National Library of Energy BETA

Sample records for achieving fusion conditions

  1. Multinational achievement: PPPL collaborates on record fusion...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Multinational achievement: PPPL collaborates on record fusion plasma in tokamak in China ... for suppressing instabilities that can cut short the life of controlled fusion reactions. ...

  2. Deuterium Uptake in Magnetic Fusion Devices with Lithium Conditioned Carbon

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    Walls | Princeton Plasma Physics Lab Deuterium Uptake in Magnetic Fusion Devices with Lithium Conditioned Carbon Walls American Fusion News Category: U.S. Universities Link: Deuterium Uptake in Magnetic Fusion Devices with Lithium Conditioned Carbon Walls

  3. COLLOQUIUM: Achieving 10MW Fusion Power in TFTR: a Retrospective |

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Princeton Plasma Physics Lab November 18, 2014, 2:00pm to 3:00pm Colloquia MBG Auditorium COLLOQUIUM: Achieving 10MW Fusion Power in TFTR: a Retrospective Dr. Michael Bell Princeton Plasma Physics Laboratory "The Tokamak Fusion Test Reactor (TFTR) operated at the Princeton Plasma Physics Laboratory (PPPL) from 1982 to 1997. TFTR set a number of world records, including a plasma temperature of 510 million degrees centigrade -- the highest ever produced in a laboratory, and well beyond

  4. Experimental demonstration of fusion-relevant conditions in magnetized

    Office of Scientific and Technical Information (OSTI)

    liner inertial fusion (Journal Article) | DOE PAGES Experimental demonstration of fusion-relevant conditions in magnetized liner inertial fusion « Prev Next » Title: Experimental demonstration of fusion-relevant conditions in magnetized liner inertial fusion This Letter presents results from the first fully integrated experiments testing the magnetized liner inertial fusion concept [S.A. Slutz et al., Phys. Plasmas 17, 056303 (2010)], in which a cylinder of deuterium gas with a preimposed

  5. Multinational achievement: PPPL collaborates on record fusion plasma in

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    tokamak in China | Princeton Plasma Physics Lab Multinational achievement: PPPL collaborates on record fusion plasma in tokamak in China By John Greenwald November 25, 2013 Tweet Widget Google Plus One Share on Facebook Interior view of EAST tokamak (Photo by Institute of Plasma Physics, Chinese Academy of Sciences ) Interior view of EAST tokamak A multinational team led by Chinese researchers in collaboration with U.S. and European partners has successfully demonstrated a novel technique

  6. Multinational achievement: PPPL collaborates on record fusion plasma in

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    tokamak in China | Princeton Plasma Physics Lab Multinational achievement: PPPL collaborates on record fusion plasma in tokamak in China By John Greenwald December 9, 2013 Tweet Widget Google Plus One Share on Facebook Interior view of EAST tokamak (Photo by Institute of Plasma Physics, Chinese Academy of Sciences ) Interior view of EAST tokamak A multinational team led by Chinese researchers in collaboration with U.S. and European partners has successfully demonstrated a novel technique for

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

    SciTech Connect (OSTI)

    Gomez, Matthew R.; Slutz, Stephen A.; Sefkow, Adam B.; Hahn, Kelly D.; Hansen, Stephanie B.; Knapp, Patrick F.; Schmit, Paul F.; Ruiz, Carlos L.; Sinars, Daniel Brian; Harding, Eric C.; Jennings, Christopher A.; Awe, Thomas James; Geissel, Matthias; Rovang, Dean C.; Smith, Ian C.; Chandler, Gordon A.; Cooper, Gary Wayne; Cuneo, Michael Edward; Harvey-Thompson, Adam James; Herrmann, Mark C.; Hess, Mark Harry; Lamppa, Derek C.; Martin, Matthew R.; McBride, Ryan D.; Peterson, Kyle J.; Porter, John L.; Rochau, Gregory A.; Savage, Mark E.; Schroen, Diana G.; Stygar, William A.; Vesey, Roger Alan

    2015-04-29

    In this study, the magnetized liner inertial fusion concept [S. A. Slutz et al., Phys. Plasmas17, 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 1012 have been produced. X-ray emission from the fuel at stagnation had widths ranging from 50 to 110 ?m over a roughly 80% of the axial extent of the target (68 mm) and lasted approximately 2 ns. X-ray yields from these experiments are consistent with a stagnation density of the hot fuel equal to 0.20.4 g/cm3. In these experiments, up to 5 1010 secondary deuterium-tritium neutrons were produced. Given that the areal density of the plasma was approximately 12 mg/cm2, 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 1010. 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.

  8. Experimental demonstration of fusion-relevant conditions in magnetized liner inertial fusion

    SciTech Connect (OSTI)

    Gomez, Matthew R.; Slutz, Stephen A..; Sefkow, Adam B.; Sinars, Daniel B.; Hahn, Kelly D.; Hansen, Stephanie B.; Harding, Eric C.; Knapp, Patrick F.; Schmit, Paul F.; Jennings, Christopher A.; Awe, Thomas James; Geissel, Matthias; Rovang, Dean C.; Chandler, Gordon A.; Cooper, Gary Wayne; Cuneo, Michael Edward; Harvey-Thompson, Adam James; Herrmann, Mark; Hess, M. H.; Johns, Owen; Lamppa, Derek C.; Martin, Matthew R.; McBride, Ryan D.; Peterson, Kyle J.; Porter, John L.; Robertson, Grafton Kincannon; Rochau, Gregory A.; Ruiz, Carlos L.; Savage, Mark E.; Smith, Ian C.; Stygar, William A.; Vesey, Roger A.

    2014-10-06

    This Letter presents results from the first fully integrated experiments testing the magnetized liner inertial fusion concept [S.A. Slutz et al., Phys. Plasmas 17, 056303 (2010)], in which a cylinder of deuterium gas with a preimposed axial magnetic field of 10 T is heated by Z beamlet, a 2.5 kJ, 1 TW laser, and magnetically imploded by a 19 MA current with 100 ns rise time on the Z facility. Despite a predicted peak implosion velocity of only 70 km/s, the fuel reaches a stagnation temperature of approximately 3 keV, with Te ? Ti, and produces up to 2e12 thermonuclear DD neutrons. In this study, X-ray emission indicates a hot fuel region with full width at half maximum ranging from 60 to 120 ?m over a 6 mm height and lasting approximately 2 ns. The number of secondary deuterium-tritium neutrons observed was greater than 1010, indicating significant fuel magnetization given that the estimated radial areal density of the plasma is only 2 mg/cm2.

  9. A comparison of hydrogen vs. helium glow discharge effects on fusion device first-wall conditioning

    SciTech Connect (OSTI)

    Dylla, H.F.

