-RS and PB-loaded Eu-RS NPs, respectively). The optimum PB-loaded Eu-RS NPs at the PB to Eu-RS weight ratio of 1-4 and 20 % of loaded PB released from the nanocarriers within 100 h.

  6. Elaboration of functionally graded materials for plasma facing components of the thermonuclear machines

    International Nuclear Information System (INIS)

    Autissier, Emmanuel

    2014-01-01

    The objective of this study was to develop a Functionally Graded Material (FGM) W/Cu to replace the compliance layer (Cu-OFHC) in the plasma facing components of thermonuclear fusion reactor like ITER. The peculiarity of this work is to elaborate these materials without exceeding the melting temperature of copper in order to control its microstructure. The co-sintering is the most attractive solution to achieve this goal. The first phase of this study has been to decrease the sintering temperature of the tungsten to achieve this co-sintering. The elaboration of a Functionally Graded Materials being delicate, thermomechanical calculations were performed in order to determine the number and chemical composition in order to increase the lifespan of Plasma Facing Components. Spark Plasma Sintering conditions were optimized in order to achieve maximum density of W x Cu 1-x composites. The effect of copper content and density of the W x Cu 1-x composites on thermal and mechanical properties was investigated. The SPS conditions were applied for W/CuCrZr assemblies with a compliance layer composed of several interlayers. The importance of time for the integrity of assemblies thereof has been highlighted. The study of the dwell time during W/CuCrZr assembly leads to identify a parameter to characterize the integrity of the interface regardless of the composition and the nature of the layer of compliance. Moreover, the phenomena associated with the formation of the interface assembly have been identified. The interface W/W x Cu 1-x is formed by the extrusion of the copper layer of the W x Cu 1-x inside the tungsten porosities. The W y Cu 1-y /CuCrZr interface is formed by copper migration of CuCrZr layer inside the W y Cu 1-y layer. Finally optimization assembly conditions showed that the mechanical stresses due to the densification of the Functionally Graded Materials can be limited by sintering the FGM before the assembly. (author)

  7. Production of synthetic methanol from air and water using controlled thermonuclear reactor power

    International Nuclear Information System (INIS)

    Dang, V.D.; Steinberg, M.

    1977-01-01

    Energy requirement and process development of methanol production from air and water using controlled thermonuclear fusion power was discussed in Part 1 (Steinberg et al., Energy conversion;17:97(1977)). This second part presents an economic analysis of the nine processes presented for obtaining carbon dioxide recovery from the atmosphere or the sea for methanol production. It is found that the most economical process of obtaining carbon dioxide is by stripping from sea water. The process of absorption/stripping by dilute potassium carbonate solution is found to be the most economical for the extraction of carbon dioxide from air at atmospheric pressure. The total energy required for methanol synthesis from these sources of carbon dioxide is 3.90 kWh(e)/lb methanol of which 90% is used for generation of hydrogen. The process which consumes the greatest amount of energy is the absorption/stripping of air by water at high pressure and amounts to 13.2 kWh(e)/lb methanol. With nuclear fusion power plants of 1000to 9000 MW(e), it is found that the cost of methanol using the extraction of carbon dioxide from air with dilute potassium carbonate solution is estimated to be in the range between Pound1.73 and Pound2.90/MMB.t.u. (energy equivalent - 1974 cost) for plant capacities of 21 400 to 193 000 bbl/day methanol. This methanol cost is competitive with gasoline in the range of 19 approximately equal to 33c/gallon. For the process of stripping of carbon dioxide from sea water, the cost is found to lie in the range of Pound1.65 to Pound2.71/MMB.t.u. (energy equivalent) for plant capacities of 21 700 to 195 000 bbl/day methanol which is competitive with gasoline in the range of 18 approximately equal to 30 c/gallon. Projection of methanol demand in the year 2020 is presented based on both its conventional use as chemicals and as a liquid fuel substituting for oil and gas. (author)

  8. International Thermonuclear Experimental Reactor U.S. Home Team Quality Assurance Plan

    Energy Technology Data Exchange (ETDEWEB)

    Sowder, W. K.

    1998-10-01

    The International Thermonuclear Experimental Reactor (ITER) project is unique in that the work is divided among an international Joint Central Team and four Home Teams, with the overall responsibility for the quality of activities performed during the project residing with the ITER Director. The ultimate responsibility for the adequacy of work performed on tasks assigned to the U.S. Home Team resides with the U.S. Home Team Leader and the U.S. Department of Energy Office of Fusion Energy (DOE-OFE). This document constitutes the quality assurance plan for the ITER U.S. Home Team. This plan describes the controls exercised by U.S. Home Team management and the Performing Institutions to ensure the quality of tasks performed and the data developed for the Engineering Design Activities assigned to the U.S. Home Team and, in particular, the Research and Development Large Projects (7). This plan addresses the DOE quality assurance requirements of 10 CFR 830.120, "Quality Assurance." The plan also describes U.S. Home Team quality commitments to the ITER Quality Assurance Program. The ITER Quality Assurance Program is based on the principles described in the International Atomic Energy Agency Standard No. 50-C-QA, "Quality Assurance for Safety in Nuclear Power Plants and Other Nuclear Facilities." Each commitment is supported with preferred implementation methodology that will be used in evaluating the task quality plans to be submitted by the Performing Institutions. The implementing provisions of the program are based on guidance provided in American National Standards Institute/American Society of Mechanical Engineers NQA-1 1994, "Quality Assurance." The individual Performing Institutions will implement the appropriate quality program provisions through their own established quality plans that have been reviewed and found to comply with U.S. Home Team quality assurance plan commitments to the ITER Quality Assurance Program. The extent of quality program provisions

  9. Proposal for a decision of the Council concerning the planning of a research- and education-program (1982-1986) on the field of thermonuclear fusion

    International Nuclear Information System (INIS)

    The thermonuclear fusion is in an early development state and has however in principle possible advantages which could be especially valuable for Europe. The primary fusion fuels (D, Li) are plentiful existent, wide spread and cheap (1 g natural Lithium could generate 15 MHW); both fuels and the end product of the reactions - Helium - are stable. From the nuclear-technological point of view a thermonuclear reactor could be built with high safety; the doubling time for breeding of new fuels in principle could be very short. These potential advantages however are balanced by certain disadvantages, e.g. high costs for the construction of a thermonuclear reactor etc. The research program, other possibilities and the costs are outlined. (orig./HT) [de

  10. Proposal for a decision of the EC Council concerning the planning of a research- and education-program (1982-1986) on the field of controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    The thermonuclear fusion is in a early development state and has, however, in principle possible advantages which could be especially valuable for Europe: the primary fusion fuels (D, Li) are plentiful existent, wide spread and cheap (1 g natural Lithium could generate 15 MWh); both fuels and the end product of the reactions - Helium - are stable. From the nuclear-technological point of view a thermonuclear reactor could be built with high safety; the doubling time for breeding of new fuels in principle could be very short. These potential advantages, however, are balanced by certain disadvantages, e.g. high costs for the construction of a thermonuclear reactor etc. The research program, other possibilities and the costs are outlined. (orig./HT) [de

  11. HLA variants rs9271366 and rs9275328 are associated with systemic lupus erythematosus susceptibility in Malays and Chinese.

    Science.gov (United States)

    Chai, H C; Phipps, M E; Othman, I; Tan, L P; Chua, K H

    2013-02-01

    Human leukocyte antigen (HLA) antigens and genes have long been reported associated with systemic lupus erythematosus (SLE) susceptibility in many populations. With the advance in technologies such as genome-wide association studies, many newly discovered SLE-associated single-nucleotide polymorphisms (SNPs) have been reported in recent years. These include HLA-DRB1/HLA-DQA1 rs9271366 and HLA-DQB1/HLA-DQA2 rs9275328. Our aim was to investigate these SNPs in a Malaysian SLE cohort. SNPs rs9271366 and rs9275328 were screened across 790 Malaysian citizens from three ethnic groups (360 patients and 430 healthy volunteers) by Taqman SNP genotyping assays. Allele and genotyping frequencies, Hardy-Weinberg equilibrium, Fisher's exact test and odds ratio were calculated for each SNP and ethnic group. Linkage disequilibrium and interaction between the two SNPs were also evaluated. The minor allele G and its homozygous genotype GG of HLA-DRB1/HLA-DQA1 rs9271366 significantly increased the SLE susceptibility in Malaysian patients, including those of Malay and Chinese ethnicity (odds ratio (OR) > 1, p < 0.05). As for HLA-DQB1/HLA-DQA2 rs9275328, the minor allele T and the heterozygous genotype CT conferred protective effect to SLE in Malaysians, as well as in Malays and Chinese, by having OR < 1 and p value <0.05. Both SNPs did not show associations to SLE in Indians. D' and r (2) values for the two SNPs in LD analysis were 0.941 and 0.065, respectively, with haplotype GC and AT being significantly associated with SLE (p < 5.0 × 10(-4)) after 10,000 permutations were performed. The MDR test clustered the genotype combinations of GG and CC, and AG and CC of rs9271366 and rs9275328, accordingly, as high-risk group, and the two SNPs interacted redundantly by removing 1.96% of the entropy. Our findings suggest that in addition to some classical HLA variants, rs9271366 and rs9275328 are additional polymorphisms worth considering in the Malaysian and possibly in

  12. Evaluation of transcobalamin II rs1801198 and transcobalamin II receptor rs2336573 gene polymorphisms in recurrent spontaneous abortion.

    Science.gov (United States)

    Hashemi, Mohammad; Mokhtari, Mojgan; Yazdani-Shahrbabaki, Vajiheh; Danesh, Hiva; Bizhani, Fatemeh; Taheri, Mohsen

    2018-03-14

    It has been proposed that transcobalamin 2 (TCN2) and the transcobalamin 2 receptor (TCN2R) are associated with idiopathic recurrent spontaneous abortion (RSA). The aim of the present study was to investigate the impact of TCN2 rs1801198 and TCN2R rs2336573 polymorphism on RSA in a sample of Iranian population. This case-control study was done on 92 RSA patients and 93 normal, fertile women. Genotyping of the TCN2 rs1801198 and TCN2R rs2336573 variants was done by polymerase chain reaction restriction fragment length polymorphism (PCR-RFLP). The findings showed no significant association between the TCN2 rs1801198 and TCN2R rs2336573 polymorphisms and the risk/protection of RSA. Our results did not support an association between the TCN2 polymorphism and the risk of RSA in a sample of southeast Iranian population. Larger studies with different ethnicities are needed to evaluate the possible impact of TCN2 and TCN2R polymorphisms on the pathogenesis of RSA. Impact statement What is already known on this subject? Recurrent spontaneous abortion (RSA), a multifactorial condition, is one of the most common complications of pregnancy. It has been proposed that genetic polymorphisms play a role in the pathogenesis of RSA. Few studies have examined the association between TNC2 and TCN2R polymorphisms and the RSA risk and the findings were inconsistent. The aim of the current study was to determine the possible association between the TCN2 rs1801198 and TCN2R rs2336573 polymorphisms and the RSA in a sample of the southeast Iranian population. What do the results of the study add? The findings of the present case-control study did not support an association between the TCN2 rs1801198 and TCN2R rs2336573 polymorphisms and the risk of RSA in a sample of the Iranian population. What are the implications of these findings for clinical practice and future research? The findings of this study may provide a basis for future studies with larger sample sizes and different ethnicities

  13. Association of PTPN22 rs2476601 and STAT4 rs7574865 polymorphisms with rheumatoid arthritis: A meta-analysis update.

    Science.gov (United States)

    Elshazli, Rami; Settin, Ahmad

    2015-08-01

    Rheumatoid arthritis (RA) is a common autoimmune disease with a complex genetic background. The genes encoding protein tyrosine phosphatase non-receptor type 22 (PTPN22) and signal transducer and activator of transcription 4 (STAT4) have been reported to be associated with RA in several ethnic populations. This work aims to assess the association between PTPN22 rs2476601 and STAT4 rs7574865 polymorphisms with RA susceptibility through an updated meta-analysis of available case-control studies. A literature search of all relevant studies published from January 2007 up to December 2014 was conducted using Pubmed and Science Direct databases. The observed studies that were related to an association between PTPN22 rs2476601 and STAT4 rs7574865 polymorphisms with RA susceptibility were identified. Meta-analysis of the pooled and stratified data was done and assessed using varied genetic models. Thirty-seven case-control studies with a total of 47 comparisons (29 for PTPN22 rs2476601 polymorphism and 18 for STAT4 rs7574865 polymorphism) met our inclusion criteria. The meta-analysis showed an association between PTPN22 T allele, CT+TT and TT genotypes with RA susceptibility. Furthermore, The meta-analysis showed an association between STAT4 T allele, GT+TT and TT genotypes with RA susceptibility. Stratification of RA patients according to ethnic groups showed that PTPN22 T allele, CT+TT genotypes, STAT4 T allele and STAT4 GT+TT were significantly associated with RA in European, Asian, African subjects, while PTPN22 TT genotype was significantly associated with RA in European but not in Asian and African subjects and STAT4 TT genotype was significantly associated with RA in European and Asian but not in African subject. A subgroup analysis according to the presence or absence of rheumatoid factor (RF) and anti-cyclic citrullinated peptide (anti-CCP) antibodies revealed that the association between PTPN22 rs2476601 and STAT4 rs7574865 polymorphisms with RA susceptibility

  14. Association between rs6812193 polymorphism and sporadic Parkinson's disease susceptibility.

    Science.gov (United States)

    Huo, Qiang; Li, Tao; Zhao, Peiqing; Wang, Lianqing

    2015-08-01

    Recently, the association of a single nucleotide polymorphism rs6812193 C/T with sporadic Parkinson's disease (PD) susceptibility has been widely evaluated, but the results remained inconsistent. This association should be clarified because of the importance of it on human health and quality of life. We performed a comprehensive meta-analysis to evaluate the association between the rs6812193 polymorphism and sporadic PD. PubMed was used to retrieve articles published up to June 2014 for all studies evaluating the rs6812193 polymorphism and PD in humans. Ethnicity-specific subgroup analysis was also performed based on ethnicity susceptibility. A total of 17 independent study samples (15 Caucasians and 2 Asians) including 17,956 cases and 52,751 controls were used in the presented study. The MAFT (minor allele T frequency) in PD patients of European descent is obviously higher than Asian cases (p susceptibility among overall samples (OR 0.882, 95 % CI 0.856-0.908) and Caucasian population (OR 0.881, 95 % CI 0.856-0.907), but not in Asian samples (OR 0.918, 95 % CI 0.721-1.168). No evidence of publication bias was observed. Throughout our analysis, the rs6812193 polymorphism is significantly associated with sporadic PD susceptibility in Caucasian samples, and ethnicity might be the key point of inconsistency in rs6812193 studies. Further studies are warranted to re-examine the observed associations, especially in different ethnicities.

  15. Development and evaluation of plasma facing materials for future thermonuclear fusion reactors

    International Nuclear Information System (INIS)

    Linke, J.; Pintsuk, G.; Roedig, M.; Schmidt, A.; Thomser, C.

    2010-01-01

    More and more attention is directed towards thermonuclear fusion as a possible future energy source. Major advantages of this energy conversion technology are the almost inexhaustible resources and the option to produce energy without CO 2 -emissions. However, in the most advanced field of magnetic plasma confinement a number of technological challenges have to be met. In particular high-temperature resistant and plasma compatible meterials have to be developed and qualified which are able to withstand the extreme environments in a commercial thermonuclear power reactor. The plasma facing materials (PEMs) and components (PFCs) in such fusion devices, i.e. the first wall (FW), the limiters and the divertor, are strongly affected by the plasma wall interaction processes and the applied intense thermal loads during plasma operation. On the one hand, these mechanisms have a strong influence on the plasma performance; on the other hand, they have major impact on the lifetime of the plasma facing armour. Materials for plasma facing components have to fulfill a number of requirements. First of all the materials have to be plasma compatible, i.e. they should exhibit a low atomic number to avoid radiative losses whenever atoms from the wall material will be ionized in the plasma. In addition, the materials must have a high melting point, a high thermal conductivity, and adequate mechanical properties. To select the most suitable material candidates, a comprehensive data base is required which includes all thermo-physical and mechanical properties. In present-day and next step devices the resulting thermal steady state heat loads to the first wall remain below 1 MWm -2 , meanwhile the limiters and the divertor are expected to be exposed to power densities being at least one order of magnitude above the FW-level, i.e. up to 20 MWm -2 for next step tokamaks such as ITER or DEMO. These requirements are responsible for high demands on the selection of qualified PFMs and heat

  16. Development and evaluation of plasma facing materials for future thermonuclear fusion reactors

    Energy Technology Data Exchange (ETDEWEB)

    Linke, J.; Pintsuk, G.; Roedig, M.; Schmidt, A.; Thomser, C. [Forschungszentrum Juelich GmbH, EURATOM Association, Juelich (Germany)

    2010-07-01

    More and more attention is directed towards thermonuclear fusion as a possible future energy source. Major advantages of this energy conversion technology are the almost inexhaustible resources and the option to produce energy without CO{sub 2}-emissions. However, in the most advanced field of magnetic plasma confinement a number of technological challenges have to be met. In particular high-temperature resistant and plasma compatible meterials have to be developed and qualified which are able to withstand the extreme environments in a commercial thermonuclear power reactor. The plasma facing materials (PEMs) and components (PFCs) in such fusion devices, i.e. the first wall (FW), the limiters and the divertor, are strongly affected by the plasma wall interaction processes and the applied intense thermal loads during plasma operation. On the one hand, these mechanisms have a strong influence on the plasma performance; on the other hand, they have major impact on the lifetime of the plasma facing armour. Materials for plasma facing components have to fulfill a number of requirements. First of all the materials have to be plasma compatible, i.e. they should exhibit a low atomic number to avoid radiative losses whenever atoms from the wall material will be ionized in the plasma. In addition, the materials must have a high melting point, a high thermal conductivity, and adequate mechanical properties. To select the most suitable material candidates, a comprehensive data base is required which includes all thermo-physical and mechanical properties. In present-day and next step devices the resulting thermal steady state heat loads to the first wall remain below 1 MWm{sup -2}, meanwhile the limiters and the divertor are expected to be exposed to power densities being at least one order of magnitude above the FW-level, i.e. up to 20 MWm{sup -2} for next step tokamaks such as ITER or DEMO. These requirements are responsible for high demands on the selection of qualified PFMs

  17. On the implementation of a chain nuclear reaction of thermonuclear fusion on the basis of the p+11B process

    Science.gov (United States)

    Belyaev, V. S.; Krainov, V. P.; Zagreev, B. V.; Matafonov, A. P.