    1989-09-01

    Hydrogen- and deuterium-fueled glow discharges are used for the initial conditioning of magnetic fusion device vacuum vessels following evacuation from atmospheric pressure. Hydrogenic glow discharge conditioning (GDC) significantly reduces the near-surface concentration of simple adsorbates, such as H/sub 2/O, CO, and CH/sub 4/, and lowers ion-induced desorption coefficients by typically three orders of magnitude. The time evolution of the residual gas production observed during hydrogen-glow discharge conditioning of the carbon first-wall structure of the TFTR device is similar to the time evolution observed during hydrogen GDC of the initial first-wall configuration in TFTR, which was primarily stainless steel. Recently, helium GDC has been investigated for several wall-conditioning tasks on a number of tokamaks including TFTR. Helium GDC shows negligible impurity removal with stainless steel walls. For impurity conditioning with carbon walls, helium GDC shows significant desorption of H/sub 2/O, CO, and CO/sub 2/; however, the total desorption yield is limited to the monolayer range. In addition, helium GDC can be used to displace hydrogen isotopes from the near-surface region of carbon first-walls in order to lower hydrogenic retention and recycling. 38 refs., 6 figs.

  10. Effect of delivery condition on desorption rate of ZrCo metal hydride bed for fusion fuel cycle

    SciTech Connect (OSTI)

    Kang, H.G.; Yun, S.H.; Chung, D.; Oh, Y.H.; Chang, M.H.; Cho, S.; Chung, H.; Song, K.M.

    2015-03-15

    For the safety of fusion fuel cycle, hydrogen isotope gases including tritium are stored as metal hydride form. To satisfy fueling requirement of fusion machine, rapid delivery from metal hydride bed is one of major factors for the development of tritium storage and delivery system. Desorption from metal hydride depends on the operation scenario by pressure and temperature control of the bed. The effect of operation scenario and pump performance on desorption rate of metal hydride bed was experimentally investigated using ZrCo bed. The results showed that the condition of pre-heating scenario before actual delivery of gas affected the delivery performance. Different pumps were connected to desorption line from bed and the effect of pump capacity on desorption rate were also found to be significant. (authors)

  11. Intense fusion neutron sources

    SciTech Connect (OSTI)

    Kuteev, B. V.; Goncharov, P. R.; Sergeev, V. Yu.; Khripunov, V. I.

    2010-04-15

    The review describes physical principles underlying efficient production of free neutrons, up-to-date possibilities and prospects of creating fission and fusion neutron sources with intensities of 10{sup 15}-10{sup 21} neutrons/s, and schemes of production and application of neutrons in fusion-fission hybrid systems. The physical processes and parameters of high-temperature plasmas are considered at which optimal conditions for producing the largest number of fusion neutrons in systems with magnetic and inertial plasma confinement are achieved. The proposed plasma methods for neutron production are compared with other methods based on fusion reactions in nonplasma media, fission reactions, spallation, and muon catalysis. At present, intense neutron fluxes are mainly used in nanotechnology, biotechnology, material science, and military and fundamental research. In the near future (10-20 years), it will be possible to apply high-power neutron sources in fusion-fission hybrid systems for producing hydrogen, electric power, and technological heat, as well as for manufacturing synthetic nuclear fuel and closing the nuclear fuel cycle. Neutron sources with intensities approaching 10{sup 20} neutrons/s may radically change the structure of power industry and considerably influence the fundamental and applied science and innovation technologies. Along with utilizing the energy produced in fusion reactions, the achievement of such high neutron intensities may stimulate wide application of subcritical fast nuclear reactors controlled by neutron sources. Superpower neutron sources will allow one to solve many problems of neutron diagnostics, monitor nano-and biological objects, and carry out radiation testing and modification of volumetric properties of materials at the industrial level. Such sources will considerably (up to 100 times) improve the accuracy of neutron physics experiments and will provide a better understanding of the structure of matter, including that of the neutron itself.

  12. Magneto-Inertial Fusion

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Wurden, G. A.; Hsu, S. C.; Intrator, T. P.; Grabowski, T. C.; Degnan, J. H.; Domonkos, M.; Turchi, P. J.; Campbell, E. M.; Sinars, D. B.; Herrmann, M. C.; et al

    2015-11-17

    In this community white paper, we describe an approach to achieving fusion which employs a hybrid of elements from the traditional magnetic and inertial fusion concepts, called magneto-inertial fusion (MIF). The status of MIF research in North America at multiple institutions is summarized including recent progress, research opportunities, and future plans.

  13. Effects of Fusion Zone Size and Failure Mode on Peak Load and Energy Absorption of Advanced High Strength Steel Spot Welds under Lap Shear Loading Conditions

    SciTech Connect (OSTI)

    Sun, Xin; Stephens, Elizabeth V.; Khaleel, Mohammad A.

    2008-06-01

    This paper examines the effects of fusion zone size on failure modes, static strength and energy absorption of resistance spot welds (RSW) of advanced high strength steels (AHSS) under lap shear loading condition. DP800 and TRIP800 spot welds are considered. The main failure modes for spot welds are nugget pullout and interfacial fracture. Partial interfacial fracture is also observed. Static weld strength tests using lap shear samples were performed on the joint populations with various fusion zone sizes. The resulted peak load and energy absorption levels associated with each failure mode were studied for all the weld populations using statistical data analysis tools. The results in this study show that AHSS spot welds with conventionally required fusion zone size of can not produce nugget pullout mode for both the DP800 and TRIP800 welds under lap shear loading. Moreover, failure mode has strong influence on weld peak load and energy absorption for all the DP800 welds and the TRIP800 small welds: welds failed in pullout mode have statistically higher strength and energy absorption than those failed in interfacial fracture mode. For TRIP800 welds above the critical fusion zone level, the influence of weld failure modes on peak load and energy absorption diminishes. Scatter plots of peak load and energy absorption versus weld fusion zone size were then constructed, and the results indicate that fusion zone size is the most critical factor in weld quality in terms of peak load and energy absorption for both DP800 and TRIP800 spot welds.

  14. Photons & Fusion Newsletter - 2014

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    4 Photons & Fusion Newsletter - 2014 February Photons & Fusion is a monthly review of science and technology at the National Ignition Facility & Photon Science Directorate. For more information, submit a question. Nature Article Reports on Fuel Gain Achieved In NIF High-Foot Experiments A key step on the way to ignition on NIF is for the energy generated through fusion reactions in an inertially confined fusion plasma to exceed the amount of energy deposited into the

  15. The Role of Lithium Conditioning in Achieving High Performance, Long Pulse H-mode Discharges in the NSTX and EAST Devices

    SciTech Connect (OSTI)

    Maingi, Rajesh; Mansfield, D. K.; Gong, X. Z.; Sun, Z.; Bell, M. G.

    2014-10-01

    In this paper, the role of lithium wall conditioning on the achievement of high performance, long pulse discharges in the National Spherical Torus Experiment (NSTX) and the Experimental Advanced Superconducting Tokamak (EAST) is documented. Common observations include recycling reduction and elimination of ELMs. In NSTX, lithium conditioning typically resulted in ELM-free operation with impurity accumulation, which was ameliorated e.g. with pulsed 3D fields to trigger controlled ELMs. Active lithium conditioning in EAST discharges has overcome this problem, producing an ELM-free Hmode with controlled density and impurities.

  16. Magnetic fusion reactor economics

    SciTech Connect (OSTI)

    Krakowski, R.A.