    2015-07-01

    Various theoretical and experimental schemes for implementing a thermonuclear reactor on the basis of the p+11B reaction are considered. They include beam collisions, fusion in degenerate plasmas, ignition upon plasma acceleration by ponderomotive forces, and the irradiation of a solid-state target from 11B with a proton beam under conditions of a Coulomb explosion of hydrogen microdrops. The possibility of employing ultra-short high-intensity laser pulses to initiate the p+11B reaction under conditions far from thermodynamic equilibrium is discussed. This and some other weakly radioactive thermonuclear reactions are promising owing to their ecological cleanness—there are virtually no neutrons among fusion products. Nuclear reactions that follow the p+11B reaction may generate high-energy protons, sustaining a chain reaction, and this is an advantage of the p+11B option. The approach used also makes it possible to study nuclear reactions under conditions close to those in the early Universe or in the interior of stars.

  18. Codificador RS(n,k basado en LFCS: caso de estudio RS(7,3

    Directory of Open Access Journals (Sweden)

    Cecilia Sandoval-Ruiz

    2012-01-01

    Full Text Available El presente artículo presenta el diseño de un codi® cador Reed Solomon basado en un circuito concurrente, LFCS - Linear Feedback Concurrent Structure- que permite la generación de los símbolos de redundancia del código de forma paralela, siempre que se le suministren los k símbolos de información a codificar de forma simultánea, el codifi cador ofrece a su salida los símbolos de redundancia correspondientes. Para lograr este desarrollo se generalizó el modelo matemáticos para la descripción del comportamiento del codificador, se realizó la configuración en lenguaje descriptor de hardware VHDL de un codificador Reed Solomon, tomando como caso de estudio el RS(7,3, se simuló el diseño propuesto validando así su funcionamiento, para finalmente realizar la comparación de la implementación del codifi cador entre la versión secuencial y la versión basada en LFCS, obteniendo una reducción de componentes hardware y optimizando la velocidad de respuesta y consumo de potencia. Concluyendo, que el diseño del codi® cador propuesto valida el modelo concurrente generalizado a partir de la correspondencia con la arquitectura del LFCS.

  19. Enhancement and feature extraction of RS images from seismic area and seismic disaster recognition technologies

    Science.gov (United States)

    Zhang, Jingfa; Qin, Qiming

    2003-09-01

    Many types of feature extracting of RS image are analyzed, and the work procedure of pattern recognizing in RS images of seismic disaster is proposed. The aerial RS image of Tangshan Great Earthquake is processed, and the digital features of various typical seismic disaster on the RS image is calculated.

  20. RS-Predictor models augmented with SMARTCyp reactivities

    DEFF Research Database (Denmark)

    Zaretzki, Jed; Rydberg, Patrik; Bergeron, Charles

    2012-01-01

    (82.3%) and merged(86.0%). Comprehensive datamining of each substrate set and careful statistical analyses of the predictions made by the different models revealed new insights into molecular features that control metabolic regioselectivity and enable accurate prospective prediction of likely SOMs.......RS-Predictor is a tool for creating pathway-independent, isozyme-specific site of metabolism (SOM) prediction models using any set of known cytochrome P450 substrates and metabolites. Until now, the RS-Predictor method was only trained and validated on CYP 3A4 data, but in the present study we...... report on the versatility the RS-Predictor modeling paradigm by creating and testing regioselectivity models for substrates of the nine most important CYP isozymes. Through curation of source literature, we have assembled 680 substrates distributed among CYPs 1A2, 2A6, 2B6, 2C19, 2C8, 2C9, 2D6, 2E1 and 3...

  1. Polymorphisms rs12998 and rs5780218 in KiSS1 Suppressor Metastasis Gene in Mexican Patients with Breast Cancer

    Directory of Open Access Journals (Sweden)

    Edhit Guadalupe Cruz Quevedo

    2015-01-01

    Full Text Available Aims. KiSS1 is a metastasis suppressor gene associated with inhibition of cellular chemotaxis and invasion attenuating the metastasis in melanoma and breast cancer cell lines. Along the KiSS-1 gene at least 294 SNPs have been described; however the association of these polymorphisms as genetic markers for metastasis in breast cancer studies has not been investigated. Here we describe two simple PCR-RFLPs protocols to identify the rs5780218 (9DelT and the rs12998 (E20K KiSS1 polymorphisms and the allelic, genotypic, and haplotypic frequencies in Mexican general population (GP and patients with benign breast disease (BBD or breast cancer (BC. Results. The rs5780218 polymorphism was individually associated with breast cancer (P=0.0332 and the rs12998 polymorphism shows statistically significant differences when GP versus case (BC and BBD groups were compared (P<0.0001. The H1 Haplotype (G/- occurred more frequently in BC group (0.4256 whereas H2 haplotype (G/T was the most prevalent in BBD group (0.4674. Conclusions. Our data indicated that the rs5780218 polymorphism individually confers susceptibility for development of breast cancer in Mexican population and a possible role as a genetic marker in breast cancer metastasis for H1 haplotype (Wt/variant in KiSS1 gene must be analyzed in other populations.

  2. Resiliency Scale (RS): Scale Development, Reliability and Validity Study

    OpenAIRE

    GÜRGAN, Uğur

    2003-01-01

    The purpose of this study was to develop a new Resiliency Scale (RS) for Turkish samples. Various items from some major resiliency scales, most of them with some partial change, were collected and a pool of 228 items containing almost all possible resilience areas were obtained. This item-pool was administered to a college sample of 419. Resulting of analysis 50 item RS were obtained and administered to a new college sample of 112 participants. This second sample has also received the Rosenba...

  3. Crosstalk XVI, basic data communication and RS-232C

    International Nuclear Information System (INIS)

    Hwang, Hui Yung

    1988-10-01

    This book is divided into three parts, which deals with compatible software of data communication with IBM PC XT/AT. The first part consists of an introduction to crosstalk XVI, getting start for user, crosstalk practice, call with crosstalk, terminal feature, switch of communication parameter, terminal emulation, capturing data, transmission of text file answer mode, file transfer, command file and script file, command summary and examples. The second part deals with basic personal computer communication, RS-232C and explanation of communication control : RS-232C interface, transmission device and interrupt controller 8259.

  4. THE HISTORY OF LABORATORY ANIMALS AND THE 3RS

    DEFF Research Database (Denmark)

    Alstrup, Aage Kristian Olsen

    This talk will give an introduction to the history of the use of laboratory animals with focus on the history of the three Rs (3Rs). We will see how animal experimentation has been performed early in our civilization, and how the suffering of animals has been justified. This will include Rene...... Descartes´s mechanical view of animals in the seventeenth century, and Charles Darwin's ambivalent relationship to animal experimentation, which he views as cruel but necessary. In the 1870s the Danish Foundation for Protection of Animals (“Dyrenes Beskyttelse”) and Professor Peter Panum discussed the use...

  5. Validation of Omron RS8, RS6, and RS3 home blood pressure monitoring devices, in accordance with the European Society of Hypertension International Protocol revision 2010.

    Science.gov (United States)

    Takahashi, Hakuo; Yoshika, Masamichi; Yokoi, Toyohiko

    2013-01-01

    Allowing patients to measure their blood pressure at home is recognized as being of clinical value. However, it is not known how often these measurements are taken correctly. Blood pressure monitors for home use fall into two types based on the position of the cuff, ie, at the upper arm or the wrist. The latter is particularly convenient, as measurements can be taken fully clothed. This study aimed to evaluate the performance of the wrist-type blood pressure monitors Omron RS8 (HEM-6310F-E), Omron RS6 (HEM-6221-E), and Omron RS3 (HEM-6130-E). A team of three trained doctors validated the performance of these devices by comparing the measurements obtained from these devices with those taken using a standard mercury sphygmomanometer. All the devices met the validation requirements of the European Society of Hypertension International Protocol revision 2010. The difference in blood pressure readings between the tested device and the standard mercury sphygmomanometer was within 3 mmHg, which is acceptable according to the European Society of Hypertension guidelines. All the home devices tested were found to be suitable for measuring blood pressure at home because their performance fulfilled the requirement of the guidelines.

  6. The Two-Component System CprRS Senses Cationic Peptides and Triggers Adaptive Resistance in Pseudomonas aeruginosa Independently of ParRS

    DEFF Research Database (Denmark)

    Fernandez, Luca; Jenssen, Håvard; Bains, Manjeet

    2012-01-01

    dependency on the CprRS and ParRS systems in a concentration-dependent manner. It was further demonstrated that, following exposure to inducing antimicrobial peptides, cprRS mutants did not become adaptively resistant to polymyxins as was observed for wild-type cells. Our microarray studies demonstrated...

  7. Nano-scale bubble thermonuclear fusion in acoustically cavitated deuterated liquid

    International Nuclear Information System (INIS)

    Robert I Nigmatulin; Richard T Lahey Jr; Rusi Taleyarkhan

    2005-01-01

    Full text of publication follows: It has been experimentally shown (Taleyarkhan, West, Cho, Lahey, Nigmatulin, Block, 2002, 2004) that neutron emission and tritium formation may occur in deuterated acetone (D-acetone C 3 DO 6 ) under acoustic cavitation conditions. Intensity of the fast neutron (2.45 MeV) emission and tritium nucleus production is ∼ 4 x 10 5 s -1 . This suggests ultrahigh compression of matter produced inside bubbles during their collapse. In the paper a systematic theoretical analysis of the vapor bubble growth and subsequent implosion in intense acoustic fields in D-acetone is presented. The goal is to describe and explain the experimental observations of thermonuclear fusion for collapsing cavitation bubble in D-acetone. The dynamics of bubbles formed during maximum rarefaction in the liquid is numerically studied on the basis of the developed models of a single bubble and bubble clusters. It is supposed that during their growth the bubbles coagulate and form a few bigger bubbles, which then collapse under the action of additional pressure pulses produced in the liquid through the intensification of acoustic waves within the cluster. A shock wave is shown to be formed inside the bubble during the latter's rapid contraction. Focusing of this shock wave in the bubble center initiates dissociation and ionization, violent increases in density (10 4 kg m 3 ), pressure (10 10 -10 11 bar) and temperature (2 x 10 8 K), high enough to produce nuclear fusion reactions. The bubble looks like micro-hydrogen bomb. The diameter of the neutron emission zone is about 100 nm. The highest neutron emission is recorded at about 10-20 nm from the bubble center. It is found out that the intensity of bubble implosion and the number of neutron emitted increase with variations in nucleation phase, positive half-wave amplitude, liquid temperature and also with the involvement of coagulation mechanisms within the cluster during the bubble simultaneous growth. The number

  8. Association of the matrix metalloproteinase-3 polymorphisms rs679620 and rs3025058 with ischemic stroke risk: a meta-analysis

    Directory of Open Access Journals (Sweden)

    Zhang Q

    2018-01-01

    Full Text Available Qi-Wei Zhang Department of Neurosurgery, The Affiliated Hospital of Jilin Medical University, Jilin, People’s Republic of China Purpose: The relationship of the matrix metalloproteinase-3 (MMP-3 polymorphisms rs679620 and rs3025058 with ischemic stroke has received much attention. The aim of the present study was to perform a meta-analysis of published case–control studies to evaluate the cumulative evidence.Methods: We performed a search of ISI Web of Science, Embase, PubMed, and China National Knowledge Infrastructure databases. Pooled odds ratios (ORs were appropriately derived from fixed-effects or random-effects models.Results: We identified seven eligible studies including 5,204 subjects. The pooled analysis showed that the MMP-3 rs679620 A allele carriers had increased risk of ischemic stroke compared with homozygotes for the G allele in Asians (AA + GA vs GG: OR =1.42, 95% CI: 1.05–1.91, P=0.022. Concerning the rs3025058 polymorphism, the results did not suggest an association between rs3025058 genotypes and ischemic stroke risk (5A5A + 6A5A vs 6A6A: OR =1.04, 95% CI: 0.73–1.47, P=0.844; 5A5A vs 6A5A + 6A6A: OR =1.14, 95% CI: 0.74–1.77, P=0.556; and 5A5A vs 6A6A: OR =1.11, 95% CI: 0.68–1.80, P=0.677. In subgroup analysis by ethnicity, no statistically significant associations were demonstrated for rs3025058 in Asians and Caucasians, respectively. There was no evidence for publication bias.Conclusion: Our findings indicate that the rs679620 A allele carriers have increased risk of ischemic stroke in Asians, but there is no association between rs3025058 and ischemic stroke risk. Keywords: ischemic stroke, meta-analysis, MMP-3, polymorphism

  9. RS485 optical router for HIRFL-CSR

    International Nuclear Information System (INIS)

    Zhang Shuocheng; Wang Dan; Jing Lan; Qiao Weimin

    2007-01-01

    A communication equipment-RS485 optical router has been developed to satisfy requirements of control system communication network of HIRFL-CSR (Heavy Ion Research Facility at Lanzhou-Cooling Storage Ring). The equipment is compatible with multiple communication protocols, such as Ethernet, RS232 and RS485 standard. It can be used to setup the RS485 communication network quickly and connected to the Ethernet easily. The fiber optical interface is introduced to facilitate the connection with the network of industrial Fiber Optics Communication (FOC), which expands the application field of the equipment in a large extent. This paper introduces the details of the equipment, including the design of the circuit and software, features of the equipment and how it works in the whole control system network. Its application in the HIRFL-CSR control system shows that the equipment is in accordance with the general requirement of automatic control communication system. It could also be used in other industrial automatic control fields. (authors)

  10. CAT bags orders worth Rs 90 Crore from EU

    CERN Multimedia

    2002-01-01

    "Orders to the tune of Rs 90 crore have been received by Indore-based Centre for Advanced Technology (CAT) from laboratories in the European Union (EU) and more orders are likely to follow in the near future, according to Pune-based Patel Analog and Digital Measurement Company (PADMCO) director Madhu Patel" (1/2 page).

  11. Genetic association of polymorphism rs1333049 with gout.

    Science.gov (United States)

    Wang, Binbin; Meng, Dongmei; Wang, Jing; Liu, Shiguo; Zhou, Sirui; Miao, Zhimin; Han, Lin; Chu, Nan; Zhang, Kun; Ma, Xu; Li, Changgui

    2011-09-01

    We suspect that genes or loci that contribute to coronary artery disease (CAD) may also play a role in the pathogenesis of gout, since hyperuricaemia leads to gout, and serum uric acid (SUA) levels are potential risk factors for CAD. The single nucleotide polymorphism (SNP) rs1333049 (C/G) on chromosome 9p21 has been implicated in previous studies to be associated with CAD. The aim of this study was to evaluate the relationship between this SNP and gout pathogenesis. Nine hundred Chinese Han were recruited for this study (461 gout patients and 439 gout-free individuals). The rs1333049 SNP and surrounding sequences were PCR sequenced. There was a clear link between the rs1333049 genotypic and allelic frequencies between gout cases and controls (χ(2) = 6.81, df = 2, P = 0.033 by genotype; χ(2) = 6.63, df = 1, P = 0.01 by allele). There was a significantly increased risk of gout in carriers of the CC genotype (odds ratio = 1.43, 95% CI 1.07, 1.91). To the best of our knowledge, our findings are the first to establish an association of rs1333049 with gout in a Chinese Han population. Meanwhile, this SNP is homologous to miR-519 and miR-520.

  12. 7q21-rs6964587 and breast cancer risk

    DEFF Research Database (Denmark)

    Milne, Roger L; Lorenzo-Bermejo, Justo; Burwinkel, Barbara

    2011-01-01

    Using the Breast Cancer Association Consortium, the authors previously reported that the single nucleotide polymorphism 7q21-rs6964587 (AKAP9-M463I) is associated with breast cancer risk. The authors have now assessed this association more comprehensively using 16 independent case-control studies....

  13. Work in Progress: The Seven Rs of Team Building

    Science.gov (United States)

    Brunelli, Jean; Schneider, Elaine Fogel

    2004-01-01

    This article argues that supportive teams--including professionals, paraprofessionals, and parents--can teach staff members how to identify and implement best practices in early intervention settings. The authors describe "the seven Rs of team building" distilled from their many years of team building and maintenance: 1) Reading cues; 2) Regular…

  14. Associations of polymorphisms in the cytokine genes IL1β (rs16944), IL6 (rs1800795), IL12b (rs3212227) and growth factor VEGFA (rs2010963) with anthracosilicosis in coal miners in Russia and related genotoxic effects.

    Science.gov (United States)

    Volobaev, Valentin P; Larionov, Aleksey V; Kalyuzhnaya, Ekaterina E; Serdyukova, Ekaterina S; Yakovleva, Svetlana; Druzhinin, Vladimir G; Babich, Olga O; Hill, Elena G; Semenihin, Victor A; Panev, Nikolay I; Minina, Varvara I; Sivanesan, Saravana Devi; Naoghare, Pravin; da Silva, Juliana; Barcelos, Gustavo R M; Prosekov, Alexander Y

    2018-04-13

    Anthracosilicosis (AS), a prevalent form of pneumoconiosis among coal miners, results from the accumulation of carbon and silica in the lungs from inhaled coal dust. This study investigated genotoxic effects and certain cytokine genes polymorphic variants in Russian coal miners with АS. Peripheral leukocytes were sampled from 129 patients with AS confirmed by X-ray and tissue biopsy and from 164 asymptomatic coal miners. Four single-nucleotide polymorphisms were genotyped in the extracted DNA samples: IL1β T-511C (rs16944), IL6 C-174G (rs1800795), IL12b A1188C (rs3212227) and VEGFA C634G (rs2010963). Genotoxic effects were assessed by the analysis of chromosome aberrations in cultured peripheral lymphocytes. The mean frequency of chromatid-type aberrations and chromosome-type aberrations, namely, chromatid-type breaks and dicentric chromosomes, was found to be higher in AS patients [3.70 (95% confidence interval {CI}, 3.29-4.10) and 0.28 (95% CI, 0.17-0.38)] compared to the control group [2.41 (95% CI, 2.00-2.82) and 0.09 (95% CI, 0.03-0.15)], respectively. IL1β gene T/T genotype (rs16944) was associated with AS [17.83% in AS patients against 4.35% in healthy donors, odds ratio = 4.77 (1.88-12.15), P < 0.01]. A significant increase in the level of certain chromosome interchanges among AS donors is of interest because such effects are typical for radiation damage and caused by acute oxidative stress. IL1β T allele probably may be considered as an AS susceptibility factor among coal miners.

  15. APOC3 rs2070666 Is Associated with the Hepatic Steatosis Independently of PNPLA3 rs738409 in Chinese Han Patients with Nonalcoholic Fatty Liver Diseases.

    Science.gov (United States)

    Zhang, Rui-Nan; Zheng, Rui-Dan; Mi, Yu-Qiang; Zhou, Da; Shen, Feng; Chen, Guang-Yu; Zhu, Chan-Yan; Pan, Qin; Fan, Jian-Gao

    2016-08-01

    The association between nonalcoholic fatty liver disease (NAFLD) and apolipoprotein C3 gene (APOC3) promoter region single-nucleotide polymorphisms (SNPs) rs2854117 and rs2854116 is controversial. The aim of this study was to investigate the relationship between other polymorphisms of APOC3 and NAFLD in Chinese. Fifty-nine liver biopsy-proven NAFLD patients and 72 healthy control subjects were recruited to a cohort representing Chinese Han population. The polymorphisms in the exons and flanking regions of APOC3 and patatin-like phospholipase domain-containing protein 3 (PNPLA3) rs738409 polymorphisms were genotyped. Among the five SNPs (rs4225, rs4520, rs5128, rs2070666, and rs2070667) in APOC3, only rs2070666 (c.179 + 62 T/A) was significantly different in genotype and allele frequency (both p steatosis (OR 4.986, 95 % CI 1.020-24.371), but neither to liver stiffness measurement values nor to hepatic histological activity and fibrosis in NAFLD patients. The APOC3 rs2070666 A allele is a risk factor for NAFLD independent of obesity, dyslipidemia, and PNPLA3 rs738409, and it might contribute to increased liver fat content in Chinese Han population.

  16. Comprehensive safety analysis code system for nuclear fusion reactors II: Thermal analysis during plasma disruptions for international thermonuclear experimental reactor

    International Nuclear Information System (INIS)

    Honda, T.; Maki, K.; Okazaki, T.

    1994-01-01

    Thermal characteristics of a fusion reactor [International Thermonuclear Experimental Reactor (ITER) Conceptual Design Activity] during plasma disruptions have been analyzed by using a comprehensive safety analysis code for nuclear fusion reactors. The erosion depth due to disruptions for the armor of the first wall depends on the current quench time of disruptions occurring in normal operation. If it is possible to extend the time up to ∼50 ms, the erosion depth is considerably reduced. On the other hand, the erosion depth of the divertor is ∼570 μm for only one disruption, which is determined only by the thermal flux during the thermal quench. This means that the divertor plate should be exchanged after about nine disruptions. Counter-measures are necessary for the divertor to relieve disruption influences. As other scenarios of disruptions, beta-limit disruptions and vertical displacement events were also investigated quantitatively. 13 refs., 5 figs

  17. Possible applications of a hybrid thermonuclear energy source based on a DPF device in modern energy complexes

    International Nuclear Information System (INIS)

    Gribkov, V.A.; Tyagunov, M.G.

    1983-01-01

    A source of thermonuclear energy based on the dense plasma focus (DPF) device in a hybrid fusion-fission version is proposed. In its initial operating phase such a facility would be a net energy consumer and would breed fissile material; as the fissile content in the blanket increases, the installation would become a net energy producer. Under the proposed scheme of blanket operation, up to 50% of the uranium could be burned while maintaining electrical output and without refabrication of fuel elements. If desired, operation could continue after the fuel is almost completely exhausted to burn the nuclear waste. It is thought that the new source could become both technologically and economically feasible in the near future. Smooth control should present no problem and the speed at which the device could be brought up to full load should greatly improve the flexibility of the overall electrical supply system

  18. New stainless steels of ferrite-martensite grade and perspectives of their application in thermonuclear facilities and fast reactors

    International Nuclear Information System (INIS)

    Ajtkhozhin, Eh.S.; Maksimkin, O.P.

    2007-01-01

    Review of scientific literature for last 5 years in which results on study of radiation effect on ferrite-martensite steels - construction materials of fast reactors and most probable candidates for first wall and blanket of the thermonuclear facilities ITER and Demo - are presented. Alongside with this a prior experimental data on study of microstructure changing and physical- mechanical properties of ferrite-martensite steel EhP-450 - the material of hexahedral case of spent assembly of BN-350 fast reactor- are cited. Principal attention was paid to considering of radiation effects of structural components content changing and ferrite-martensite steel swelling irradiated at comparatively low values of radiation damage climb rate

  19. Annual report of the Summit Members' Working Group on Controlled Thermonuclear Fusion (Fusin Working Group (FWG))

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1987-04-01

    The Summit Members' Working Group on Controlled Thermonuclear Fusion (Fusion Working Group (FWG)) was established in 1983 in response to the Declaration of the Heads of State and Government at the Versailles Economic Summit meeting of 1982, and in response to the subsequent report of the Working Group in Technology, Growth and Employment (TGE) as endorsed at the Williamsburg Summit meeting, 1983. This document contains the complete written record of each of the three FWG meetings which include the minutes, lists of attendees, agendas, statements, and summary conclusions as well as the full reports of the Technical Working Party. In addition, there is a pertinent exchange of correspondence between FWG members on the role of the Technical Working Party and a requested background paper on the modalities associated with a possible future ETR project.

  20. Short-term and medium-term health effects of thermonuclear weapons and war on individuals and health services

    International Nuclear Information System (INIS)

    Lechat, M.F.

    1984-01-01

    In the aftermath of a thermonuclear attack a number of health problems would appear, related to the changed living conditions, lack of food, absence of sanitation, the environmental effects, and disruption of the health services. Internal irradiation by ingestion of radioactive isotopes deposited on the ground would constitute a major hazard from the fallout. In the first few weeks following the attack iodine-131 would present the greatest hazard. Its main entry into the body would be through milk from livestock grazing on pastures contaminated with fallout; milk from local cattle pasturing in open land would thus be unsuitable for consumption. There is much speculation about the possible outbreaks of communicable diseases following a nuclear attack. Infection could emerge as a major problem. It constitutes a leading cause of death in burns. In the Japanese experience acute radiation sickness was generally accompanied by infectious complications

  1. TIBER (Tokamak Ignition/Burn Experimental Reactor) II as a precursor to an international thermonuclear experimental reactor

    International Nuclear Information System (INIS)

    Henning, C.D.; Gilleland, J.R.

    1988-01-01

    The Tokamak Ignition/Burn Experimental Reactor (TIBER) was pursued in the US as one option for an International Thermonuclear Experimental Reactor (ITER). This concept evolved from earlier work on the Tokamak Fusion Core Experiment (TFCX) to develop a small, ignited tokamak. While the copper-coil versions of TFCX became the short-pulsed, 1.23-m radius, Compact Ignition Tokamak (CIT), the superconducting TIBER with long pulse or steady state and a 2.6-m radius was considered for international collaboration. Recently the design was updated to TIBER II, to accommodate more conservative confinement scaling, double-poloidal divertors for impurity control, steady-state current drive, and nuclear testing. 18 refs., 1 fig

  2. Requirements for design of accelerator, beam transport, and target in a study of thermonuclear reaction cross section

    Energy Technology Data Exchange (ETDEWEB)

    Itahashi, T; Takahisa, K; Fujiwara, M; Toki, H; Ejiri, H [Osaka Univ., Ibaraki (Japan). Research Center for Nuclear Physics; Ohsumi, H; Komori, M

    1997-03-01

    A compact accelerator with high current ion source, low energy beam transport elements and windowless gas target was designed to investigate the thermonuclear reaction cross section. The idea of this project focused on the cross section measurement of the fusion reaction data {sup 3}He+{sup 3}He-{sup 4}He+p+p at 25keV. The system will be installed in Otoh Cosmo Observatory (1270m.w.e.) to get rid of the huge cosmic and environmental background. It consists of NANOGUN ECR ion source, focusing elements made of permanent magnets window less {sup 3}He gas target and/or He{sup 3} plasma target and detector telescopes with low noise and low background. Requirements for these were discussed technically and various ideas were proposed. (author)

  3. Genetic polymorphisms of IL-18 rs1946518 and IL-1β rs16944 are associated with prognosis and survival of acute myeloid leukemia.

    Science.gov (United States)

    Wang, Hong; Hua, Mingqiang; Wang, Shukang; Yu, Jie; Chen, Chen; Zhao, Xueyun; Zhang, Chen; Zhong, Chaoqin; Wang, Ruiqing; He, Na; Hou, Ming; Ma, Daoxin

    2017-03-01

    Though the pathogenesis of AML is still unknown, accumulating evidence revealed that immune response plays a vital part in it. NLRP3 inflammasome as a component of immune system has been found related to several cancers. The single nucleotide polymorphisms (SNPs) of NLRP3 inflammasome genes may be related to pathogenesis and prognosis of AML. We determined polymorphisms of NLRP3 (rs35829419), CARD8 (rs2043211), IL-1β (rs16944), IL-18 (rs1946518) and NF-κB -94 ins/del ATTG in de novo AML patients to find out whether they play roles in the susceptibility and severity of AML. In our study, 383 AML cases and 300 randomly selected healthy individuals were examined for the polymorphisms and expression of NLRP3 genes. IL-1β (rs16944) polymorphism in different risk AML subgroups was found statistically different, with more GA genotype in favorable-risk cytogenetics group. We also demonstrated that the bone marrow blasts of patients carrying IL-18 (rs1946518) GG or GT genotype were higher than patients of TT genotype. IL-18 plasma level of patients with IL-18 (rs1946518) GT or TT genotype was higher than GG genotype. Moreover, the GT genotype of IL-18 (rs1946518) led to statistically poorer AML-specific survival. IL-1β (rs16944) and IL-18 (rs1946518) may be served as potential predictors for AML.

  4. Predicting pKa for proteins using COSMO-RS

    DEFF Research Database (Denmark)

    Andersson, Martin Peter; Jensen, Jan Halborg; Stipp, Susan Louise Svane

    2013-01-01

    We have used the COSMO-RS implicit solvation method to calculate the equilibrium constants, pKa, for deprotonation of the acidic residues of the ovomucoid inhibitor protein, OMTKY3. The root mean square error for comparison with experimental data is only 0.5 pH units and the maximum error 0.8 p......H units. The results show that the accuracy of pKa prediction using COSMO-RS is as good for large biomolecules as it is for smaller inorganic and organic acids and that the method compares very well to previous pKa predictions of the OMTKY3 protein using Quantum Mechanics/Molecular Mechanics. Our approach...

  5. Solvation quantities from a COSMO-RS equation of state

    International Nuclear Information System (INIS)

    Panayiotou, C.; Tsivintzelis, I.; Aslanidou, D.; Hatzimanikatis, V.

    2015-01-01

    Highlights: • Extension of the successful COSMO-RS model to an equation-of-state model. • Two scaling constants, obtained from atom-specific contributions. • Overall estimation of the solvation quantities and contributions. - Abstract: This work focuses on the extension of the successful COSMO-RS model of mixtures into an equation-of-state model of fluids and its application for the estimation of solvation/hydration quantities of a variety of chemical substances. These quantities include free-energies, enthalpies and entropies of hydration as well as the separate contributions to each of them. Emphasis is given on the estimation of contributions from the conformational changes of solutes upon solvation and the associated restructuring of solvent in its immediate neighborhood. COSMO-RS is a quantum-mechanics based group/segment contribution model in which the Quasi-Chemical (QC) approach is used for the description of the non-random distribution of interacting segments in the system. Thus, the equation-of-state development is done through such a QC framework. The new model will not need any adjustable parameters for the strong specific interactions, such as hydrogen bonds, since they will be provided by the quantum-mechanics based cosmo-files – a key feature of COSMO-RS model. It will need, however, one volumetric and one energy parameter per fluid, which are scaling constants or molecular descriptors of the fluid and are obtained from rather easily available data such as densities, boiling points, vapor pressures, heats of vaporization or second virial coefficients. The performance and the potential of the new equation-of-state model to become a fully predictive model are critically discussed

  6. Převodník Ethernet na RS-232

    OpenAIRE

    Dreiseitel, Jiří

    2012-01-01

    Práce je věnována problematice konstrukce převodníku Ethernet na RS-232 za pomocí jednočipového mikrokontroléru. Cílem je seznámit čtenáře se síťovou technologií Ethernet a technologií pro sériový přenos založený na protokolu RS-232 a zároveň s technologií vestavěných systémů pro konstrukci zařízení. Součástí práce je kompletní návrh převodníku Ethernet na RS-232 včetně návrhu a implementace firmware v jazyce C za využití LwIP TCP/IP stacku. Převodník je postaven na základě vývojového kitu ST...

  7. FTO gene polymorphisms (rs9939609 and rs17817449) as predictors of Type 2 Diabetes Mellitus in obese Iraqi population.

    Science.gov (United States)

    Younus, Laith A; Algenabi, Abdul Hussein A; Abdul-Zhara, Mohammed S; Hussein, Majid K

    2017-09-05

    The variation of the SNPs in FTO (fat mass and obesity associated) gene are improved to be associated with obesity and type 2 diabetes (T2DM) in some ethnic groups for example in European while, this consistency is controversial in Asians and there were few studies in Iraqi population about the effect of this gene on the development of T2DM in obese patients. Therefore, the objective of this study is to investigate the impact of the two common FTO gene variants in the development of T2DM in obese Iraqi patients. A case-control study in which the FTO gene variants rs9939609 and rs17817449 were genotyping in a total of 800 individuals, 400 T2DM obese patients (patients group) and 400 healthy control obese volunteers (control group) to explore the relation of these SNPs with T2DM in obese Iraqi population. The patients group was enrolled from diabetic clinic in Al Najaf al Ashraf based on WHO guidelines of T2DM. From whole blood the DNA was extraction and genotyped by using ScaI and AlwNI enzymes respectively in the PCR-RFLP technique. Multinomial logistic regression was applied to compare the proportions of genotypes and alleles. The odd's ratio, t-test P value at 95% confidence interval were measured before and after adjustment of BMI, age and sex adjustment. The genetic power, Hardy Weinberg equilibrium and haplotype analysis were tested in the present study. It was observed that the presence of T allele in the two SNPs rs9939609 and rs17817449 in the FTO gene polymorphisms was associated with increased risk for the development of T2DM in Iraqi obese individuals. The minor allele (T) in rs9939609 was significantly higher (P=0.0001) in T2DM (31.25%) when compared with that of the control obese group (20%). The Homozygous genotype (TT) significantly (OR=3.25, CI 95% 1.87-5.64, P=0.000) increased the risk of T2DM by three folds with respect to those of wild type (AA) after adjustment for age, sex and BMI, furthermore, it was significantly increased the risk in the

  8. Genetic Association for P2X7R rs3751142 and CARD8 rs2043211 Polymorphisms for Susceptibility of Gout in Korean Men: Multi-Center Study.

    Science.gov (United States)

    Lee, Sung Won; Lee, Shin Seok; Oh, Dong Ho; Park, Dong Jin; Kim, Hyun Sook; Choi, Jung Ran; Chae, Soo Cheon; Yun, Ki Jung; Chung, Won Tae; Choe, Jung Yoon; Kim, Seong Kyu

    2016-10-01

    The aim of this study was to determine the association between P2X7R rs3751142 and CARD8 rs2043211 polymorphisms and gout susceptibility in male Korean subjects. This study enrolled a total of 242 male patients with gout and 280 healthy controls. The polymorphisms of two individual genes including rs3751142(C>A) in the P2X7R gene and rs2043211(A>T) in the CARD8 gene were assessed using Taq-Man analysis. Statistical analyses were performed using the Chi-square test, Kruskal-Wallis test, and logistic regression analyses. A difference in genotypic frequency of the P2X7R rs3751142 and CARD8 rs2043211 genes was not detected between gout and control patients. Clinical parameters including age, onset age, disease duration, body mass index, and serum uric acid levels were not different among the three genotypes for either P2X7R or CARD8 (P > 0.05 for all). A pair-wise comparison of P2X7R rs3751142 and CARD8 rs2043211 genotype combinations revealed that subjects with the CA P2X7R rs3751142 genotype and the TT CARD8 rs2043211 genotype had a trend toward a higher risk of gout compared to the CC/AA combination (P = 0.056, OR = 2.618, 95% CI 0.975 - 7.031). In conclusion, this study revealed that genetic variability of the P2X7R rs3751142 and CARD8 rs2043211 genes might, in part, be associated with susceptibility for gout.

  9. Association of the ENPP1 rs997509 polymorphism with obesity in ...

    African Journals Online (AJOL)

    ) polymorphisms have been associated with metabolic traits. There is no data on the effect of ENPP1 in South African children or adults. Objective: To investigate the role of K121Q (rs1044498), rs997509 and rs9402349 in obesity and other ...

  10. Dr Robert Aymar, Director of the International Thermonuclear Experimental Reactor (ITER), was nominated to succeed Professor Luciano Maiani as CERN's Director General, to take office on 1 January 2004.

    CERN Document Server

    2002-01-01

    Dr Robert Aymar, Director of the International Thermonuclear Experimental Reactor (ITER), was nominated to succeed Professor Luciano Maiani as CERN's Director General, to take office on 1 January 2004.