    1995-12-01

    An almost primordial trend in the conversion and use of energy is an increased complexity and cost of conversion systems designed to utilize cheaper and more-abundant fuels; this trend is exemplified by the progression fossil fission {yields} fusion. The present projections of the latter indicate that capital costs of the fusion ``burner`` far exceed any commensurate savings associated with the cheapest and most-abundant of fuels. These projections suggest competitive fusion power only if internal costs associate with the use of fossil or fission fuels emerge to make them either uneconomic, unacceptable, or both with respect to expensive fusion systems. This ``implementation-by-default`` plan for fusion is re-examined by identifying in general terms fusion power-plant embodiments that might compete favorably under conditions where internal costs (both economic and environmental) of fossil and/or fission are not as great as is needed to justify the contemporary vision for fusion power. Competitive fusion power in this context will require a significant broadening of an overly focused program to explore the physics and simbiotic technologies leading to more compact, simplified, and efficient plasma-confinement configurations that reside at the heart of an attractive fusion power plant.

  17. Realizing Technologies for Magnetized Target Fusion

    SciTech Connect (OSTI)

    Wurden, Glen A.

    2012-08-24

    Researchers are making progress with a range of magneto-inertial fusion (MIF) concepts. All of these approaches use the addition of a magnetic field to a target plasma, and then compress the plasma to fusion conditions. The beauty of MIF is that driver power requirements are reduced, compared to classical inertial fusion approaches, and simultaneously the compression timescales can be longer, and required implosion velocities are slower. The presence of a sufficiently large Bfield expands the accessibility to ignition, even at lower values of the density-radius product, and can confine fusion alphas. A key constraint is that the lifetime of the MIF target plasma has to be matched to the timescale of the driver technology (whether liners, heavy ions, or lasers). To achieve sufficient burn-up fraction, scaling suggests that larger yields are more effective. To handle the larger yields (GJ level), thick liquid wall chambers are certainly desired (no plasma/neutron damage materials problem) and probably required. With larger yields, slower repetition rates ({approx}0.1-1 Hz) for this intrinsically pulsed approach to fusion are possible, which means that chamber clearing between pulses can be accomplished on timescales that are compatible with simple clearing techniques (flowing liquid droplet curtains). However, demonstration of the required reliable delivery of hundreds of MJ of energy, for millions of pulses per year, is an ongoing pulsed power technical challenge.

  18. Fusion energy

    SciTech Connect (OSTI)

    Baylor, Larry

    2014-05-02

    Larry Baylor explains how the US ITER team is working to prevent solar flare-like events at a fusion energy reactor that will be like a small sun on earth

  19. Fusion energy

    ScienceCinema (OSTI)

    Baylor, Larry

    2014-05-23

    Larry Baylor explains how the US ITER team is working to prevent solar flare-like events at a fusion energy reactor that will be like a small sun on earth

  20. Experimental Fusion Research | Princeton Plasma Physics Lab

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    Experimental Fusion Research PPPL fusion research centers on the National Spherical Torus Experiment (NSTX), which is undergoing a $94 million upgrade that will make it the most powerful experimental fusion facility, or tokamak, of its type in the world when work is completed in 2014. Experiments will test the ability of the upgraded spherical facility to maintain a high-performance plasma under conditions of extreme heat and power. Results could strongly influence the design of future fusion

  1. US ITER - Why Fusion?

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    US Fusion Research Sites US Fusion Research Sites DOE Office of Science: US Fusion Energy Sciences Program Fusion Power Associates General Atomics DIIII-D National Fusion Facility Georgia Tech: Fusion Research Center Lawrence Livermore National Laboratory: National Ignition Facility Los Alamos National Laboratory: Fusion Energy Sciences MIT: Plasma Science and Fusion Center Naval Research Laboratory: Plasma Physics Division Oak Ridge National Laboratory: Fusion Energy Division Princeton Plasma

  2. (Fusion energy research)

    SciTech Connect (OSTI)

    Phillips, C.A.

    1988-01-01

    This report discusses the following topics: principal parameters achieved in experimental devices (FY88); tokamak fusion test reactor; Princeton beta Experiment-Modification; S-1 Spheromak; current drive experiment; x-ray laser studies; spacecraft glow experiment; plasma deposition and etching of thin films; theoretical plasma; tokamak modeling; compact ignition tokamak; international thermonuclear experimental reactor; Engineering Department; Project Planning and Safety Office; quality assurance and reliability; and technology transfer.

  3. The National Ignition Facility and the Path to Fusion Energy

    SciTech Connect (OSTI)

    Moses, E

    2011-07-26

    The National Ignition Facility (NIF) is operational and conducting experiments at the Lawrence Livermore National Laboratory (LLNL). The NIF is the world's largest and most energetic laser experimental facility with 192 beams capable of delivering 1.8 megajoules of 500-terawatt ultraviolet laser energy, over 60 times more energy than any previous laser system. The NIF can create temperatures of more than 100 million degrees and pressures more than 100 billion times Earth's atmospheric pressure. These conditions, similar to those at the center of the sun, have never been created in the laboratory and will allow scientists to probe the physics of planetary interiors, supernovae, black holes, and other phenomena. The NIF's laser beams are designed to compress fusion targets to the conditions required for thermonuclear burn, liberating more energy than is required to initiate the fusion reactions. Experiments on the NIF are focusing on demonstrating fusion ignition and burn via inertial confinement fusion (ICF). The ignition program is conducted via the National Ignition Campaign (NIC) - a partnership among LLNL, Los Alamos National Laboratory, Sandia National Laboratories, University of Rochester Laboratory for Laser Energetics, and General Atomics. The NIC program has also established collaborations with the Atomic Weapons Establishment in the United Kingdom, Commissariat a Energie Atomique in France, Massachusetts Institute of Technology, Lawrence Berkeley National Laboratory, and many others. Ignition experiments have begun that form the basis of the overall NIF strategy for achieving ignition. Accomplishing this goal will demonstrate the feasibility of fusion as a source of limitless, clean energy for the future. This paper discusses the current status of the NIC, the experimental steps needed toward achieving ignition and the steps required to demonstrate and enable the delivery of fusion energy as a viable carbon-free energy source.

  4. Magnetized Target Fusion Collaboration. Final report

    SciTech Connect (OSTI)

    John Slough

    2012-04-18

    Nuclear fusion has the potential to satisfy the prodigious power that the world will demand in the future, but it has yet to be harnessed as a practical energy source. The entry of fusion as a viable, competitive source of power has been stymied by the challenge of finding an economical way to provide for the confinement and heating of the plasma fuel. It is the contention here that a simpler path to fusion can be achieved by creating fusion conditions in a different regime at small scale (~ a few cm). One such program now under study, referred to as Magnetized Target Fusion (MTF), is directed at obtaining fusion in this high energy density regime by rapidly compressing a compact toroidal plasmoid commonly referred to as a Field Reversed Configuration (FRC). To make fusion practical at this smaller scale, an efficient method for compressing the FRC to fusion gain conditions is required. In one variant of MTF a conducting metal shell is imploded electrically. This radially compresses and heats the FRC plasmoid to fusion conditions. The closed magnetic field in the target plasmoid suppresses the thermal transport to the confining shell, thus lowering the imploding power needed to compress the target. The undertaking described in this report was to provide a suitable target FRC, as well as a simple and robust method for inserting and stopping the FRC within the imploding liner. The FRC must also survive during the time it takes for the metal liner to compress the FRC target. The initial work at the UW was focused on developing adequate preionization and flux trapping that were found to be essential in past experiments for obtaining the density, flux and most critically, FRC lifetime required for MTF. The timescale for testing and development of such a source can be rapidly accelerated by taking advantage of a new facility funded by the Department of Energy. At this facility, two inductive plasma accelerators (IPA) were constructed and tested. Recent experiments with these IPAs have demonstrated the ability to rapidly form, accelerate and merge two hypervelocity FRCs into a compression chamber. The resultant FRC that was formed was hot (T{sub ion} ~ 400 eV), stationary, and stable with a configuration lifetime several times that necessary for the MTF liner experiments. The accelerator length was less than 1 meter, and the time from the initiation of formation to the establishment of the final equilibrium was less than 10 microseconds. With some modification, each accelerator can be made capable of producing FRCs suitable for the production of the target plasma for the MTF liner experiment. Based on the initial FRC merging/compression results, the design and methodology for an experimental realization of the target plasma for the MTF liner experiment can now be defined. The construction and testing of the key components for the formation of the target plasma at the Air Force Research Laboratory (AFRL) will be performed on the IPA experiment, now at MSNW. A high density FRC plasmoid will be formed and accelerated out of each IPA into a merging/compression chamber similar to the imploding liner at AFRL. The properties of the resultant FRC plasma (size, temperature, density, flux, lifetime) will be obtained. The process will be optimized, and a final design for implementation at AFRL will be carried out. When implemented at AFRL it is anticipated that the colliding/merging FRCs will then be compressed by the liner. In this manner it is hoped that ultimately a plasma with ion temperatures reaching the 10 keV range and fusion gain near unity can be obtained.

  5. Fusion Power

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Power www.pppl.gov FACT SHEET FUSION POWER Check us out on YouTube. http://www.youtube.com/ppplab Find us on Facebook. http://www.facebook.com/PPPLab Follow us on Twitter. @PPPLab Access our RSS feed @PPPLab Deuterium Electron Proton Hydrogen Tritium Neutron For centuries, the way in which the sun and stars produce their energy remained a mystery to man. During the twentieth century, scientists discovered that they produce their energy by the fusion process. E=mc 2 , Albert Einstein's familiar

  6. Fusion Power | Princeton Plasma Physics Lab

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    Fusion Power For centuries, the way in which the sun and stars produce their energy remained a mystery to man. During the twentieth century, scientists discovered that they produce their energy through the fusion of light atoms. E=mc2, Albert Einstein's familiar formula, provided the basis for understanding fusion. Einstein's theory that mass can be converted into energy was further explored by other physicists who discovered two practical methods for achieving this conversion. Publication File:

  7. Scientific Achievement

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    introduced the general principles for achieving maximal viola6on of detailed balance in thermal radia6on, i.e. unity difference between direc6onal spectral e missivity a nd a...

  8. Scientific Achievement

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    have shown that even higher maximum solar cell efficiencies can be achieved by using "spectrum---spli;ng" geometries that combine strong light trapping and r adiave c oupling....

  9. US ITER | Why Fusion?

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Why Fusion? US Fusion Research Educational Resources Why Fusion? Home > Why Fusion? What is Fusion? Fusion is a key element in long-term US energy plans. ITER will allow scientists to explore the physics of a burning plasma at energy densities close to that of a commercial power plant. This is a critical step towards producing and delivering electricity from fusion to the grid. Nuclear fusion occurs naturally in stars, like our sun. When hydrogen gets hot enough, the process of fusion

  10. Measuring time of flight of fusion products in an inertial electrostatic confinement fusion device for spatial profiling of fusion reactions

    SciTech Connect (OSTI)

    Donovan, D. C.; Boris, D. R.; Kulcinski, G. L.; Santarius, J. F.; Piefer, G. R.

    2013-03-15

    A new diagnostic has been developed that uses the time of flight (TOF) of the products from a nuclear fusion reaction to determine the location where the fusion reaction occurred. The TOF diagnostic uses charged particle detectors on opposing sides of the inertial electrostatic confinement (IEC) device that are coupled to high resolution timing electronics to measure the spatial profile of fusion reactions occurring between the two charged particle detectors. This diagnostic was constructed and tested by the University of Wisconsin-Madison Inertial Electrostatic Confinement Fusion Group in the IEC device, HOMER, which accelerates deuterium ions to fusion relevant energies in a high voltage ({approx}100 kV), spherically symmetric, electrostatic potential well [J. F. Santarius, G. L. Kulcinski, R. P. Ashley, D. R. Boris, B. B. Cipiti, S. K. Murali, G. R. Piefer, R. F. Radel, T. E. Radel, and A. L. Wehmeyer, Fusion Sci. Technol. 47, 1238 (2005)]. The TOF diagnostic detects the products of D(d,p)T reactions and determines where along a chord through the device the fusion event occurred. The diagnostic is also capable of using charged particle spectroscopy to determine the Doppler shift imparted to the fusion products by the center of mass energy of the fusion reactants. The TOF diagnostic is thus able to collect spatial profiles of the fusion reaction density along a chord through the device, coupled with the center of mass energy of the reactions occurring at each location. This provides levels of diagnostic detail never before achieved on an IEC device.

  11. Fusion Energy Sciences

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Fusion Energy Sciences Fusion Energy Sciences Expanding the fundamental understanding of matter at very high temperatures and densities and to build the scientific foundation ...

  12. Neutron scattering effects on fusion ion temperature measurements.

    SciTech Connect (OSTI)

    Ziegler, Lee (Bechtel/Nevada, Las Vegas, NV); Starner, Jason R.; Cooper, Gary Wayne; Ruiz, Carlos L.; Franklin, James Kenneth (Ktech Corporation, Albuquerque, NM); Casey, Daniel T.

    2006-06-01

    To support the nuclear fusion program at Sandia National Laboratories (SNL), a consistent and verifiable method to determine fusion ion temperatures needs to be developed. Since the fusion temperature directly affects the width in the spread of neutron energies produced, a measurement of the neutron energy width can yield the fusion temperature. Traditionally, the spread in neutron energies is measured by using time-of-flight to convert a spread in neutron energies at the source to a spread in time at detector. One potential obstacle to using this technique at the Z facility at SNL is the need to shield the neutron detectors from the intense bremsstrahlung produced. The shielding consists of eight inches of lead and the concern is that neutrons will scatter in the lead, artificially broaden the neutron pulse width and lead to an erroneous measurement. To address this issue, experiments were performed at the University of Rochester's Laboratory for Laser Energetics, which demonstrated that a reliable ion temperature measurement can be achieved behind eight inches of lead shielding. To further expand upon this finding, Monte Carlo N-Particle eXtended (MCNPX) was used to simulate the experimental geometric conditions and perform the neutron transport. MCNPX was able to confidently estimate results observed at the University of Rochester.

  13. Fixed conditions for achieving the real-valued partition function of one-dimensional Gross-Pitaevskii equation coupled with time-dependent potential

    SciTech Connect (OSTI)

    Prayitno, T. B.

    2014-03-24

    We have imposed the conditions in order to preserve the real-valued partition function in the case of onedimensional Gross-Pitaevskii equation coupled by time-dependent potential. In this case we have solved the Gross-Pitaevskii equation by means of the time-dependent perturbation theory by extending the previous work of Kivshar et al. [Phys. Lett A 278, 225–230 (2001)]. To use the method, we have treated the equation as the macroscopic quantum oscillator and found that the expression of the partition function explicitly has complex values. In fact, we have to choose not only the appropriate functions but also the suitable several values of the potential to keep the real-valued partition function.