  11. Results from MARBLE DT Experiments on the National Ignition Facility: Implosion of Foam-Filled Capsules for Studying Thermonuclear Burn in the Presence of Heterogeneous Mix

    Science.gov (United States)

    Murphy, T. J.; Douglas, M. R.; Cardenas, T.; Cooley, J. H.; Gunderson, M. A.; Haines, B. M.; Hamilton, C. E.; Kim, Y.; Lee, M. N.; Oertel, J. A.; Olson, R. E.; Randolph, R. B.; Shah, R. C.; Smidt, J. M.

    2017-10-01

    The MARBLE campaign on NIF investigates the effect of heterogeneous mix on thermonuclear burn for comparison to a probability distribution function (PDF) burn model. MARBLE utilizes plastic capsules filled with deuterated plastic foam and tritium gas. The ratio of DT to DD neutron yield is indicative of the degree to which the foam and the gas atomically mix. Platform development experiments have been performed to understand the behavior of the foam and of the gas separately using two types of capsule. The first experiments using deuterated foam and tritium gas have been performed. Results of these experiments, and the implications for our understanding of thermonuclear burn in heterogeneously mixed separated reactant experiments will be discussed. This work is supported by US DOE/NNSA, performed at LANL, operated by LANS LLC under contract DE-AC52-06NA25396.

  12. The problems associated with the monitoring of complex workplace radiation fields at European high-energy accelerators and thermonuclear fusion facilities

    Czech Academy of Sciences Publication Activity Database

    Bilski, P.; Blomgren, J.; d´Errico, F.; Esposito, A.; Fehrenbacher, G.; Fernández, F.; Fuchs, A.; Golnik, N.; Lacoste, V.; Leuschner, A.; Sandri, S.; Silari, M.; Spurný, František; Wiegel, B.; Wright, P.

    2007-01-01

    Roč. 126, 1-4 (2007), s. 491-496 ISSN 0144-8420 R&D Projects: GA MŠk 1P05OC032 Grant - others:ES(XE) Contract no FI6R-012684 Institutional research plan: CEZ:AV0Z10480505 Keywords : radiation fields * european high-energy accelerators * thermonuclear fusion facilities Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 0.528, year: 2007

  13. Study of a filter spectrometer in the framework of a new method for measuring the temperature of thermonuclear plasmas by relativistic Thomson scattering

    International Nuclear Information System (INIS)

    Lasalle, J.

    1975-06-01

    A new method which greatly simplifies the number of measurements necessary for obtaining the temperature in thermonuclear plasmas, using the relativistic effects of Thomson scattering is presented. A few orders of magnitude are computed for probing the feasibility of such temperature measurements. The data used correspond to magnitudes relating to T.F.R. The characteristics of a filter equipped spectrometer are then defined in view of a double function: separation of the lambda>lambda laser and lambda [fr

  14. Exceptional longevity and muscle and fitness related genotypes: a functional in vitro analysis and case-control association replication study with SNPs THRH rs7832552, IL6 rs1800795 and ACSL1 rs6552828

    Directory of Open Access Journals (Sweden)

    Noriyuki eFuku

    2015-05-01

    Full Text Available There are several gene variants that are candidates to influence functional capacity in long-lived individuals. As such, their potential association with exceptional longevity (EL, i.e., reaching 100+ years deserves analysis. Among them are rs7832552 in the thyrotropin-releasing hormone receptor (TRHR gene, rs1800795 in the interleukin-6 (IL6 gene and rs6552828 in the coenzyme A synthetase long-chain 1 (ACSL1 gene. To gain insight into their functionality (which is yet unknown, here we determined for the first time luciferase gene reporter activity at the muscle tissue level in rs7832552 and rs6552828. We then compared allele/genotype frequencies of the 3 abovementioned variants among centenarians [n=138, age range 100-111 years (114 women] and healthy controls [n=334, 20-50 years (141 women] of the same ethnic and geographic origin (Spain. We also studied healthy centenarians [n=79, 100-104 years (40 women] and controls [n=316, 27-81 years (156 women] from Italy, and centenarians [n=742, 100-116 years (623 women] and healthy controls [n=499, 23-59 years (356 women] from Japan. The THRH rs7832552 T-allele and ACSL1 rs6552828 A-allele up-regulated luciferase activity compared to the C and G-allele, respectively (P≤0.001. Yet we found no significant association of EL with rs7832552, rs1800795 or rs6552828 in any of the 3 cohorts. Further research is needed with larger cohorts of centenarians of different origin as well as with younger old people.

  15. Determination of IL-1B (rs16944) and IL-6 (rs1800796) genetic polymorphisms in IgA nephropathy in a northwest Chinese Han population.

    Science.gov (United States)

    Zhang, Daofa; Xie, Maowei; Yang, Xiaohong; Zhang, Yin; Su, Yan; Wang, Yanni; Huang, Haiyang; Han, Hui; Li, Wenning; Fu, Keying; Su, Huiluan; Xu, Wentan; Han, Yeguang; Wang, Ru; Zhang, Pei; Wu, Wei; Huang, Yun; Chen, Daojun; Jin, Tianbo; Wei, Jiali

    2017-09-22

    IgA nephropathy (IgAN) is the most common form of primary glomerulonephritis worldwide, but etiology and pathogenesis continue to be poorly understood. Polymorphisms in the cytokine genes may play a role in the etiology and pathogenesis of IgAN. The incidence of different between diverse ethnic groups suggested important genetic influences on its pathogenesis. We genotype 10 single nucleotide polymorphisms (SNPs) in IL-1B and IL-6 gene using Sequenom Mass-ARRAY technology from 417 IgAN patients and 463 healthy controls of the Chinese Han population. We evaluated these SNPs associated with IgAN utilising the chi-square tests and genetic model analysis. We identified that the minor alleles of rs16944 ("A"), rs1800796 ("G") in IL-1B, IL-6 were involved in an increasingly risk of IgAN in allelic model analysis, respectively. The rs16944 in IL-1B and rs1800796 in IL-6 were associated with 1.23-fold (95% CI, 1.02-1.48, P = 0.031) and 1.33-fold (95% CI, 1.11-1.66, P = 0.003) increases in the risk of developing IgAN, respectively. There was only rs1800796 still correlated with IgAN in the allelic model after adjustment by age and gender and the Bonferroni correction. In addition, Haplotype G rs1800796 A rs2069837 G rs2069840 ( P = 0.037) and G rs1800796 A rs2069837 C rs2069840 ( P = 0.042) in IL-6 were considered to be associated with increased IgAN risk. This study verified the IL-6, IL-1B genetic variants polymorphisms contributed to IgAN susceptibility in a Chinese Han population. Although we identified SNPs susceptibility, however, replication studies and functional research are required to confirm the genetic contribution in IgAN.

  16. PC interfacing using Centronics, RS232 and game ports

    CERN Document Server

    An, Pei

    1998-01-01

    The main links with your PC and the outside world are the centronic port, used for connecting the printer, the RS232 port, used for the mouse, and the games port for a joystick. This book explores how these input/output (I/O) ports can be put to use through a range of other interfacing applications. This is especially useful for laptop and palmtop PCs which cannot be fitted with internal I/O cards. A novel approach is taken by this book, combining the hardware through which the ports can be explored, and the software programming needed to carry out a range of experiments.Circuits are p

  17. A conceptual composite blanket design for the Tokamak type of thermonuclear reactor incorporating thermoelectric pumping of liquid lithium

    International Nuclear Information System (INIS)

    Dutta Gupta, P.B.

    1981-01-01

    The conceptual liquid lithium blanket design for the tokamak type of thermonuclear reactor put forward is a modification of the initial simple but novel design concept enunciated earlier that exploits the availability of suitably oriented magnetic fields and temperature gradients within the blanket to pump the liquid as has been shown feasible by laboratory model experiments. The modular construction of the blanket cells is retained but the earlier simple back to back double spiralling channel module is replaced by a composite unit of three radially nested layer-structures to optimise heat and tritium extraction from the blanket. The layer-structure at the first wall generates liquid lithium circulation by thermoelectric magnetohydrodynamic forces and the segregated double spiralling channels serve as inlet-outlet driving devices. The outermost layer-structure is cooled by helium. Liquid lithium in the intermediate layer-structure is pumped at a very slow rate. The choice of the relative dimensional proportions of the three layer-structure and the channel cross-section, material property and the spiralling contour is of critical importance for the design. This paper presents the design data for a conceptual design of such a blanket with a 5000 MW (th) rating. (author)

  18. Radiation assisted thermonuclear burn wave dynamics in heavy ion fast ignition of cylindrical deuterium-tritium fuel target

    International Nuclear Information System (INIS)

    Rehman, S.; Kouser, R.; Nazir, R.; Manzoor, Z.; Tasneem, G.; Jehan, N.; Nasim, M.H.; Salahuddin, M.

    2015-01-01

    Dynamics of thermonuclear burn wave propagation assisted by thermal radiation precursor in a heavy ion fast ignition of cylindrical deuterium-tritium (DT) fuel target are studied by two dimensional radiation hydrodynamic simulations using Multi-2D code. Thermal radiations, as they propagate ahead of the burn wave, suffer multiple reflections and preheat the fuel, are found to play a vital role in burn wave dynamics. After fuel ignition, the burn wave propagates in a steady state manner for some time. Multiple reflection and absorption of radiation at the fuel-tamper interface, fuel ablation and radial implosion driven by ablative shock and fast fusion rates on the fuel axis, at relatively later times, result into filamentary wave front. Strong pressure gradients are developed and sausage like structures behind the front are appeared. The situation leads to relatively reduced and non-uniform radial fuel burning and burn wave propagation. The fuel burning due to DD reaction is also taken into account and overall fusion energy and fusion power density, due to DT and DD reactions, during the burn wave propagation are determined as a function of time. (authors)

  19. Response of beryllium to severe thermal shocks -simulation of disruption and vertical displacement events in future thermonuclear devices

    Energy Technology Data Exchange (ETDEWEB)

    Linke, J.; Duwe, R.; Roedig, M.; Schuster, A. [Association Euratom-Forschungszentrum Juelich GmbH (Germany); Merola, M.; Qian, R.H.

    1998-01-01

    Beryllium will play an important role for plasma facing components in next step thermonuclear fusion devices such as ITER. In particular for the first wall beryllium will be used with an armor thickness of several millimeters. However, during plasma instabilities they will experience severe thermal shocks. Here plasma disruptions with deposited energy densities of several ten MJm{sup -2} are the most essential damaging mechanism. However, a signifant fraction of the incident energy will be absorbed by a dense cloud of ablation vapor, hence reducing the effective energy density at the beryllium surface to values in the order of 10 MJm{sup -2}. To investigate the material response to all these plasma instabilities thermal shock tests on small scale test coupons (disruption effects) and on actively cooled divertor modules (VDEs) have been performed in the electron beam test facility JUDITH at ITER relevant surface heat loads. These tests have been performed on different bulk beryllium grades and on plasma sprayed coatings; the influence of pulse duration, power density, and temperature effects has been investigated experimentally. Detailed in-situ diagnostics (for beam characterization, optical pyrometry etc.) and post mortem analyses (profilometry, metallography, optical and electron microscopy) have been applied to quantify the resulting material damage. 1D- and 2D models have developed to verify the experimental results obtained in the electron beam simulation experiments. (J.P.N.)

  20. Algorithm for study on the stressed-strained state of thermonuclear device vacuum chambers under dynamic loads

    International Nuclear Information System (INIS)

    Zhuravleva, A.M.; Litvinov, V.B.

    1982-01-01

    The problem of dynamic analysis of stressed-strained state of vacuum chambers is vital for large thermonuclear devices during the stall of the plasma-filament apd other tpansitional operation regimes when loading for a chamber are nonstationary. To plot a mathematical model the design of the vacuum chamber is discreted on the basis of the method of final elements. To approximate vacuum shell, a plate triangular element with 3 joint points and 5 parameters in the joint is used. It is obtained due to the unity of the bemded element and the element for the flat problem. To investigate nonstationary oscillations of vacuum chambers discreted on the basis of the method of final elements, it is suggested to use the numeric conversion of the Japlace transformation. On the basis of the algorithm suggested a program of numerical function conversion is developed. Test calculations have shown a good stability of the algorithm when selecting the values of transformation parameter in the range of lower intrinsic system frequencies. The advantage of the above method is in the fact that the time-structure shift function is found instantly in the form of the series for the whole time interval and does not require temporary steps, which bring about large expenses of counting time and error accumulation

  1. Modeling of secondary emission processes in the negative ion based electrostatic accelerator of the International Thermonuclear Experimental Reactor

    Directory of Open Access Journals (Sweden)

    G. Fubiani

    2008-01-01

    Full Text Available The negative ion electrostatic accelerator for the neutral beam injector of the International Thermonuclear Experimental Reactor (ITER is designed to deliver a negative deuterium current of 40 A at 1 MeV. Inside the accelerator there are several types of interactions that may create secondary particles. The dominating process originates from the single and double stripping of the accelerated negative ion by collision with the residual molecular deuterium gas (≃29% losses. The resulting secondary particles (positive ions, neutrals, and electrons are accelerated and deflected by the electric and magnetic fields inside the accelerator and may induce more secondaries after a likely impact with the accelerator grids. This chain of reactions is responsible for a non-negligible heat load on the grids and must be understood in detail. In this paper, we will provide a comprehensive summary of the physics involved in the process of secondary emission in a typical ITER-like negative ion electrostatic accelerator together with a precise description of the numerical method and approximations involved. As an example, the multiaperture-multigrid accelerator concept will be discussed.

  2. Analysis of the two accelerator concepts foreseen for the neutral beam injector of the International Thermonuclear Experimental Reactor

    Directory of Open Access Journals (Sweden)

    G. Fubiani

    2009-05-01

    Full Text Available Typical high-energy negative ion electrostatic accelerators such as the ones designed for fusion applications produce a significant amount of secondary particles. These particles may originate from coextracted electrons, which flow from the ion source, impacting the accelerator grids or as by-products of collisions between accelerated negative ions and the residual background gas, in the accelerator. Secondary emission particles may carry a non-negligible power and consequently must be precisely studied. The electrostatic-accelerator-Monte-Carlo-simulation code (EAMCC [G. Fubiani et al., Phys. Rev. ST Accel. Beams 11, 014202 (2008PRABFM1098-440210.1103/PhysRevSTAB.11.014202] was developed in order to provide a three-dimensional characterization of power and current deposition on all parts of the accelerator. The code includes all the relevant physics associated with secondary emission processes and consequently may be used as a tool for design improvement. In this paper, the two accelerator designs considered for the International Thermonuclear Experimental Reactor, that is, the multiaperture-multigrid and the single gap single aperture (SINGAP designs, are discussed and their predicted performances compared. Simulations have been compared with measurements on prototype accelerators of the SINGAP type. Reasonable agreement between EAMCC calculations and measurements of backstreaming ions and transmitted electrons was found.

  3. Analysis of quench-vent pressures for present design of ITER [International Thermonuclear Experimental Reactor] TF [toroidal field] coils

    International Nuclear Information System (INIS)

    Slack, D.S.

    1989-01-01

    The International Thermonuclear Experimental Reactor (ITER) is a new tokamak design project with joint participation from Japan, the European Community, the Union of the Soviet Union, and the United States. This paper examines the effects of a quench within the toroidal field (TF) coils based on current ITER design. It is a preliminary, rough analysis. Its intent is to assist ITER designers while more accurate computer codes are being developed and to provide a check against these more rigorous solutions. Rigorous solutions to the quench problem are very complex involving three-dimensional heat transfer, extreme changes in heat capacities and copper resistivity, and varying flow dynamics within the conductors. This analysis addresses all these factors in an approximate way. The result is much less accurate than a rigorous analysis. Results here could be in error as much as 30 to 40 percent. However, it is believed that this paper can still be very useful to the coil designer. Coil pressures and temperatures vs time into a quench are presented. Rate of helium vent, energy deposition in the coil, and depletion of magnetic stored energy are also presented. Peak pressures are high (about 43 MPa). This is due to the very long vent path length (446 m), small hydraulic diameters, and high current densities associated with ITER's cable-in-conduit design. The effects of these pressures as well as the ability of the coil to be self protecting during a quench are discussed. 3 refs., 3 figs., 1 tab

  4. Performance of cable-in-conduit conductors in ITER [International Thermonuclear Experimental Reactor] toroidal field coils with varying heat loads

    International Nuclear Information System (INIS)

    Kerns, J.A.; Wong, R.L.