  14. US ITER - Why Fusion?

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    Educational Resources Fusion Educational Resources DOE Office of Science Fusion Energy Programs Education Links FuseNet: The European Fusion Education Network General Atomics Fusion Education PPPL Science Education Program PPPL FusEdWeb Educational Outreach: US ITER staff members are available for presentations on fusion energy and the ITER project to technical, civic, community, and student groups. To make arrangements for a speaker, please contact Mark Uhran, Communications Manager,

  15. Fusion Energy Sciences

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    Fusion Energy Sciences Fusion Energy Sciences Expanding the fundamental understanding of matter at very high temperatures and densities and to build the scientific foundation needed to develop a fusion energy source. Get Expertise Don Rej (505) 665-1883 Email Building the scientific foundation needed to develop a fusion energy source The mission of the DOE Office of Science's Fusion Energy Sciences (FES) program is to expand the fundamental understanding of matter at very high temperatures and

  16. Fusion Power Associates Awards

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    Fusion Power Associates Awards Fusion Power Associates is "a non-profit, tax-exempt research and educational foundation, providing information on the status of fusion development and other applications of plasma science and fusion research". The Association makes awards in four categories: Distinguished Career Awards, Leadership Awards, Excellence in Fusion Engineering, and Special Awards. Since 1987, Distinguished Career Awards have been presented "to individuals who have made

  17. Fusion heating technology

    SciTech Connect (OSTI)

    Cole, A.J.

    1982-06-01

    John Lawson established the criterion that in order to produce more energy from fusion than is necessary to heat the plasma and replenish the radiation losses, a minimum value for both the product of plasma density and confinement time t, and the temperature must be achieved. There are two types of plasma heating: neutral beam and electromagnetic wave heating. A neutral beam system is shown. Main development work on negative ion beamlines has focused on the difficult problem of the production of high current sources. The development of a 30 keV-1 ampere multisecond source module is close to being accomplished. In electromagnetic heating, the launcher, which provides the means of coupling the power to the plasma, is most important. The status of heating development is reviewed. Electron cyclotron resonance heating (ECRH), lower hybrid heating (HHH), and ion cyclotron resonance heating (ICRH) are reviewed.

  18. Shell stability and conditions analyzed using a new method of extracting shell areal density maps from spectrally resolved images of direct-drive inertial confinement fusion implosions

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Johns, H. M.; Mancini, R. C.; Nagayama, T.; Mayes, D. C.; Tommasini, R.; Smalyuk, V. A.; Regan, S. P.; Delettrez, J. A.

    2016-01-25

    In warm target direct-drive ICF implosion experiments performed at the OMEGA laser facility, plastic microballoons doped with a titanium tracer layer in the shell and filled with deuterium gas were imploded using a low-adiabat shaped laser pulse. Continuum radiation emitted in the core is transmitted through the tracer layer and the resulting spectrum recorded with a gated multi-monochromatic x-ray imager (MMI). Titanium K-shell line absorption spectra observed in the data are due to transitions in L-shell titanium ions driven by the backlighting continuum. The MMI data consist of an array of spectrally resolved images of the implosion. These 2-D space-resolvedmore » titanium spectral features constrain the plasma conditions and areal density of the titanium doped region of the shell. The MMI data were processed to obtain narrow-band images and space resolved spectra of titanium spectral features. Shell areal density maps, ρL(x,y), extracted using a new method using both narrow-band images and space resolved spectra are confirmed to be consistent within uncertainties. We report plasma conditions in the titanium-doped region of electron temperature (Te) = 400±28eV, electron number density (Ne) = 8.5x1024±2.5x1024 cm-3, and average areal density <ρR> = 86±7mg/cm2. Fourier analysis of areal density maps reveals shell modulations caused by hydrodynamic instability growth near the fuel-shell interface in the deceleration phase. We observe significant structure in modes l = 2-9, dominated by l = 2. We extract a target breakup fraction of 7.1±1.5% from our Fourier analysis. A new method for estimating mix width is evaluated against existing literature and our target breakup fraction. We estimate a mix width of 10.5±1μm.« less

  19. Final report on the Magnetized Target Fusion Collaboration

    SciTech Connect (OSTI)

    John Slough

    2009-09-08

    Nuclear fusion has the potential to satisfy the prodigious power that the world will demand in the future, but it has yet to be harnessed as a practical energy source. The entry of fusion as a viable, competitive source of power has been stymied by the challenge of finding an economical way to provide for the confinement and heating of the plasma fuel. It is the contention here that a simpler path to fusion can be achieved by creating fusion conditions in a different regime at small scale (~ a few cm). One such program now under study, referred to as Magnetized Target Fusion (MTF), is directed at obtaining fusion in this high energy density regime by rapidly compressing a compact toroidal plasmoid commonly referred to as a Field Reversed Configuration (FRC). To make fusion practical at this smaller scale, an efficient method for compressing the FRC to fusion gain conditions is required. In one variant of MTF a conducting metal shell is imploded electrically. This radially compresses and heats the FRC plasmoid to fusion conditions. The closed magnetic field in the target plasmoid suppresses the thermal transport to the confining shell, thus lowering the imploding power needed to compress the target. The undertaking to be described in this proposal is to provide a suitable target FRC, as well as a simple and robust method for inserting and stopping the FRC within the imploding liner. The timescale for testing and development can be rapidly accelerated by taking advantage of a new facility funded by the Department of Energy. At this facility, two inductive plasma accelerators (IPA) were constructed and tested. Recent experiments with these IPAs have demonstrated the ability to rapidly form, accelerate and merge two hypervelocity FRCs into a compression chamber. The resultant FRC that was formed was hot (T&ion ~ 400 eV), stationary, and stable with a configuration lifetime several times that necessary for the MTF liner experiments. The accelerator length was less than 1 meter, and the time from the initiation of formation to the establishment of the final equilibrium was less than 10 microseconds. With some modification, each accelerator was made capable of producing FRCs suitable for the production of the target plasma for the MTF liner experiment. Based on the initial FRC merging/compression results, the design and methodology for an experimental realization of the target plasma for the MTF liner experiment can now be defined. A high density FRC plasmoid is to be formed and accelerated out of each IPA into a merging/compression chamber similar to the imploding liner at AFRL. The properties of the resultant FRC plasma (size, temperature, density, flux, lifetime) are obtained in the reevant regime of interest. The process still needs to be optimized, and a final design for implementation at AFRL must now be carried out. When implemented at AFRL it is anticipated that the colliding/merging FRCs will then be compressed by the liner. In this manner it is hoped that ultimately a plasma with ion temperatures reaching the 10 keV range and fusion gain near unity can be obtained.

  20. Fusion Forum 1981

    SciTech Connect (OSTI)

    Fowler, T.K.

    1981-07-28

    This review covers the basics of the fusion process. Some research programs and their present status are mentioned. (MOW)

  1. Pre-Amplifier Module for Laser Inertial Confinement Fusion

    SciTech Connect (OSTI)

    Heebner, J E; Bowers, M W

    2008-02-06

    The Pre-Amplifier Modules (PAMs) are the heart of the National Ignition Facility (NIF), providing most of the energy gain for the most energetic laser in the world. Upon completion, NIF will be the only laboratory in which scientists can examine the fusion processes that occur inside stars, supernovae, and exploding nuclear weapons and that may someday serve as a virtually inexhaustible energy source for electricity. Consider that in a fusion power plant 50 cups of water could provide the energy comparable to 2 tons of coal. Of paramount importance for achieving laser-driven fusion ignition with the least energy input is the synchronous and symmetric compression of the target fuel--a condition known as laser power balance. NIF's 48 PAMs thus must provide energy gain in an exquisitely stable and consistent manner. While building one module that meets performance requirements is challenging enough, our design has already enabled the construction and fielding of 48 PAMs that are stable, uniform, and interchangeable. PAM systems are being tested at the University of Rochester's Laboratory for Laser Energetics, and the Atomic Weapons Enterprise of Great Britain has purchased the PAM power system.

  2. Magneto-inertial fusion (MIF) needs a

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Magneto-inertial fusion (MIF) needs a credible demonstration of the key physics principles along with validated simulation models in order to be able to adequately assess the prospects for attractive MIF energy production. SNL and the Laboratory for Laser Energetics at the University of Rochester (LLE) are working collaboratively to investigate the compression and heating of magnetized plasmas at fusion relevant conditions. This work is being conducted through a series of focused experiments

  3. Macron Formed Liner Compression as a Practical Method for Enabling Magneto-Inertial Fusion

    SciTech Connect (OSTI)

    Slough, John

    2011-12-10

    The entry of fusion as a viable, competitive source of power has been stymied by the challenge of finding an economical way to provide for the confinement and heating of the plasma fuel. The main impediment for current nuclear fusion concepts is the complexity and large mass associated with the confinement systems. To take advantage of the smaller scale, higher density regime of magnetic fusion, an efficient method for achieving the compressional heating required to reach fusion gain conditions must be found. The very compact, high energy density plasmoid commonly referred to as a Field Reversed Configuration (FRC) provides for an ideal target for this purpose. To make fusion with the FRC practical, an efficient method for repetitively compressing the FRC to fusion gain conditions is required. A novel approach to be explored in this endeavor is to remotely launch a converging array of small macro-particles (macrons) that merge and form a more massive liner inside the reactor which then radially compresses and heats the FRC plasmoid to fusion conditions. The closed magnetic field in the target FRC plasmoid suppresses the thermal transport to the confining liner significantly lowering the imploding power needed to compress the target. With the momentum flux being delivered by an assemblage of low mass, but high velocity macrons, many of the difficulties encountered with the liner implosion power technology are eliminated. The undertaking to be described in this proposal is to evaluate the feasibility achieving fusion conditions from this simple and low cost approach to fusion. During phase I the design and testing of the key components for the creation of the macron formed liner have been successfully carried out. Detailed numerical calculations of the merging, formation and radial implosion of the Macron Formed Liner (MFL) were also performed. The phase II effort will focus on an experimental demonstration of the macron launcher at full power, and the demonstration of megagauss magnetic field compression by a small array of full scale macrons. In addition the physics of the compression of an FRC to fusion conditions will be undertaken with a smaller scale MFL. The timescale for testing will be rapidly accelerated by taking advantage of other facilities at MSNW where the target FRC will be created and translated inside the MFL just prior to implosion of the MFL. Experimental success would establish the concept at the “proof of principle” level and the following phase III effort would focus on the full development of the concept into a fusion gain device. Successful operation would lead to several benefits in various fields. It would have application to high energy density physics, as well as nuclear waste transmutation and alternate fission fuel cycles. The smaller scale device could find immediate application as an intense source of neutrons for diagnostic imaging and non-invasive object interrogation.

  4. Inertial Confinement Fusion: How to Make a Star

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Inertial Confinement Fusion: How to Make a Star The idea for the National Ignition Facility (NIF) grew out of the decades-long effort to generate fusion burn and gain in the laboratory. Current nuclear power plants, which use fission, or the splitting of atoms to produce energy, have been pumping out electric power for more than 50 years. But achieving nuclear fusion burn and gain has not yet been demonstrated to be viable for electricity production. For fusion burn and gain to occur, a special

  5. Photons & Fusion Newsletter

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    photons fusion / 2012 Photons & Fusion Newsletter August 2012 Photons & Fusion is a monthly review of science and technology at the National Ignition Facility & Photon Science Directorate. For more information , submit a question. Preparing the NIF Beamlines for Routine High-Energy Operations Much more went into NIF's record-breaking two-megajoule (MJ), 500-terawatt (TW)-plus shot on July 5 than just turning up the energy of NIF's 192 powerful lasers (see the LLNL News Release). In

  6. Photons & Fusion Newsletter - 2014

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Discovery Science on NIF: Exploring the Physics of Star Formation Article on MOIRE Optics on Cover of Applied Optics Mode 1 Drive Asymmetry in NIF Inertial Confinement Fusion...

  7. Fusion Communication Summit cover

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    COMMUNICATIONS SUMMIT for U.S. Magnetic Fusion September 12-13, 2012 Princeton University - Frist Campus Center Princeton, New Jersey, USA Mission Statement Announcements...

  8. Glossary of fusion energy

    SciTech Connect (OSTI)

    Whitson, M.O.

    1982-01-01

    This glossary gives brief descriptions of approximately 400 terms used by the fusion community. Schematic diagrams and photographs of the major US experiments are also included. (MOW)

  9. Photons & Fusion Newsletter

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    2 Photons & Fusion Newsletter May 2012 Reducing the Time to Grow Good Cryogenic Layers One of the most demanding aspects of preparing targets for NIF ignition experiments is...

  10. Photons & Fusion Newsletter

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    June 2013 Photons & Fusion is a monthly review of science and technology at the National Ignition Facility & Photon Science Directorate. For more information, submit a question....

  11. Fusion and Ignition

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    science Fusion and Ignition What is Fusion? Fusion is the process that powers the sun and the stars. Fusion describes what happens when the nuclei of light atoms overcome the electrical resistance that keeps them apart and get close enough to activate the strong nuclear force that holds them together, or "fuse." When fused, they form a bigger nucleus; two elements combine to create a different element at the level of the nucleus. Making elements fuse requires an enormous amount of heat

  12. Taming Plasma Fusion Snakes

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Image credit: Linda Sugiyama Controlled nuclear fusion has held the promise of a safe, clean, sustainable energy resource for decades. Now, with concerns over global climate change ...

  13. Science DMZ Fuels Fusion Research

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Report Network Problems: trouble@es.net Provide Web Site Feedback: info@es.net Science DMZ Fuels Fusion Research General Atomics remote controls fusion experiments, bridges...

  14. Method of achieving the controlled release of thermonuclear energy

    DOE Patents [OSTI]

    Brueckner, Keith A.

    1986-01-01

    A method of achieving the controlled release of thermonuclear energy by illuminating a minute, solid density, hollow shell of a mixture of material such as deuterium and tritium with a high intensity, uniformly converging laser wave to effect an extremely rapid build-up of energy in inwardly traveling shock waves to implode the shell creating thermonuclear conditions causing a reaction of deuterons and tritons and a resultant high energy thermonuclear burn. Utilizing the resulting energy as a thermal source and to breed tritium or plutonium. The invention also contemplates a laser source wherein the flux level is increased with time to reduce the initial shock heating of fuel and provide maximum compression after implosion; and, in addition, computations and an equation are provided to enable the selection of a design having a high degree of stability and a dependable fusion performance by establishing a proper relationship between the laser energy input and the size and character of the selected material for the fusion capsule.