    1989-01-01

    The toroidal field (TF) coils in the International Thermonuclear Experimental Reactor (ITER) will operate with varying heat loads generated by ac losses and nuclear heating. The total heat load is estimated to be 2 kW per TF coil under normal operation and can be higher for different operating scenarios. Ac losses are caused by ramping the poloidal field (PF) for plasma initiation, burn, and shutdown; nuclear heating results from neutrons that penetrate into the coil past the shield. Present methods to reduce or eliminate these losses lead to larger and more expensive machines, which are unacceptable with today's budget constraints. A suitable solution is to design superconductors that operate with high heat loads. The cable-in-conduit conductor (CICC) can operate with high heat loads. One CICC design is analyzed for its thermal performance using two computer codes developed at LLNL. One code calculates the steady state flow conditions along the flow path, while the other calculates the transient conditions in the flow. We have used these codes to analyze the superconductor performance during the burn phase of the ITER plasma. The results of these analyses give insight to the choice of flow rate on superconductor performance. 4 refs., 5 figs

  5. Thermo-mechanical analysis of an acceleration grid for the international thermonuclear experimental reactor-neutral beam injection system

    International Nuclear Information System (INIS)

    Fujiwara, Yukio; Hanada, Masaya; Okumura, Yoshikazu; Suzuki, Satoshi; Watanabe, Kazuhiro

    2001-01-01

    In the engineering design of a negative-ion beam source for a high-power neutral beam injection (NBI) system, one of the most important issues is thermo-mechanical design of acceleration grids for producing several tens of MW ion beams. An acceleration grid for the international thermonuclear experimental reactor-neutral beam injection (ITER-NBI) system will be subjected to the heat loading as high as 1.5 MW. In the present paper, thermo-mechanical characteristics of the acceleration grid for the ITER-NBI system were analyzed. Numerical simulation indicated that maximum aperture-axis displacement of the acceleration grid due to thermal expansion would be about 0.7 mm for the heat loading of 1.5 MW. From the thin lens theory of beam optics, beamlet deflection angle by the aperture-axis displacement was estimated to be about 2 mrad, which is within the requirement of the engineering design of the ITER-NBI system. Numerical simulation also indicated that no melting on the acceleration grid would occur for a heat loading of 1.5 MW, while local plastic deformation would happen. To avoid the plastic deformation, it is necessary to reduce the heat loading onto the acceleration grid to less than 1 MW

  6. Polymorphism of rs7688672 and rs10033237 in cGKII/PRKG2 and gout susceptibility of Han population in northern China.

    Science.gov (United States)

    Guo, Min; Cheng, Zhifeng; Li, Changgui; Li, Shanshan; Li, Ming; Wang, Mingli; Xu, Jinmei; Tang, Yingying; Wang, Yujing; Qiu, Wenli; Liu, Xiaomin

    2015-05-10

    Gout is a genetic or acquired metabolic disease caused by increase of uric acid synthesis resulted from purine metabolic abnormalities. Whether cGMP-dependent protein kinase 2 (cGKII/PRKG2) is correlated with gout remains controversial. The objective of the present study was to investigate whether there is a correlation between polymorphism of cGKII/PRKG2 and gout susceptibility of Han population in northern China. Four hundred and five male patients with gout in the case group and 429 controls in the control group were collected from the Department of Endocrinology and Metabolic Disease, the Fourth Affiliated Hospital of Harbin Medical University. A case-control study method was used to study the correlation between cGKII/PRKG2 polymorphism rs7688672 and rs10033237 and gout susceptibility. The genotype frequencies of rs7688672 and rs10033237 polymorphisms of cGKII/PRKG2 in the case group and the control group both were in accordance with Hardy-Weinberg equilibrium. There were significant differences of rs10033237 in the allele frequencies and genotype distributions (Pgout. Combined mutation sites AA(*) from rs7688672 and rs10033237 were negatively correlated with gout susceptibility, whereas haplotype GG(*) was positively correlated with gout susceptibility. In conclusion, patients with rs10033237 polymorphism of cGKII/PRKG2 gene are more likely to suffer from gout. With regard to haplotypes of rs10033237 and rs7688672, both AA(*) and GG(*) are related to gout. AA(*) is a gout susceptible gene, whereas GG(*) is a protective gene. Copyright © 2015 Elsevier B.V. All rights reserved.

  7. STAT4 rs7574865 G/T and PTPN22 rs2488457 G/C polymorphisms influence the risk of developing juvenile idiopathic arthritis in Han Chinese patients.

    Science.gov (United States)

    Fan, Zhi-Dan; Wang, Fei-Fei; Huang, Hui; Huang, Na; Ma, Hui-Hui; Guo, Yi-Hong; Zhang, Ya-Yuan; Qian, Xiao-Qing; Yu, Hai-Guo

    2015-01-01

    Juvenile idiopathic arthritis (JIA) is a common autoimmune disease characterized by environmental influences along with several predisposing genes in the pathogenesis. The protein tyrosine phosphatase nonreceptor 22 (PTPN22) and signal transducer and activator of transcription factor 4 (STAT4) have been recognized as susceptibility genes for numerous autoimmune diseases. Associations of STAT4 rs7574865 G/T and PTPN22 (rs2488457 G/C and rs2476601 C/T) polymorphisms with JIA have repeatedly been replicated in several Caucasian populations. The aim of this study was to investigate the influence of three polymorphisms mentioned above on the risk of developing JIA in Han Chinese patients. Genotyping was performed on a total of 137 Chinese patients with JIA (JIA group) and 150 sex and age frequency-matched healthy volunteers (Control group). The single-nucleotide polymorphisms (SNP) were determined by using direct sequencing of PCR-amplified products. There were significant differences of PTPN22 rs2488457 G/C and STAT4 rs7574865 G/T polymorphisms between both groups. However, no significant difference was observed in distribution frequencies of PTPN22 rs2476601 polymorphism. The association with the PTPN22 rs2488457 G/C polymorphism remained significant in the stratifications by age at onset, ANA status, splenomegaly, lymphadenectasis and involvement joints. As with the STAT4 rs7574865 G/T polymorphisms, the enthesitis-related arthritis and presence of hepatomegaly had strong effect on the association. Our data strengthen STAT4 rs7574865 G/T and PTPN22 rs2488457 G/C polymorphisms as susceptibility factors for JIA.

  8. STAT4 rs7574865 G/T and PTPN22 rs2488457 G/C polymorphisms influence the risk of developing juvenile idiopathic arthritis in Han Chinese patients.

    Directory of Open Access Journals (Sweden)

    Zhi-Dan Fan

    Full Text Available Juvenile idiopathic arthritis (JIA is a common autoimmune disease characterized by environmental influences along with several predisposing genes in the pathogenesis. The protein tyrosine phosphatase nonreceptor 22 (PTPN22 and signal transducer and activator of transcription factor 4 (STAT4 have been recognized as susceptibility genes for numerous autoimmune diseases. Associations of STAT4 rs7574865 G/T and PTPN22 (rs2488457 G/C and rs2476601 C/T polymorphisms with JIA have repeatedly been replicated in several Caucasian populations. The aim of this study was to investigate the influence of three polymorphisms mentioned above on the risk of developing JIA in Han Chinese patients. Genotyping was performed on a total of 137 Chinese patients with JIA (JIA group and 150 sex and age frequency-matched healthy volunteers (Control group. The single-nucleotide polymorphisms (SNP were determined by using direct sequencing of PCR-amplified products. There were significant differences of PTPN22 rs2488457 G/C and STAT4 rs7574865 G/T polymorphisms between both groups. However, no significant difference was observed in distribution frequencies of PTPN22 rs2476601 polymorphism. The association with the PTPN22 rs2488457 G/C polymorphism remained significant in the stratifications by age at onset, ANA status, splenomegaly, lymphadenectasis and involvement joints. As with the STAT4 rs7574865 G/T polymorphisms, the enthesitis-related arthritis and presence of hepatomegaly had strong effect on the association. Our data strengthen STAT4 rs7574865 G/T and PTPN22 rs2488457 G/C polymorphisms as susceptibility factors for JIA.

  9. Research programme on controlled thermonuclear fusion - Synthesis report 2010; Programme de recherche Fusion thermonucleaire controlee. Rapport de synthese 2010

    Energy Technology Data Exchange (ETDEWEB)

    Vaucher, C. [Secretariat d' Etat a l' education et a la recherche, Berne (Switzerland); Tran, M. Q.; Villard, L. [Swiss Federal Institute of Technology (EPFL), Lausanne (Switzerland); Marot, L. [University of Basel, Basel (Switzerland)

    2011-07-01

    Since 1978, research on thermonuclear fusion in Switzerland is closely related to the research programme of the European Atomic Energy Community (EURATOM). The Swiss projects tackle aspects of plasma physics and fusion technology. Switzerland participates to the construction and operation of the Joint European Torus (JET). The International Thermonuclear Experimental Reactor (ITER) is being built; the first plasma is expected in 2019. The 'Centre de Recherches en Physique des Plasmas' (CRPP) of the EPFL participates to EURATOM scientific and technological projects in magnetic confinement physics, through an experimental contribution (the Variable Configuration Tokamak, TCV) and theoretical studies. Thanks to the large flexibility of the TCV design and operation modus, plasmas of different shapes can be created and controlled, what is a very useful option to verify numerical simulation results. Besides, the injection of millimetre waves allows directing the injected power according to specific profiles. A configuration of type 'snowflakes' could be created, reducing the power deposition at the edge of the plasma. Theoretical studies on turbulence have improved the plasma stability in the TCV. For the first time in the world, TCV could reach a stable plasma, the plasma current being generated using the so-called 'bootstrap' phenomenon. Besides turbulence, studies were focused on heat and particle transport in tokamaks, on an analysis of the equilibrium and magneto-hydrodynamic stability of tokamaks and stellarators, on the application of radiofrequency waves and on the optimization of new confinement configurations. Experiments in the JET facility confirmed the numerical results of theoretical simulations. The TORPEX facility, which is simpler than TCV, allows high space-temporal resolution measurements for the study of turbulences and plasma threads ('blobs'). At the Paul Scherrer Institute (PSI), research topics include

  10. Research programme on controlled thermonuclear fusion. Synthesis report 2011; Programme de recherche Fusion thermonucleaire controlee. Rapport de synthese 2011

    Energy Technology Data Exchange (ETDEWEB)

    Vaucher, C. [Secretariat d' Etat a l' education et a la recherche, Berne (Switzerland); Tran, M. Q.; Villard, L. [Swiss Federal Institute of Technology (EPFL), Lausanne (Switzerland); Marot, L. [University of Basel, Basel (Switzerland)

    2012-07-01

    Since 1978, research on thermonuclear fusion in Switzerland is closely related to the research programme of the European Atomic Energy Community (EURATOM). The Swiss projects tackle aspects of plasma physics and fusion technology. Switzerland participates to the construction and operation of the Joint European Torus (JET), which started operation again in 2011. The International Thermonuclear Experimental Reactor (ITER) is the last step before DEMO, a prototype fusion reactor able to deliver electricity and demonstrate the economic viability of fusion energy. The 'Centre de Recherches en Physique des Plasmas' (CRPP) of the EPFL went on with its participation to the scientific and technological programme of EURATOM. Researches are carried out essentially on 2 sites: (i) at EPFL, where topics dealt with include the physics of magnetic confinement studied using the Variable Configuration Tokamak (TCV), the basic experiment TORPEX, theory and numerical modelling, and the technology of plasma heating and current generation by hyper-frequency waves; (ii) at the Paul Scherrer Institute (PSI), where activities are devoted to superconductivity and structure materials. Thanks to the large flexibility of the TCV design and operation modus, plasmas of different shapes can be created and controlled, what is a very useful option to verify numerical simulation results. Besides, the injection of millimetre waves allows directing the injected power according to specific profiles. In the TCV it could be demonstrated for the first time that the injection of Electronic Cyclotronic Heating (ECH) waves is able to double the frequency of so-called 'Edge Localized Modes' (ELM), reducing by a factor of 2 the energy expelled by each ELM. In particular, it was possible to considerably reduce the statistical dispersion of the repetition frequency of ELM, and to avoid the appearance of gigantic ELM that are particularly harmful for reactor operation. The effect of plasma

  11. X-Ray Reflection and an Exceptionally Long Thermonuclear Helium Burst from IGR J17062-6143

    Energy Technology Data Exchange (ETDEWEB)

    Keek, L.; Strohmayer, T. E. [X-ray Astrophysics Laboratory, Astrophysics Science Division, NASA/GSFC, Greenbelt, MD 20771 (United States); Iwakiri, W.; Serino, M. [MAXI team, RIKEN, 2-1 Hirosawa, Wako, Saitama 351-0198 (Japan); Ballantyne, D. R. [Center for Relativistic Astrophysics, School of Physics, Georgia Institute of Technology, 837 State Street, Atlanta, GA 30332-0430 (United States); Zand, J. J. M. in’t, E-mail: laurens.keek@nasa.gov [SRON Netherlands Institute for Space Research, Sorbonnelaan 2, 3584 CA Utrecht (Netherlands)

    2017-02-10

    Thermonuclear X-ray bursts from accreting neutron stars power brief but strong irradiation of their surroundings, providing a unique way to study accretion physics. We analyze MAXI /Gas Slit Camera and Swift /XRT spectra of a day-long flash observed from IGR J17062-6143 in 2015. It is a rare case of recurring bursts at a low accretion luminosity of 0.15% Eddington. Spectra from MAXI , Chandra , and NuSTAR observations taken between the 2015 burst and the previous one in 2012 are used to determine the accretion column. We find it to be consistent with the burst ignition column of 5×10{sup 10} g cm{sup −2}, which indicates that it is likely powered by burning in a deep helium layer. The burst flux is observed for over a day, and decays as a straight power law: F ∝ t {sup −1.15}. The burst and persistent spectra are well described by thermal emission from the neutron star, Comptonization of this emission in a hot optically thin medium surrounding the star, and reflection off the photoionized accretion disk. At the burst peak, the Comptonized component disappears, when the burst may dissipate the Comptonizing gas, and it returns in the burst tail. The reflection signal suggests that the inner disk is truncated at ∼10{sup 2} gravitational radii before the burst, but may move closer to the star during the burst. At the end of the burst, the flux drops below the burst cooling trend for 2 days, before returning to the pre-burst level.

  12. NICER Detection of Strong Photospheric Expansion during a Thermonuclear X-Ray Burst from 4U 1820–30

    Science.gov (United States)

    Keek, L.; Arzoumanian, Z.; Chakrabarty, D.; Chenevez, J.; Gendreau, K. C.; Guillot, S.; Güver, T.; Homan, J.; Jaisawal, G. K.; LaMarr, B.; Lamb, F. K.; Mahmoodifar, S.; Markwardt, C. B.; Okajima, T.; Strohmayer, T. E.; in ’t Zand, J. J. M.

    2018-04-01

    The Neutron Star Interior Composition Explorer (NICER) on the International Space Station (ISS) observed strong photospheric expansion of the neutron star in 4U 1820–30 during a Type I X-ray burst. A thermonuclear helium flash in the star’s envelope powered a burst that reached the Eddington limit. Radiation pressure pushed the photosphere out to ∼200 km, while the blackbody temperature dropped to 0.45 keV. Previous observations of similar bursts were performed with instruments that are sensitive only above 3 keV, and the burst signal was weak at low temperatures. NICER's 0.2–12 keV passband enables the first complete detailed observation of strong expansion bursts. The strong expansion lasted only 0.6 s, and was followed by moderate expansion with a 20 km apparent radius, before the photosphere finally settled back down at 3 s after the burst onset. In addition to thermal emission from the neutron star, the NICER spectra reveal a second component that is well fit by optically thick Comptonization. During the strong expansion, this component is six times brighter than prior to the burst, and it accounts for 71% of the flux. In the moderate expansion phase, the Comptonization flux drops, while the thermal component brightens, and the total flux remains constant at the Eddington limit. We speculate that the thermal emission is reprocessed in the accretion environment to form the Comptonization component, and that changes in the covering fraction of the star explain the evolution of the relative contributions to the total flux.

  13. Charged-particle thermonuclear reaction rates: II. Tables and graphs of reaction rates and probability density functions

    International Nuclear Information System (INIS)

    Iliadis, C.; Longland, R.; Champagne, A.E.; Coc, A.; Fitzgerald, R.

    2010-01-01

    Numerical values of charged-particle thermonuclear reaction rates for nuclei in the A=14 to 40 region are tabulated. The results are obtained using a method, based on Monte Carlo techniques, that has been described in the preceding paper of this issue (Paper I). We present a low rate, median rate and high rate which correspond to the 0.16, 0.50 and 0.84 quantiles, respectively, of the cumulative reaction rate distribution. The meaning of these quantities is in general different from the commonly reported, but statistically meaningless expressions, 'lower limit', 'nominal value' and 'upper limit' of the total reaction rate. In addition, we approximate the Monte Carlo probability density function of the total reaction rate by a lognormal distribution and tabulate the lognormal parameters μ and σ at each temperature. We also provide a quantitative measure (Anderson-Darling test statistic) for the reliability of the lognormal approximation. The user can implement the approximate lognormal reaction rate probability density functions directly in a stellar model code for studies of stellar energy generation and nucleosynthesis. For each reaction, the Monte Carlo reaction rate probability density functions, together with their lognormal approximations, are displayed graphically for selected temperatures in order to provide a visual impression. Our new reaction rates are appropriate for bare nuclei in the laboratory. The nuclear physics input used to derive our reaction rates is presented in the subsequent paper of this issue (Paper III). In the fourth paper of this issue (Paper IV) we compare our new reaction rates to previous results.

  14. CRSEC: a general purpose Hauser--Feshbach code for the calculation of nuclear cross-sections and thermonuclear reaction rates

    International Nuclear Information System (INIS)

    Woosley, S.; Fowler, W.A.

    1977-09-01

    CRSEC is a FORTRAN IV computer code designed for the efficient calculation of average nuclear cross sections in situations where a statistical theory of nuclear reactions is applicable and where compound nuclear formation is the dominant reaction mechanism. This code generates cross sections of roughly factor of 2 accuracy for incident particle energies in the range of 10 keV to 10 MeV for most target nuclei from magnesium to bismuth. Exceptions usually involve reactions that enter the compound nucleus at such a low energy that fewer than 10 levels are present in the ''energy window of interest.'' The incident particle must be a neutron, proton, or alpha particle, and only binary reactions resulting in the emission of a single n, p, α, or γ (cascade) are calculated. CRSEC is quite fast, a complete calculation of 12 different reactions over a grid of roughly 150 energy points and the generation of Maxwellian averaged rates taking about 30 seconds of CDC7600 time. Also the semi-empirical parameterization of nuclear properties contained in CRSEC is very general. Greater accuracy may be obtained, however, by furnishing specific low-lying excited states, level density parameterization, and nuclear strength functions. A more general version of CRSEC, called CRSECI, is available that conserves isospin properly in all reactions and allows the user to specify a given degree of isospin mixing in the highly excited states of the compound nucleus. Besides the cross section as a function of center-of-mass energy, CRSEC also generates the Maxwell--Boltzmann averaged thermonuclear reaction rate and temperature dependent nuclear partition function for a grid of temperatures from 10 8 to 10 10 0 K. Sections of this report describe in greater detail the physics employed in CRSEC and how to use the code. 2 tables

  15. Recycling, inventory and permeation of hydrogen isotopes and helium in the first wall of a thermonuclear fusion reactor

    International Nuclear Information System (INIS)

    Gervasini, G.; Reiter, F.