  15. Anomaly Detection for Resilient Control Systems Using Fuzzy-Neural Data Fusion Engine

    SciTech Connect (OSTI)

    Ondrej Linda; Milos Manic; Timothy R. McJunkin

    2011-08-01

    Resilient control systems in critical infrastructures require increased cyber-security and state-awareness. One of the necessary conditions for achieving the desired high level of resiliency is timely reporting and understanding of the status and behavioral trends of the control system. This paper describes the design and development of a neural-network based data-fusion system for increased state-awareness of resilient control systems. The proposed system consists of a dedicated data-fusion engine for each component of the control system. Each data-fusion engine implements three-layered alarm system consisting of: (1) conventional threshold-based alarms, (2) anomalous behavior detector using self-organizing maps, and (3) prediction error based alarms using neural network based signal forecasting. The proposed system was integrated with a model of the Idaho National Laboratory Hytest facility, which is a testing facility for hybrid energy systems. Experimental results demonstrate that the implemented data fusion system provides timely plant performance monitoring and cyber-state reporting.

  16. Princeton Plasma Physics Laboratory achieves milestone, completing first

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    part of heart of fusion experiment | Princeton Plasma Physics Lab Princeton Plasma Physics Laboratory achieves milestone, completing first part of heart of fusion experiment By John Greenwald March 22, 2013 Tweet Widget Google Plus One Share on Facebook The completed first section of the NSTX-U center stack. (Photo by Elle Starkman, PPPL Office of Communications) The completed first section of the NSTX-U center stack. Gallery: Related Images: Engineers and technicians at the U.S. Department

  17. Spherical torus fusion reactor

    DOE Patents [OSTI]

    Martin Peng, Y.K.M.

    1985-10-03

    The object of this invention is to provide a compact torus fusion reactor with dramatic simplification of plasma confinement design. Another object of this invention is to provide a compact torus fusion reactor with low magnetic field and small aspect ratio stable plasma confinement. In accordance with the principles of this invention there is provided a compact toroidal-type plasma confinement fusion reactor in which only the indispensable components inboard of a tokamak type of plasma confinement region, mainly a current conducting medium which carries electrical current for producing a toroidal magnet confinement field about the toroidal plasma region, are retained.

  18. HEDP and new directions for fusion energy

    SciTech Connect (OSTI)

    Kirkpatrick, Ronald C

    2009-01-01

    The Quest for fusion energy has a long history and the demonstration of thermonuclear energy release in 1951 represented a record achievement for high energy density. While this first demonstration was in response to the extreme fears of mankind, it also marked the beginning of a great hope that it would usher in an era of boundless cheap energy. In fact, fusion still promises to be an enabling technology that can be compared to the prehistoric utilization of fire. Why has the quest for fusion energy been so long on promises and so short in fulfillment? This paper briefly reviews past approaches to fusion energy and suggests new directions. By putting aside the old thinking and vigorously applying our experimental, computational and theoretical tools developed over the past decades we should be able to make rapid progress toward satisfying an urgent need. Fusion not only holds the key to abundant green energy, but also promises to enable deep space missions and the creation of rare elements and isotopes for wide-ranging industrial applications and medical diagnostics.

  19. Fusion-breeder program

    SciTech Connect (OSTI)

    Moir, R.W.

    1982-11-19

    The various approaches to a combined fusion-fission reactor for the purpose of breeding /sup 239/Pu and /sup 233/U are described. Design aspects and cost estimates for fuel production and electricity generation are discussed. (MOW)

  20. Cold nuclear fusion

    SciTech Connect (OSTI)

    Tsyganov, E. N.

    2012-02-15

    Recent accelerator experiments on fusion of various elements have clearly demonstrated that the effective cross-sections of these reactions depend on what material the target particle is placed in. In these experiments, there was a significant increase in the probability of interaction when target nuclei are imbedded in a conducting crystal or are a part of it. These experiments open a new perspective on the problem of so-called cold nuclear fusion.

  1. Fusion Materials Research at Oak Ridge National Laboratory in Fiscal Year 2014

    SciTech Connect (OSTI)

    Wiffen, Frederick W.; Noe, Susan P.; Snead, Lance Lewis

    2014-10-01

    The realization of fusion energy is a formidable challenge with significant achievements resulting from close integration of the plasma physics and applied technology disciplines. Presently, the most significant technological challenge for the near-term experiments such as ITER, and next generation fusion power systems, is the inability of current materials and components to withstand the harsh fusion nuclear environment. The overarching goal of the ORNL fusion materials program is to provide the applied materials science support and understanding to underpin the ongoing DOE Office of Science fusion energy program while developing materials for fusion power systems. In doing so the program continues to be integrated both with the larger U.S. and international fusion materials communities, and with the international fusion design and technology communities.

  2. Inertial fusion: an energy-production option for the future

    SciTech Connect (OSTI)

    Hovingh, J.; Pitts, J.H.; Monsler, M.J.; Grow, G.R.

    1982-05-01

    The authors discuss the inertial-confinement approach to fusion energy. After explaining the fundamentals of fusion, they describe the state of the art of fusion experiments, emphasizing the results achieved through the use of neodymium-doped glass lasers at Lawrence Livermore National Laboratory and at other laboratories. They highlight recent experimental results confirming theoretical predictions that short-wavelength lasers have excellent energy absorption on fuel pellets. Compressions of deuterium-tritium fuel of over 100 times liquid density have been measured, only a factor of 10 away from the compression required for a commercial reactor. Finally, it is shown how to exploit the unique characteristics of inertial fusion to design reactor chambers that have a very high power density and a long life, features that the authors believe will eventually lead to fusion power at a competitive cost.

  3. LIFE: The Case for Early Commercialization of Fusion Energy

    SciTech Connect (OSTI)

    Anklam, T; Simon, A J; Powers, S; Meier, W R

    2010-11-30

    This paper presents the case for early commercialization of laser inertial fusion energy (LIFE). Results taken from systems modeling of the US electrical generating enterprise quantify the benefits of fusion energy in terms of carbon emission, nuclear waste and plutonium production avoidance. Sensitivity of benefits-gained to timing of market-entry is presented. These results show the importance of achieving market entry in the 2030 time frame. Economic modeling results show that fusion energy can be competitive with other low-carbon energy sources. The paper concludes with a description of the LIFE commercialization path. It proposes constructing a demonstration facility capable of continuous fusion operations within 10 to 15 years. This facility will qualify the processes and materials needed for a commercial fusion power plant.