    1989-01-01

    The work was divided into three parts. The first part, which is theoretical, examines the behaviour of hydrogen in metals. After an introduction on the presence of hydrogen isotopes in fusion reactors, the main phenomena connected with hydrogen-metal interaction are summarised: solubility, diffusivity and trapping in material defects. The metal temperature is highlighted as the main parameter in the description of the phenomena. The second part of the work, also theoretical, concerns the interaction between helium and metals. We have tried as much as possible to show analogies and differences in the comparisons of the behaviour of hydrogen. The main types of damage caused by helium in metallic structures, which are the most important consequence of helium-metal interaction, were summarised. The characteristics of helium were treated in greater depth than those of hydrogen, because the latter are very well known. Also, there is a vast literature on the hydrogen-metal interaction. In the third and last part of the work a model was identified which allows the simulation of the evolution of a system formed from a metal in which hydrogen and helium isotopes have been introduced. A system of algebraic-differential equations was used to study the temporal evolution of the concentrations, the recycling, the inventory and the permeation of tritium and helium considering that these atoms diffuse in the metallic lattice and remain trapped in the vacancies created inside the metal by the bombardment of the neutrons from the fusion reactions. For the numerical simulation a series of data intended to represent the situation inside a thermonuclear reactor as precisely as possible were used for the numerical simulation. Analysis of the system was preceded by the analytical resolution of the steady state equations so that they could be compared with the simulation results

  16. Association of TNF-α rs1799964 and IL-1β rs16944 polymorphisms with multiple system atrophy in Chinese Han population.

    Science.gov (United States)

    Zhou, Xin; Wang, Chunrong; Chen, Zhao; Peng, Yun; Peng, Huirong; Hou, Xuan; Ye, Wei; Qiu, Rong; Xia, Kun; Tang, Beisha; Jiang, Hong

    2018-01-07

    Recent evidence suggested that several single nucleotide polymorphisms (SNPs) of inflammation-related genes (TNF-α rs1799964, IL-1α rs1800587, IL-1β rs16944, IL-8 rs4073, ICAM-1 rs5498) were associated with multiple system atrophy (MSA). Herein, we conducted this case-control study to evaluate the possible correlation between the five SNPs related to inflammation and MSA in Chinese Han population. We recruited 154 sporadic patients with MSA and 223 health controls in this study. All subjects were genotyped for the five SNPs using polymerase chain reaction amplification and Sanger sequencing. TNF-α rs1799964, genotype distribution and minor allele frequency (MAF) showed significant differences between patients and controls, which might illustrate the minor allele C may increase the risk for MSA (genotype, P = 0.006, OR = 1.245, 95% CI = [1.066-1.455]; allele, P = 0.001, OR = 1.887, 95% CI = [1.303-2.733]). For rs16944, patients carrying AA genotype showed a nearly 5-year early age at onset (AAO) than GG genotype (50.52 ± 7.45 years vs. 54.90 ± 7.21 years, P = 0.037). No differences were found in genotype distribution and MAF of the five SNPs between patients with MSA with predominant cerebellar ataxia (MSA-C) and with predominant Parkinsonism (MSA-P). Our study suggests that rs1799964 of TNF-α may act as a risk factor for MSA and the IL-1β rs16944 might be a genetic factor that modifies the AAO in MSA. Moreover, the exact mechanism of neuroinflammatory response in MSA deserves further exploration.

  17. Vad ersätter företagets avbrottsförsäkring?

    OpenAIRE

    Rosenqvist, Felix

    2010-01-01

    I arbetet redogörs för hur en avbrottsförsäkring är uppbyggd och hur ersättningen räknas ut i praktiken. I teoridelen behandlas försäkringshistoria, de frivilliga skadeförsäkringarna och mera djupgående avbrottsförsäkringen. Skadehanteringsprocessen beskrivs också i teoridelen. För att åskådliggöra ämnet har själva resultatredovisnigen förverkligats genom en fiktiv fallstudie. Detta för att göra det enklare för läsaren att förstå hur avbrottsförsäkringen fungerar i praktiken...

  18. The obesity-associated polymorphisms FTO rs9939609 and MC4R rs17782313 and endometrial cancer risk in non-Hispanic white women.

    Directory of Open Access Journals (Sweden)

    Galina Lurie

    2011-02-01

    Full Text Available Overweight and obesity are strongly associated with endometrial cancer. Several independent genome-wide association studies recently identified two common polymorphisms, FTO rs9939609 and MC4R rs17782313, that are linked to increased body weight and obesity. We examined the association of FTO rs9939609 and MC4R rs17782313 with endometrial cancer risk in a pooled analysis of nine case-control studies within the Epidemiology of Endometrial Cancer Consortium (E2C2. This analysis included 3601 non-Hispanic white women with histologically-confirmed endometrial carcinoma and 5275 frequency-matched controls. Unconditional logistic regression models were used to assess the relation of FTO rs9939609 and MC4R rs17782313 genotypes to the risk of endometrial cancer. Among control women, both the FTO rs9939609 A and MC4R rs17782313 C alleles were associated with a 16% increased risk of being overweight (p = 0.001 and p = 0.004, respectively. In case-control analyses, carriers of the FTO rs9939609 AA genotype were at increased risk of endometrial carcinoma compared to women with the TT genotype [odds ratio (OR  = 1.17; 95% confidence interval (CI: 1.03-1.32, p = 0.01]. However, this association was no longer apparent after adjusting for body mass index (BMI, suggesting mediation of the gene-disease effect through body weight. The MC4R rs17782313 polymorphism was not related to endometrial cancer risk (per allele OR = 0.98; 95% CI: 0.91-1.06; p = 0.68. FTO rs9939609 is a susceptibility marker for white non-Hispanic women at higher risk of endometrial cancer. Although FTO rs9939609 alone might have limited clinical or public health significance for identifying women at high risk for endometrial cancer beyond that of excess body weight, further investigation of obesity-related genetic markers might help to identify the pathways that influence endometrial carcinogenesis.

  19. NACRE II: an update of the NACRE compilation of charged-particle-induced thermonuclear reaction rates for nuclei with mass number A<16

    International Nuclear Information System (INIS)

    Xu, Y.; Takahashi, K.; Goriely, S.; Arnould, M.; Ohta, M.; Utsunomiya, H.

    2013-01-01

    An update of the NACRE compilation [3] is presented. This new compilation, referred to as NACRE II, reports thermonuclear reaction rates for 34 charged-particle induced, two-body exoergic reactions on nuclides with mass number A 6 ≲T⩽10 10 K range. Along with the ‘adopted’ rates, their low and high limits are provided. The new rates are available in electronic form as part of the Brussels Library (BRUSLIB) of nuclear data. The NACRE II rates also supersede the previous NACRE rates in the Nuclear Network Generator (NETGEN) for astrophysics. [ (http://www.astro.ulb.ac.be/databases.html)

  20. Design of a Fast Neutral He Beam System for Feasibility Study of Charge-Exchange Alpha-Particle Diagnostics in a Thermonuclear Fusion Reactor

    CERN Document Server

    Shinto, Katsuhiro; Kitajima, Sumio; Kiyama, Satoru; Nishiura, Masaki; Sasao, Mamiko; Sugawara, Hiroshi; Takenaga, Mahoko; Takeuchi, Shu; Wada, Motoi

    2005-01-01

    For alpha-particle diagnostics in a thermonuclear fusion reactor, neutralization using a fast (~2 MeV) neutral He beam produced by the spontaneous electron detachment of a He- is considered most promising. However, the beam transport of produced fast neutral He has not been studied, because of difficulty for producing high-brightness He- beam. Double-charge-exchange He- sources and simple beam transport systems were developed and their results were reported in the PAC99* and other papers.** To accelerate an intense He- beam and verify the production of the fast neutral He beam, a new test stand has been designed. It consists of a multi-cusp He+

  1. A Combination of CD28 (rs1980422 and IRF5 (rs10488631 Polymorphisms Is Associated with Seropositivity in Rheumatoid Arthritis: A Case Control Study.

    Directory of Open Access Journals (Sweden)

    Lucia Vernerova

    Full Text Available The aim of the study was to analyse genetic architecture of RA by utilizing multiparametric statistical methods such as linear discriminant analysis (LDA and redundancy analysis (RDA.A total of 1393 volunteers, 499 patients with RA and 894 healthy controls were included in the study. The presence of shared epitope (SE in HLA-DRB1 and 11 SNPs (PTPN22 C/T (rs2476601, STAT4 G/T (rs7574865, CTLA4 A/G (rs3087243, TRAF1/C5 A/G (rs3761847, IRF5 T/C (rs10488631, TNFAIP3 C/T (rs5029937, AFF3 A/T (rs11676922, PADI4 C/T (rs2240340, CD28 T/C (rs1980422, CSK G/A (rs34933034 and FCGR3A A/C (rs396991, rheumatoid factor (RF, anti-citrullinated protein antibodies (ACPA and clinical status was analysed using the LDA and RDA.HLA-DRB1, PTPN22, STAT4, IRF5 and PADI4 significantly discriminated between RA patients and healthy controls in LDA. The correlation between RA diagnosis and the explanatory variables in the model was 0.328 (Trace = 0.107; F = 13.715; P = 0.0002. The risk variants of IRF5 and CD28 genes were found to be common determinants for seropositivity in RDA, while positivity of RF alone was associated with the CTLA4 risk variant in heterozygous form. The correlation between serologic status and genetic determinants on the 1st ordinal axis was 0.468, and 0.145 on the 2nd one (Trace = 0.179; F = 6.135; P = 0.001. The risk alleles in AFF3 gene together with the presence of ACPA were associated with higher clinical severity of RA.The association among multiple risk variants related to T cell receptor signalling with seropositivity may play an important role in distinct clinical phenotypes of RA. Our study demonstrates that multiparametric analyses represent a powerful tool for investigation of mutual relationships of potential risk factors in complex diseases such as RA.

  2. A Combination of CD28 (rs1980422) and IRF5 (rs10488631) Polymorphisms Is Associated with Seropositivity in Rheumatoid Arthritis: A Case Control Study.

    Science.gov (United States)

    Vernerova, Lucia; Spoutil, Frantisek; Vlcek, Miroslav; Krskova, Katarina; Penesova, Adela; Meskova, Milada; Marko, Andrea; Raslova, Katarina; Vohnout, Branislav; Rovensky, Jozef; Killinger, Zdenko; Jochmanova, Ivana; Lazurova, Ivica; Steiner, Guenter; Smolen, Josef; Imrich, Richard

    2016-01-01

    The aim of the study was to analyse genetic architecture of RA by utilizing multiparametric statistical methods such as linear discriminant analysis (LDA) and redundancy analysis (RDA). A total of 1393 volunteers, 499 patients with RA and 894 healthy controls were included in the study. The presence of shared epitope (SE) in HLA-DRB1 and 11 SNPs (PTPN22 C/T (rs2476601), STAT4 G/T (rs7574865), CTLA4 A/G (rs3087243), TRAF1/C5 A/G (rs3761847), IRF5 T/C (rs10488631), TNFAIP3 C/T (rs5029937), AFF3 A/T (rs11676922), PADI4 C/T (rs2240340), CD28 T/C (rs1980422), CSK G/A (rs34933034) and FCGR3A A/C (rs396991), rheumatoid factor (RF), anti-citrullinated protein antibodies (ACPA) and clinical status was analysed using the LDA and RDA. HLA-DRB1, PTPN22, STAT4, IRF5 and PADI4 significantly discriminated between RA patients and healthy controls in LDA. The correlation between RA diagnosis and the explanatory variables in the model was 0.328 (Trace = 0.107; F = 13.715; P = 0.0002). The risk variants of IRF5 and CD28 genes were found to be common determinants for seropositivity in RDA, while positivity of RF alone was associated with the CTLA4 risk variant in heterozygous form. The correlation between serologic status and genetic determinants on the 1st ordinal axis was 0.468, and 0.145 on the 2nd one (Trace = 0.179; F = 6.135; P = 0.001). The risk alleles in AFF3 gene together with the presence of ACPA were associated with higher clinical severity of RA. The association among multiple risk variants related to T cell receptor signalling with seropositivity may play an important role in distinct clinical phenotypes of RA. Our study demonstrates that multiparametric analyses represent a powerful tool for investigation of mutual relationships of potential risk factors in complex diseases such as RA.

  3. RsComm User Manual. Data system for the control of continuous recording measuring instruments (monitors); RsComm brukermanual. Datasystem for kontroll av kontinuerlig registrerende maaleinstrumenter (monitorer)

    Energy Technology Data Exchange (ETDEWEB)

    Marsteen, L.

    1996-02-01

    Norwegian Institute for Air Research (NILU) has, as a part of the quality control systems, developed an automatic system of data recording. This report describes the installation and use of the RsComm software. Using RsComm and a NILU data recorder it is possible to run system tests on air quality analyzers via a telephone line. Test reports are generated. 17 figs.

  4. Polymorphisms of transforming growth factor beta 1 (RS#1800468 and RS#1800471) and esophageal squamous cell carcinoma among Zhuangese population, China.

    Science.gov (United States)

    Tang, Ren-Guang; Huang, Yong-Zhi; Yao, Li-Min; Xiao, Jian; Lu, Chuan; Yu, Qian

    2013-01-01

    Epidemiological evidence has shown two polymorphisms (namely RS#1800468G>A and RS#1800471G>C) of transforming growth factor-beta 1 (TGF-β1) gene may be involved in the cancer development. However, their role in the carcinogenic process of esophageal squamous cell carcinoma (ESCC) has been less well elaborated. We conducted a hospital-based case-control study including 391 ESCC cases and 508 controls without any evidence of tumors to evaluate the association between these two polymorphisms and ESCC risk and prognosis for Zhuangese population by means of polymerase chain reaction-restriction fragment length polymorphism (PCR-RFLP) and amplification refractory mutation system (ARMS)-PCR techniques. We found that individuals with the genotypes with RS#1800471 C allele (namely RS#1800471-GC or -CC) had an increased risk of ESCC than those without above genotypes (namely RS#1800471-GG, adjusted odds ratio 3.26 and 5.65, respectively). Further stratification analysis showed that this polymorphism was correlated with tumor histological grades and TNM (tumor, node, and metastasis) stage, and modified the serum levels of TGF-β1. Additionally, RS#1800471 polymorphism affected ESCC prognosis (hazard ratio, 3.40), especially under high serum levels of TGF-β1 conditions. However, RS#1800468 polymorphism was not significantly related to ESCC risk. These findings indicated that TGF-β1 RS#1800471G>C polymorphism may be a genetic modifier for developing ESCC in Zhuangese population. Copyright © 2012 Elsevier B.V. All rights reserved.

  5. Polymorphic Variants rs3088442 and rs2292334 in the Organic Cation Transporter 3 (OCT3) Gene and Susceptibility Against Type 2 Diabetes: Role of their Interaction.

    Science.gov (United States)

    Mahrooz, Abdolkarim; Alizadeh, Ahad; Hashemi-Soteh, Mohammad Bagher; Ghaffari-Cherati, Maryam; Hosseyni-Talei, Seyyedeh Raheleh

    2017-02-01

    In this study, we investigated whether two common variants (rs3088442G>A and rs2292334G>A) in the organic cation transporter 3 (OCT3) gene, a high-capacity transporter widely expressed in various tissues, affect susceptibility to type 2 diabetes (T2D) in patients newly diagnosed with T2D. We performed a study with 150 newly diagnosed patients with T2D and 152 controls. The genetic analyses were performed using the restricted fragment length polymorphism (RFLP) after PCR amplification. For the rs3088442G>A variant, A allele carriers had a significantly lower odds ratio (OR) vs. GG homozygotes in the BMI A variant was associated with a decreased risk of T2D (OR = 0.016, p A in the 3'-untranslated region of the OCT3 gene in susceptibility to T2D, and that the protective role is maintained in the presence of risky alleles of the variant rs2292334G>A. The association of the A allele of rs3088442G>A with T2D become weaker in obese people than that of non-obese. If confirmed in other populations, the rs3088442G>A variant as a genetic marker may potentially assist in the identification of individuals at an increased risk of T2D. Copyright © 2017 IMSS. Published by Elsevier Inc. All rights reserved.

  6. Preparation and characterization of carbons for the retention of halogens in the condenser vacuum system of a thermonuclear plant

    International Nuclear Information System (INIS)

    Roman, S.; Gonzalez, J.F.; Ganan, J.; Sabio, E.; Gonzalez-Garcia, C.M.; Ramiro, A.; Mangut, V.

    2006-01-01

    Activated carbons were prepared by air and carbon dioxide activation, from almond tree pruning, with the aim of obtaining carbons that reproduce the textural and mechanical properties of the carbons currently used in the filtering system of the condenser vacuum installation of a Thermonuclear Plant (CNA; Central Nuclear de Almaraz in Caceres, Spain), produced from coconut shell. The variables studied in non-catalytic gasification series with air were the temperature (215-270 deg. C) and the time (1-16 h) and the influence of the addition of one catalyst (Co) and the time (1-2 h) in catalytic gasification. In the case of activation with CO 2 , the influence of the temperature (700-950 deg. C) and the time (1-8 h) was studied. The resulting carbons were characterized in terms of their BET surface, porosity, and pore size distribution. The N 2 adsorption isotherms at 77 K for both series showed a type I behaviour, typical of microporous materials. The isotherms showed that with both gasificant agents the temperature rise produced an increase in the carbon porosity. With regards to the activation time, a positive effect on the N 2 adsorbed volume on the carbons was observed. The best carbons of each series, as well as the CNA (carbon currently used in the CNA), were characterized by mercury porosimetry and iodine solution adsorption isotherms. The results obtained allowed to state that several of the carbons produced had characteristics similar to the carbon that is target of reproduction (which has S BET of 741 m 2 g -1 , V mi of 0.39 cm 3 g -1 and a iodine retention capacity of 429.3 mg g -1 ): carbon C (gasification with CO 2 at 850 deg. Cduring 1 h), with S BET of 523 m 2 g -1 , V mi of 0.33 cm 3 g -1 and a iodine retention capacity of 402.5 mg g -1 , and carbon D (gasification with CO 2 at 900 deg. Cduring 1 h), whose S BET is 672 m 2 g -1 , V mi is 0.28 cm 3 g -1 and has a iodine retention capacity of 345.2 mg g -1

  7. Production of synthetic methanol from air and water using controlled thermonuclear reactor power. 2. Capital investment and production costs

    Energy Technology Data Exchange (ETDEWEB)

    Dang, V D; Steinberg, M [Brookhaven National Lab., Upton, N.Y. (USA)

    1977-01-01

    Energy requirement and process development of methanol production from air and water using controlled thermonuclear fusion power was discussed in Part 1 (Steinberg et al., Energy conversion;17:97(1977)). This second part presents an economic analysis of the nine processes presented for obtaining carbon dioxide recovery from the atmosphere or the sea for methanol production. It is found that the most economical process of obtaining carbon dioxide is by stripping from sea water. The process of absorption/stripping by dilute potassium carbonate solution is found to be the most economical for the extraction of carbon dioxide from air at atmospheric pressure. The total energy required for methanol synthesis from these sources of carbon dioxide is 3.90 kWh(e)/lb methanol of which 90% is used for generation of hydrogen. The process which consumes the greatest amount of energy is the absorption/stripping of air by water at high pressure and amounts to 13.2 kWh(e)/lb methanol. With nuclear fusion power plants of 1000to 9000 MW(e), it is found that the cost of methanol using the extraction of carbon dioxide from air with dilute potassium carbonate solution is estimated to be in the range between Pound1.73 and Pound2.90/MMB.t.u. (energy equivalent - 1974 cost) for plant capacities of 21 400 to 193 000 bbl/day methanol. This methanol cost is competitive with gasoline in the range of 19 approximately equal to 33c/gallon. For the process of stripping of carbon dioxide from sea water, the cost is found to lie in the range of Pound1.65 to Pound2.71/MMB.t.u. (energy equivalent) for plant capacities of 21 700 to 195 000 bbl/day methanol which is competitive with gasoline in the range of 18 approximately equal to 30 c/gallon. Projection of methanol demand in the year 2020 is presented based on both its conventional use as chemicals and as a liquid fuel substituting for oil and gas.

  8. Genetic Variant rs10757278 on Chromosome 9p21 Contributes to Myocardial Infarction Susceptibility

    Directory of Open Access Journals (Sweden)

    Guangyuan Chen

    2015-05-01

    Full Text Available Large-scale genome-wide association studies (GWAS have revealed that rs10757278 polymorphism (or its proxy rs1333049 on chromosome 9p21 is associated with myocardial infarction (MI susceptibility in individuals of Caucasian ancestry. Following studies in other populations investigated this association. However, some of these studies reported weak or no significant association. Here, we reevaluated this association using large-scale samples by searching PubMed and Google Scholar databases. Our results showed significant association between rs10757278 polymorphism and MI with p = 6.09 × 10−22, odds ratio (OR = 1.29, 95% confidence interval (CI 1.22–1.36 in pooled population. We further performed a subgroup analysis, and found significant association between rs10757278 polymorphism and MI in Asian and Caucasian populations. We identified that the association between rs10757278 polymorphism and MI did not vary substantially by excluding any one study. However, the heterogeneity among the selected studies varies substantially by excluding the study from the Pakistan population. We found even more significant association between rs10757278 polymorphism and MI in pooled population, p = 3.55 × 10−53, after excluding the study from the Pakistan population. In summary, previous studies reported weak or no significant association between rs10757278 polymorphism and MI. Interestingly, our analysis suggests that rs10757278 polymorphism is significantly associated with MI susceptibility by analyzing large-scale samples.

  9. Association between BDNF-rs6265 and obesity in the Boston Puerto Rican Health Study

    Science.gov (United States)

    The objective of this study is to examine a functional variant (rs6265) in the BDNF gene interacting with dietary intake modulate obesity traits in the Boston Puerto Rican Health Study population. BDNF rs6265 was genotyped in 1147 Puerto Ricans (aged 45-75 years), and examined for association with o...

  10. rs3806268 of NLRP3 gene polymorphism is associated with the development of primary gout.

    Science.gov (United States)

    Deng, Jianping; Lin, Wen; Chen, Yunpeng; Wang, Xin; Yin, Zhong; Yao, Chunhong; Liu, Tangbing; Lv, Yonghong

    2015-01-01

    The aim of the present study was to investigate the association between seven functional SNPs in NALP3 gene and the susceptibility to primary gout. A total of 247 patients with primary gout and 247 controls were selected in this study. Genotyping of NALP3 rs4612666, rs3806268, rs12239046, rs10754558, rs7512998, rs12137901 and rs12565738 was performed using the Sequenom MassARRAY platform. Comparison analysis showed that primary gout patients were more likely to have a higher body mass index, DBP, SBP, TG, urea nitrogen and uric acid (P gout when compared with the AA genotype (OR=1.83, 95% CI=1.03-3.26). However, no significant associations were identified for the remaining SNPs. In conclusion, we found a significant association between rs3806268 in NLRP3 gene and the risk of primary gout in a Chinese population. Further clinical and genetic studies are required to investigate the mechanisms underlying the association between NALP3 polymorphisms and the development of primary gout.

  11. Identification of rs671, a common variant of ALDH2, as a gout susceptibility locus.

    Science.gov (United States)

    Sakiyama, Masayuki; Matsuo, Hirotaka; Nakaoka, Hirofumi; Yamamoto, Ken; Nakayama, Akiyoshi; Nakamura, Takahiro; Kawai, Sayo; Okada, Rieko; Ooyama, Hiroshi; Shimizu, Toru; Shinomiya, Nariyoshi

    2016-05-16

    Gout is a common disease resulting from hyperuricemia. Recently, a genome-wide association study identified an association between gout and a single nucleotide polymorphism (SNP) rs2188380, located on an intergenic region between MYL2 and CUX2 on chromosome 12. However, other genes around rs2188380 could possibly be gout susceptibility genes. Therefore, we performed a fine-mapping study of the MYL2-CUX2 region. From 8,595 SNPs in the MYL2-CUX2 region, 9 tag SNPs were selected, and genotyping of 1,048 male gout patients and 1,334 male controls was performed by TaqMan method. Eight SNPs showed significant associations with gout after Bonferroni correction. rs671 (Glu504Lys) of ALDH2 had the most significant association with gout (P = 1.7 × 10(-18), odds ratio = 0.53). After adjustment for rs671, the other 8 SNPs no longer showed a significant association with gout, while the significant association of rs671 remained. rs671 has been reportedly associated with alcohol drinking behavior, and it is well-known that alcohol drinking elevates serum uric acid levels. These data suggest that rs671, a common functional SNP of ALDH2, is a genuine gout-associated SNP in the MYL2-CUX2 locus and that "A" allele (Lys) of rs671 plays a protective role in the development of gout.

  12. The role of KRAS rs61764370 in invasive epithelial ovarian cancer: implications for clinical testing

    DEFF Research Database (Denmark)

    Pharoah, Paul D P; Palmieri, Rachel T; Ramus, Susan J

    2011-01-01

    PURPOSE: An assay for the single nucleotide polymorphism (SNP) rs61764370 has recently been commercially marketed as a clinical test to aid ovarian cancer risk evaluation in women with family histories of the disease. rs67164370 is in a 3'UTR miRNA binding site of the KRAS oncogene, and is a cand...

  13. Polymorphism of glucagon-like peptide-1 receptor gene (rs1042044 ...

    African Journals Online (AJOL)

    patience

    2015-02-16

    Feb 16, 2015 ... turnover via GLP-1 receptors (GLP1Rs) in postmenopausal state. Furthermore, polymorphisms in. GLP1R gene were suggested to affect the function of GLP1Rs and be associated with many diseases. However, the relationships between GLP1R polymorphisms and osteoporosis susceptibility and bone.

  14. Polymorphism of glucagon-like peptide-1 receptor gene (rs1042044 ...

    African Journals Online (AJOL)

    Previous investigations indicated that glucagon-like peptide-1 (GLP-1) played important roles in bone turnover via GLP-1 receptors (GLP1Rs) in postmenopausal state. Furthermore, polymorphisms in GLP1R gene were suggested to affect the function of GLP1Rs and be associated with many diseases. However, the ...

  15. Pentatomids associated with different forest species in Itaara, RS, Brazil

    Directory of Open Access Journals (Sweden)

    Ervandil Corrêa Costa

    2010-03-01

    Full Text Available The objective of this study was to determine qualitatively and quantitatively the pentatomid fauna associated with the canopy of different native species during the period from September 2005 to September 2006. Insects were collected from among nine botanical species: Gochnatia polymorpha (Less. (cambará, Eugenia uniflora Berg. (pitangueira, Acca selowiana (Berg Burret (goiaba-da-serra, Psidium cattleianum Sabine (araçá, Baccharis spp., Solanaum mauritianum Scop. (fumo-bravo, Micanea cinerascens Miq. (passiquinho, Calliandra brevipes Bhent. (caliandra, and Schinus molle L. (aroeira located at Rodolfo da Costa Dam in Itaara, RS, Brazil. Samples were taken every two weeks with a conical funnel made of tin plate (2mm, 70cm in diameter at the rim and 63cm in height. One sample per botanical species for each sampling date was taken, by shaking the branches, ten times over the funnel. Samples were sent to the Entomology Laboratory of the Crop Protection Department of the Federal University of Santa Maria, where the material was analyzed. A total of nine Pentatomidae species were identified. Edessa rufomarginata (De Geer, 1773 was the species of highest ocurrence followed by Thyanta humilis (Bergroth, 1891. The botanical species S. mauritianum presented the greatest number of Pentatomidae species, with an occurrence of 26.9%.

  16. RASSF1A and the rs2073498 Cancer Associated SNP

    International Nuclear Information System (INIS)

    Donninger, Howard; Barnoud, Thibaut; Nelson, Nick; Kassler, Suzanna; Clark, Jennifer; Cummins, Timothy D.; Powell, David W.; Nyante, Sarah; Millikan, Robert C.; Clark, Geoffrey J.

    2011-01-01

    RASSF1A is one of the most frequently inactivated tumor suppressors yet identified in human cancer. It is pro-apoptotic and appears to function as a scaffolding protein that interacts with a variety of other tumor suppressors to modulate their function. It can also complex with the Ras oncoprotein and may serve to integrate pro-growth and pro-death signaling pathways. A SNP has been identified that is present in approximately 29% of European populations [rs2073498, A(133)S]. Several studies have now presented evidence that this SNP is associated with an enhanced risk of developing breast cancer. We have used a proteomics based approach to identify multiple differences in the pattern of protein/protein interactions mediated by the wild type compared to the SNP variant protein. We have also identified a significant difference in biological activity between wild type and SNP variant protein. However, we have found only a very modest association of the SNP with breast cancer predisposition.

  17. Water quality assessment of the Sinos River – RS, Brazil

    Directory of Open Access Journals (Sweden)

    C. Steffens

    Full Text Available Worldwide environmental pollution is increasing at the same rate as social and economic development. This growth, however, is disorganized and leads to increased degradation of water resources. Water, which was once considered inexhaustible, has become the focus of environmental concerns because it is essential for life and for many production processes. This article describes monitoring of the water quality at three points along the Sinos River (RS, Brazil, one in each of the upper, middle and lower stretches. The points were sampled in 2013 and again in 2014. The water samples were analyzed to determine the following physical and chemical parameters plus genotoxicity to fish: metals (Cr, Fe, Al, chemical oxygen demand, biochemical oxygen demand, chlorides, conductivity, total suspended solids, total phosphorous, total and fecal coliforms, pH, dissolved oxygen, turbidity, total Kjeldahl nitrogen nitrate and ammoniacal nitrogen. Genotoxicity was tested by exposing individuals of the species Astyanax jacuhiensis to water samples and then comparing them with a control group exposed to water from the public water supply. The results confirmed the presence of substances with genotoxic potential at the sample points located in the middle and lower stretches of the river. The results for samples from the upper stretch, at P1, did not exhibit differences in relation to the control group. The physical and chemical analyses did not detect reductions in water quality in the lower stretch, as had been expected in view of the large volumes of domestic and industrial effluents discharged into this part of the river.

  18. Performance Characterization of RaPToRS Systems

    Science.gov (United States)

    Shibata, K.; Krieger, M.; Fallica, J.; Henchen, R.; Pogozelski, E.; Padalino, S.; SUNY Geneseo Collaboration; LaboratoryLaser Energetics at University of Rochester Collaboration

    2011-10-01

    The Rapid Pneumatic Transport of Radioactive Samples (RaPToRS) system can quickly and efficiently move radioactive materials from their activation site to a counting station. Facilities such as the NIF and LLE are considering these systems while NRL is currently using one. The system is essentially a 10 cm diameter pneumatic tube with a cylindrical sample carrier. The performance of the system depends on many factors, including the mass of the carrier, length of the tube, angle and difference in height of the tube's endpoints, the carrier's physical design, and the number, type, and distribution of blowers attached to the tube. These factors have been systematically examined to develop the fastest and most reliable system. The most significant factors are the mass and the vertical travel of the carrier. When the carrier mass is low, moving air supports the carrier in the tube, resulting in low friction. The terminal velocity ranges from 13.5 to 2.5 m/s for masses varying from 1 kg to 3 kg. Using a single 1100 W blower, the initial force exerted on the carrier was 11.3 N. This work was supported in part by the US Department of Energy through the LLE.

  19. Rapid Pneumatic Transport of Radioactive Samples - RaPToRS

    Science.gov (United States)

    Padalino, S.; Barrios, M.; Sangster, C.

    2005-10-01

    Some ICF neutron activation diagnostics require quick retrieval of the activated sample. Minimizing retrieval times is particularly important when the half-life of the activated material is on the order of the transport time or the degree of radioactivity is close to the background counting level. These restrictions exist in current experiments performed at the Laboratory for Laser Energetics, thus motivating the development of the RaPToRS system. The system has been designed to minimize transportation time while requiring no human intervention during transport or counting. These factors will be important if the system is to be used at the NIF where radiological hazards will be present during post activation. The sample carrier is pneumatically transported via a 4 inch ID PVC pipe to a remote location in excess of 100 meters from the activation site at a speed of approximately 7 m/s. It arrives at an end station where it is dismounted robotically from the carrier and removed from its hermetic package. The sample is then placed by the robot in a counting station. This system is currently being developed to measure back-to-back gamma rays produced by positron annihilation which were emitted by activated graphite. Funded in part by the U.S. DOE under sub contract with LLE at the University of Rochester.

  20. Diagnosis of the retail flower market of Santa Maria, RS

    Directory of Open Access Journals (Sweden)

    Janine Farias Menegaes

    2015-12-01

    Full Text Available The present study aimed to diagnose the flowers retail market and ornamental plants in Santa Maria, RS, Brazil, by means of a research in loco, from January to June of 2013, based on questionnaires and interviews applied to the managers of the establishment, as well as of an application of a visual and phytosanitary scale to other establishments that sell flowers and ornamental plants, such as agricultural shops, fairs of horticultural products, supermarkets and providers of funeral services - cemeteries and funeral homes. The diagnosis aims to know the steps of the dynamics observed from the market of flowers until the final consumer, and to segment the types of floricultures, distinguishing them according to the commercial focus — floricultures of arrangements and bouquets, and producing flowers and landscape floricultures. Based on the diagnosis it can be concluded that the Santa Maria retail flowers and ornamental plants follows the national trend of floral arrangements and bouquets shops, with the increase of the companies focused on landscaping and gardening. Among the most marketed plants are the rose as the best-selling cut flower, the begonia as potted flower, the fern for foliage arrangements, the cactus as potted plant, the raffia as garden plant and the pansy as the best-selling plant in boxes.

  1. Torus type thermonuclear device

    International Nuclear Information System (INIS)

    Imura, Yasuya.

    1979-01-01

    Purpose: To attain supporting effect against electromagnetic force and moderate the inner stress applied to toroidal coils due to thermal expansion by intervening a stress relaxation member between the outer circumferential side of a torus and a support device in toroidal coils. Constitution: Toroidal coils for confining a plasma within a torus vacuum container is supported on a support secured to upper and lower bases. A thermoplastic stress relaxation material of a low young's modulus is put between the outer circumferential side of the torus container and the torus outer circumferential side of the support in the toroidal coil. Thermoplastic resin is best suited to the stress relaxation substance, although tetrafluoro resin may be used as the stress relaxation substance while packing non-woven tetron fabric or non-woven glass fabric impregnated with varnish in a gap between the stress relaxation substance and the support or the toroidal coils. (Seki, T.)

  2. Device for thermonuclear reactor

    International Nuclear Information System (INIS)

    Yanagisawa, Yutaro; Kawarazaki, Yuki; Sugiyama, Yu.

    1996-01-01

    A member comprising hydrogen occluding materials is introduced to a reactor incorporated with U-235 as fuels in order to moderate and breed fast neutrons and to control the reactor. Since the amount of light hydrogen or heavy hydrogen is substantially the same as that of metal, etc. of hydrogen occluding material, a moderating efficiency substantially equal with that of a moderator comprising H 2 O can be obtained. In addition, since the member acting as a moderator has an effect of multiplying neutrons, use of only natural uranium 0.72% as nuclear fuels causes chain reaction to provide a function as a nuclear reactor. Further, the hydrogen occluding material can be used also as a control rod for controlling the reactor. The hydrogen occluding material may be Ti, Zr, Pd, proton conductor, Ag, Pt, Rh or oxides thereof or alloys thereof. The member comprising hydrogen occluding materials is preferably coated with a material not permeating hydrogen. (N.H.)

  3. Thermonuclear burn criteria

    NARCIS (Netherlands)

    Oost, van G.; Jaspers, R.J.E.

    2012-01-01

    After more than 50 years of fusion research the time has arrived when fusion processes in experimental plasmas are increasingly getting important. In JET the genuine fuel (deuterium-tritium) of a fusion reactor was used for the first time in late 1991, in TFTR the same happened in 1993, and in JET

  4. The controlled thermonuclear fusion

    International Nuclear Information System (INIS)

    Barre, Bertrand

    2014-01-01

    After some generalities on particle physics, and on fusion and fission reactions, the author outlines that the fission reaction is easier to obtain than the fusion reaction, evokes the fusion which takes place in stars, and outlines the difficulty to manage and control this reaction: one of its application is the H bomb. The challenge is therefore to find a way to control this reaction and make it a steady and continuous source of energy. The author then presents the most promising way: the magnetic confinement fusion. He evokes its main issues, the already performed experiments (tokamak), and gives a larger presentation of the ITER project. Then, he evokes another way, the inertial confinement fusion, and the two main experimental installations (National Ignition Facility in Livermore, and the Laser Megajoule in Bordeaux). Finally, he gives a list of benefits and drawbacks of an industrial nuclear fusion

  5. Controlled thermonuclear program

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    Brief discussions are given for the following four areas of research: (1) tritium handling system for an experimental fusion power reactor, (2) preparation for tests of cryosorption pumping for fusion reactors, (3) tritium sorption studies, and (4) tritium sorption in Li--Al and Li--Bi alloys. (MOW)

  6. Controlled thermonuclear processing

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    Brief discussions are given on research progress during this report period for the following two topics: (1) conceptual design of a tritium handling system for Ormak F/BX, and (2) design of, and preparation for, tests of cryosorption pumping for fusion reactors. The status of the program is outlined. (MOW)

  7. Thermonuclear fusion power

    Energy Technology Data Exchange (ETDEWEB)

    Lehnert, B

    1977-01-01

    The present state and future possibilities of controlled-nuclear-fusion research are reviewed, including basic concepts and problems, as well as various approaches based on magnetic- and nonmagnetic-confinement schemes. Considerable progress has so far been made in both plasma physics and fusion-reactor technology, and a closer relationship has been established between theory and experiments. Still, none of the present approaches will, for certain, lead to the final solution of a full-scale reactor. Intensified work along broad lines, with emphasis also on basic research and new ideas, is necessary for future success.

  8. Controlled thermonuclear research program

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The Plasma Physics and Controlled-Fusion Research Program at the Lawrence Berkeley Laboratory is divided into five projects: Plasma Production and Heating Experiments, Plasma Theory, Atomic Physics Studies, the Tormac Project, and Neutral-Beam Development and Technology listed in order of increasing magnitude, as regards manpower and budget. Some cross sections and yields are shown in atomic physics

  9. Torus type thermonuclear device

    International Nuclear Information System (INIS)

    Gomei, Yoshio.

    1982-01-01

    Purpose: To facilitate heat removal at limiters and enable helium discharge without using a diverter by the separate disposition of a main limiter receiving the heat from plasmas and an auxiliary limiter for helium discharge. Constitution: A main limiter for establishing and maintaining torus plasmas and an auxiliary limiter for helium discharge are disposed separately. The auxiliary limiter is disposed between the magnetic plane at the position where the plasmas in the confining region begin to contact the main limiter and the first blanket wall. Thus, a sufficient contact area with the plasmas can be taken for the main limiter disposed to the inside of the torus to thereby avoid excess heat concentration. Further, helium ions transported through a passage along the magnetic plane between the main limiter and the first blanket wall to the exhaust chamber are neutralized and thereafter discharged by the auxiliary limiter. (Moriyama, K.)

  10. Inertia thermonuclear reactor

    International Nuclear Information System (INIS)

    Imon, Toshiharu; Nakamura, Norio; Oomura, Hiroshi.

    1983-01-01

    Purpose: To eliminate the requirement of power for controlling the flow velocity of coolants flowing through a porous structure blanket, as well as establish a uniform and stable coolant layer. Constitution: Breeding blanket is made with mesh-like or fiberous porous body, and liquid lithium is introduced into the porous body. The porous body functions as a resistive member to inhibit the free fall of the liquid lithium, so the coolant flowing velocity can be determined to a desired value by appropriately selecting the porosity therein. Further, since liquid lithium flows downwardly at a uniform speed under the effect of the gravitational force, the layer thickness is made uniform to effectively recover neutron energy. Also, while waves are formed at the boundary surface of the liquid lithium layer other than for the porous body due to the collision of fine balls or the likes, they are instantly eliminated by the porous body and the flow can be stabilized. (Yoshino, Y.)

  11. Torus type thermonuclear device

    International Nuclear Information System (INIS)

    Kitazawa, Hakaru; Saito, Ryusei.

    1981-01-01

    Purpose: To obtain toroidal coil supports structures capable of coping with the changes in the elasticity distribution due to thermal expansion and performing elastic support function corresponding to the distribution of stresses exerted on the toroidal coils, by providing elastic function to the inner circumference side of the coil support structures. Constitution: Support structures for supporting toroidal coils from above and below are formed at the torus inner circumference side thereof with ribs in contact with a central block and having elasticity coefficient corresponding to the distribution of stresses exerted on the toroidal coils, and the stresses exerted on the toroidal coils are elastically supported on the ribs. Accordingly, if the stress distribution varies due to the thermal expansion or the like, adequate supporting function can be obtained well-corresponding to such changes, whereby effective plasma confinement can be attained. (Moriyama, K.)

  12. Toroidal Thermonuclear device

    International Nuclear Information System (INIS)

    Takizawa, Teruhiro; Shizuoka, Yoshihide.

    1982-01-01

    Purpose: To reduce the shielding capacity of a current breaker for a current transformer coil and to facilitate the manufacture and the assembly of the current transformer coil. Constitution: A first current transformer coil is provided between a vacuum container for enclosing a plasma and a toroidal magnetic field coil, and a secon current transformer coil is provided outside the toroidal magnetic field coil. The rise of the plasma current is performed by the variation in the current of the coil of the first transformer having high electromagnetic coupling with the plasma current, and the variation in the magnetic flux necessary for maintaining the plasma is performed by the variation in the current of the second transformer coil. In this manner, the current shielding capacity of the first transformer coil can be reduced to decrease the number of coil turns, thereby facilitating the manufacture and assembly. (Seki, T.)

  13. Echography by Thermonuclear Fusion

    International Nuclear Information System (INIS)

    Ramos, Ruben; Moreno, Carlos; Gonzalez, Jose; Florido, Pablo; Clausse, Alejandro

    2003-01-01

    A technique to substances detection in the neighbourhood of a compact Plasma Focus (PF) is presented. The method is based on the same principle of the sonar or the echographs.The measuring system is composed by two neutron detectors operated simultaneously on every shot.The first detector is used to register the PF neutron yield in each shot; whereas the other one was designed for detecting neutrons scattered by the blanket.The complete detecting system is very simple and inexpensive. The study consisted in measuring the reflection of neutrons emitted by a Deuterium pinch. The correlation of the counts recorded by the detectors located at different positions was mapped with the water distribution around the neutron source. Moreover, we obtained the maps of the substance positions coordinates in function of measurement variables. Also we used the MCNP code in order to simulate the experiments

  14. The ARIES-RS power core - recent development in Li/V designs

    International Nuclear Information System (INIS)

    Sze Dai-Kai; Billone, M.C.; Hua, T.Q.; Tillack, M.; Najmabadi, F.; Wang Xueren; Malang, S.; El-Guebaly, L.A.; Sviatoslavsky, I.N.; Blanchard, J.P.; Crowell, J.A.; Khater, H.Y.; Mogahed, E.A.; Waganer, L.M.; Lee, D.; Cole, D.

    1998-01-01

    The ARIES-RS fusion power plant design study is based on reversed-shear (RS) physics with a Li/V (lithium breeder and vanadium structure) blanket. The reversed-shear discharge has been documented in many large tokamak experiments. The plasma in the RS mode has a high beta, low current, and low current drive requirement. Therefore, it is an attractive physics regime for a fusion power plant. The blanket system based on Li/V has high temperature operating capability, good tritium breeding, excellent high heat flux removal capability, long structural life time, low activation, low after heat and good safety characteristics. For these reasons, the ARIES-RS reactor study selected Li/V as the reference blanket. The combination of attractive physics and attractive blanket engineering is expected to result in a superior power plant design. This paper summarizes the power core design of the ARIES-RS power plant study. (orig.)

  15. Association between the rs7574865 polymorphism of STAT4 and rheumatoid arthritis: a meta-analysis.

    Science.gov (United States)

    Lee, Young Ho; Woo, Jin-Hyun; Choi, Seong Jae; Ji, Jong Dae; Song, Gwan Gyu

    2010-03-01

    The aim of this study was to determine whether the rs7574865 polymorphism of STAT4 (signal transducers and activators of transcription 4) confers susceptibility to rheumatoid arthritis (RA) in populations with different ethnicities. A meta-analysis was conducted on the T allele of the STAT4 rs7574865 polymorphism in 15 studies containing 16,088 RA patients and 16,509 normal control subjects. Meta-analysis revealed an association between RA and the STAT4 rs7574865 T allele in all subjects (OR = 1.271, 95% CI = 1.197-1.350, P rs7574865 T allele was found to be significantly associated with RA in Europeans and Asians (OR = 1.300, 95% CI = 1.195-1.414, P rs7574865 polymorphism is associated with RA susceptibility in different ethnic groups, and that its prevalence is ethnicity dependent.

  16. Finite element modeling and experimental study of brittle fracture in tempered martensitic steels for thermonuclear fusion applications

    International Nuclear Information System (INIS)

    Mueller, P. F.

    2009-10-01

    The present report studies the brittle fracture in high-chromium reduced activation tempered martensitic steels foreseen as structural materials for thermonuclear fusion reactors. Developing the adequate materials that can withstand the severe irradiation conditions of the burning plasma in a fusion reactor is one of the major challenges to be solved in order to make profit from the great advantages of thermonuclear fusion as an energy source. High-chromium tempered martensitic steels such as F82H and the most advanced version Eurofer97 are among the main candidate materials for structural applications in future fusion power plants due to low irradiation-induced swelling, good mechanical and thermal properties, and reasonably fast radioactive decay. Drawback of this kind of steels is irradiation embrittlement, which is manifested by a ductile-to-brittle transition temperature shift to higher temperatures after irradiation. The laboratory specimen fracture data has to be transferred to real components in order to assess the performance of these steels in the different operating and transient conditions they could find during the operation life of a fusion reactor. The specimen geometry effects and specimen size effects on measured fracture toughness need to be properly understood, taken into account and predicted with an appropriate model. The microstructure of Eurofer97 and F82H has been characterized and compared by means of optical microscopy, scanning electron microscopy, transmission electron microscopy and energy-dispersive X-ray spectroscopy in order to identify microstructural features that could play a role in the measured fracture toughness. Both steels have similar but slightly different chemical composition and final heat treatments but the prior austenitic grain size measured in F82H is approximately 8 times larger than in Eurofer97. The alloying element tantalum is added to stabilize the austenite grain size. In Eurofer97 it forms carbides of an

  17. Experimental measurements of the 15O(alpha,gamma)19Ne reaction rate and the stability of thermonuclear burning on accreting neutron stars

    International Nuclear Information System (INIS)

    Fisker, J; Tan, W; Goerres, J; Wiescher, M; Cooper, R

    2007-01-01

    Neutron stars in close binary star systems often accrete matter from their companion stars. Thermonuclear ignition of the accreted material in the atmosphere of the neutron star leads to a thermonuclear explosion which is observed as an X-ray burst occurring periodically between hours and days depending on the accretion rate. The ignition conditions are characterized by a sensitive interplay between the accretion rate of the fuel supply and its depletion rate by nuclear burning in the hot CNO cycle and the rp-process. For accretion rates close to stable burning the burst ignition therefore depends critically on the hot CNO breakout reaction 15 O(α, γ) 19 Ne that regulates the flow between the hot CNO cycle and the rapid proton capture process. Until recently, the 15 O(α, γ) 19 Ne reaction rate was not known experimentally and the theoretical estimates carried significant uncertainties. In this paper we perform a parameter study of the uncertainty of this reaction rate and determine the astrophysical consequences of the first measurement of this reaction rate. Our results corroborate earlier predictions and show that theoretically burning remains unstable up to accretion rates near the Eddington limit, in contrast to astronomical observations

  18. Modelling of thermal and thermalhydraulic in a heat exchanger of a fusion thermonuclear reactor using 'GENEPI' computer code

    International Nuclear Information System (INIS)

    Langlais, Gilles

    1999-01-01

    The work presented in this report has been performed in the frame of fusion safety studies for thermonuclear reactors of ITER type (International Thermonuclear Experimental Reactor). It is particularly related to the thermal and two-phases thermalhydraulic studies of heat exchangers facing plasma. These components are submitted to unidirectional high heat flux between 1 to 10 MW/m 2 . The cooling fluid is then heat by an anisotropic heat flux. This non-uniform distribution induces the presence of different heat transfer on the cooling channel (single phase forced convection, subcooled nucleate boiling). The thermal and the thermalhydraulic three-dimensional study has been performed using experimental data and coupled computer calculations developed in the frame of this thesis work. The heat transfer between solid and fluid are modelled using correlations selected after the bibliography study. These heat exchange correlations as well as the CHF ones have been assessed by comparison to the available experimental data. This allowed to modify the single phase heat transfer correlation and to select two CHF correlations. (author) [fr

  19. The LOFT perspective on neutron star thermonuclear bursts: White paper in support of the mission concept of the large observatory for X-ray timing

    Energy Technology Data Exchange (ETDEWEB)

    in' t Zand, J. J.M. [SRON Netherlands Institute for Space Research, Utrecht (The Netherlands); Malone, Christopher M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Altamirano, D. [Univ. of Southampton, Southampton (United Kingdom); Ballantyne, D. R. [Georgia Inst. of Technology, Atlanta, GA (United States); Bhattacharyya, S. [Tata Institute of Fundamental Research, Mumbai (India); Brown, E. F. [Michigan State Univ., East Lansing, MI (United States); Cavecchi, Y. [Univ. of Amsterdam, Amsterdam (The Netherlands); Chakrabarty, D. [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Chenevez, J. [Technical Univ. of Denmark, Lyngby (Denmark); Cumming, A. [McGill Univ., Montreal, QC (Canada); Degenaar, N. [Univ. of Cambridge, Cambridge (United Kingdom); Falanga, M. [International Space Science Institute, Bern (Switzerland); Galloway, D. K. [Monash Univ., VIC (Australia); Heger, A. [Monash Univ., VIC (Australia); Jose, J. [Univ. Politecnica de Catalunya, Barcelona (Spain); Institut d' Estudis Espacials de Catalunya, Barcelona (Spain); Keek, L. [Georgia Institute of Technology, Atlanta, GA (United States); Linares, M. [Univ. de La Laguna, Tenerife (Spain); Mahmoodifar, S. [Univ. of Maryland, College Park, MD (United States); Mendez, M. [Univ. of Groningen, Groningen (The Netherlands); Miller, M. C. [Univ. of Maryland, College Park, MD (United States); Paerels, F. B. S. [Columbia Astrophysics Lab., New York, NY (United States); Poutanen, J. [Univ. of Turku, Piikkio (Finland); Rozanska, A. [N. Copernicus Astronomical Center PAS, Warsaw (Poland); Schatz, H. [National Superconducting Cyclotron Laboratory at Michigan State University; Serino, M. [Institute of Physical and Chemical Research (RIKEN); Strohmayer, T. E. [NASA' s Goddard Space Flight Center, Greenbelt, MD (United States); Suleimanov, V. F. [Univ. Tubingen, Tubingen (Germany); Thielemann, F. -K. [Univ. Basel, Basel (Switzerland); Watts, A. L. [Univ. of Amsterdam, Amsterdam (The Netherlands); Weinberg, N. N. [Massachusetts Institute of Technology, Cambridge, MA (United States); Woosley, S. E. [Univ. of California, Santa Cruz, CA (United States); Yu, W. [Chinese Academy of Sciences (CAS), Shanghai (China); Zhang, S. [Institute of High-Energy Physics, Beijing (China); Zingale, M. [Stony Brook Univ., Stony Brook, NY (United States)

    2015-01-14

    The Large Area Detector (LAD) on the Large Observatory For X-ray Timing ( LOFT ), with a 8.5 m 2 photon- collecting area in the 2–30 keV bandpass at CCD-class spectral resolving power (λ/Δλ = 10 – 100), is designed for optimum performance on bright X-ray sources. Thus, it is well-suited to study thermonuclear X-ray bursts from Galactic neutron stars. These bursts will typically yield 2 x 105 photon detections per second in the LAD, which is at least 15 times more than with any other instrument past, current or anticipated. The Wide Field Monitor (WFM) foreseen for LOFT uniquely combines 2–50 keV imaging with large (30%) prompt sky coverage. This will enable the detection of tens of thousands of thermonuclear X-ray bursts during a 3-yr mission, including tens of superbursts. Both numbers are similar or more than the current database gathered in 50 years of X-ray astronomy.

  20. Study on parallel and distributed management of RS data based on spatial database

    Science.gov (United States)

    Chen, Yingbiao; Qian, Qinglan; Wu, Hongqiao; Liu, Shijin

    2009-10-01

    With the rapid development of current earth-observing technology, RS image data storage, management and information publication become a bottle-neck for its appliance and popularization. There are two prominent problems in RS image data storage and management system. First, background server hardly handle the heavy process of great capacity of RS data which stored at different nodes in a distributing environment. A tough burden has put on the background server. Second, there is no unique, standard and rational organization of Multi-sensor RS data for its storage and management. And lots of information is lost or not included at storage. Faced at the above two problems, the paper has put forward a framework for RS image data parallel and distributed management and storage system. This system aims at RS data information system based on parallel background server and a distributed data management system. Aiming at the above two goals, this paper has studied the following key techniques and elicited some revelatory conclusions. The paper has put forward a solid index of "Pyramid, Block, Layer, Epoch" according to the properties of RS image data. With the solid index mechanism, a rational organization for different resolution, different area, different band and different period of Multi-sensor RS image data is completed. In data storage, RS data is not divided into binary large objects to be stored at current relational database system, while it is reconstructed through the above solid index mechanism. A logical image database for the RS image data file is constructed. In system architecture, this paper has set up a framework based on a parallel server of several common computers. Under the framework, the background process is divided into two parts, the common WEB process and parallel process.