  4. ITER Fusion Energy

    ScienceCinema (OSTI)

    Dr. Norbert Holtkamp

    2010-01-08

    ITER (in Latin ?the way?) is designed to demonstrate the scientific and technological feasibility of fusion energy. Fusion is the process by which two light atomic nuclei combine to form a heavier over one and thus release energy. In the fusion process two isotopes of hydrogen ? deuterium and tritium ? fuse together to form a helium atom and a neutron. Thus fusion could provide large scale energy production without greenhouse effects; essentially limitless fuel would be available all over the world. The principal goals of ITER are to generate 500 megawatts of fusion power for periods of 300 to 500 seconds with a fusion power multiplication factor, Q, of at least 10. Q ? 10 (input power 50 MW / output power 500 MW). The ITER Organization was officially established in Cadarache, France, on 24 October 2007. The seven members engaged in the project ? China, the European Union, India, Japan, Korea, Russia and the United States ? represent more than half the world?s population. The costs for ITER are shared by the seven members. The cost for the construction will be approximately 5.5 billion Euros, a similar amount is foreseen for the twenty-year phase of operation and the subsequent decommissioning.

  5. Radiological Dose Calculations for Fusion Facilities

    SciTech Connect (OSTI)

    Michael L. Abbott; Lee C. Cadwallader; David A. Petti

    2003-04-01

    This report summarizes the results and rationale for radiological dose calculations for the maximally exposed individual during fusion accident conditions. Early doses per unit activity (Sieverts per TeraBecquerel) are given for 535 magnetic fusion isotopes of interest for several release scenarios. These data can be used for accident assessment calculations to determine if the accident consequences exceed Nuclear Regulatory Commission and Department of Energy evaluation guides. A generalized yearly dose estimate for routine releases, based on 1 Terabecquerel unit releases per radionuclide, has also been performed using averaged site parameters and assumed populations. These routine release data are useful for assessing designs against US Environmental Protection Agency yearly release limits.

  6. Technology of mirror machines: LLL facilities for magnetic mirror fusion

    Office of Scientific and Technical Information (OSTI)

    experiments (Conference) | SciTech Connect Conference: Technology of mirror machines: LLL facilities for magnetic mirror fusion experiments Citation Details In-Document Search Title: Technology of mirror machines: LLL facilities for magnetic mirror fusion experiments Significant progress in plasma confinement and temperature has been achieved in the 2XIIB facility at Livermore. These encouraging results, and their theoretical corroboration, have provided a firm basis for the design of a new

  7. Large Scale Computing and Storage Requirements for Fusion Energy Sciences:

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Target 2014 High Energy Physics (HEP) Nuclear Physics (NP) Overview Published Reports Case Study FAQs NERSC HPC Achievement Awards Share Your Research User Submitted Research Citations NERSC Citations Home » Science at NERSC » HPC Requirements Reviews » Requirements Reviews: Target 2014 » Fusion Energy Sciences (FES) Large Scale Computing and Storage Requirements for Fusion Energy Sciences: Target 2014 FESFrontcover.png An FES / ASCR / NERSC Workshop August 3-4, 2010 Final Report Large

  8. Inertial-confinement-fusion targets

    SciTech Connect (OSTI)

    Hendricks, C.D.

    1982-08-10

    Much of the research in laser fusion has been done using simple ball on-stalk targets filled with a deuterium-tritium mixture. The targets operated in the exploding pusher mode in which the laser energy was delivered in a very short time (approx. 100 ps or less) and was absorbed by the glass wall of the target. The high energy density in the glass literally exploded the shell with the inward moving glass compressing the DT fuel to high temperatures and moderate densities. Temperatures achieved were high enough to produce DT reactions and accompanying thermonuclear neutrons and alpha particles. The primary criteria imposed on the target builders were: (1) wall thickness, (2) sphere diameter, and (3) fuel in the sphere.

  9. Vanadium recycling for fusion reactors

    SciTech Connect (OSTI)

    Dolan, T.J.; Butterworth, G.J.

    1994-04-01

    Very stringent purity specifications must be applied to low activation vanadium alloys, in order to meet recycling goals requiring low residual dose rates after 50--100 years. Methods of vanadium production and purification which might meet these limits are described. Following a suitable cooling period after their use, the vanadium alloy components can be melted in a controlled atmosphere to remove volatile radioisotopes. The aim of the melting and decontamination process will be the achievement of dose rates low enough for ``hands-on`` refabrication of new reactor components from the reclaimed metal. The processes required to permit hands-on recycling appear to be technically feasible, and demonstration experiments are recommended. Background information relevant to the use of vanadium alloys in fusion reactors, including health hazards, resources, and economics, is provided.

  10. Review of the Inertial Fusion Energy Program

    SciTech Connect (OSTI)

    none,

    2004-03-29

    Igniting fusion fuel in the laboratory remains an alluring goal for two reasons: the desire to study matter under the extreme conditions needed for fusion burn, and the potential of harnessing the energy released as an attractive energy source for mankind. The inertial confinement approach to fusion involves rapidly compressing a tiny spherical capsule of fuel, initially a few millimeters in radius, to densities and temperatures higher than those in the core of the sun. The ignited plasma is confined solely by its own inertia long enough for a significant fraction of the fuel to burn before the plasma expands, cools down and the fusion reactions are quenched. The potential of this confinement approach as an attractive energy source is being studied in the Inertial Fusion Energy (IFE) program, which is the subject of this report. A complex set of interrelated requirements for IFE has motivated the study of novel potential solutions. Three types of drivers for fuel compression are presently studied: high-averagepower lasers (HAPL), heavy-ion (HI) accelerators, and Z-Pinches. The three main approaches to IFE are based on these drivers, along with the specific type of target (which contains the fuel capsule) and chamber that appear most promising for a particular driver.

  11. NERSC HPC Achievement Awards

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Call for Nominations (2016) 2016 Nomination Form 2015 Recipients 2014 Recipients 2013 Recipients Share Your Research User Submitted Research Citations NERSC Citations Home » Science at NERSC » NERSC HPC Achievement Awards NERSC HPC Achievement Awards The NERSC HPC Achievement Awards are presented annually to recognize extraordinary scientific achievement from NERSC users and to encourage the innovative use of NERSC's High Performance Computing and Data systems. NERSC users, project Principal

  12. Demonstration of thermonuclear conditions in magnetized liner inertial

    Office of Scientific and Technical Information (OSTI)

    fusion experiments (Journal Article) | DOE PAGES Demonstration of thermonuclear conditions in magnetized liner inertial fusion experiments This content will become publicly available on April 29, 2016 « Prev Next » Title: Demonstration of thermonuclear conditions in magnetized liner inertial fusion experiments In this study, the magnetized liner inertial fusion concept [S. A. Slutz et al., Phys. Plasmas17, 056303 (2010)] utilizes a magnetic field and laser heating to relax the pressure

  13. Spherical torus fusion reactor

    DOE Patents [OSTI]

    Peng, Yueng-Kay M.

    1989-01-01

    A fusion reactor is provided having a near spherical-shaped plasma with a modest central opening through which straight segments of toroidal field coils extend that carry electrical current for generating a toroidal magnet plasma confinement fields. By retaining only the indispensable components inboard of the plasma torus, principally the cooled toroidal field conductors and in some cases a vacuum containment vessel wall, the fusion reactor features an exceptionally small aspect ratio (typically about 1.5), a naturally elongated plasma cross section without extensive field shaping, requires low strength magnetic containment fields, small size and high beta. These features combine to produce a spherical torus plasma in a unique physics regime which permits compact fusion at low field and modest cost.

  14. Peaceful Uses of Fusion

    DOE R&D Accomplishments [OSTI]

    Teller, E.

    1958-07-03

    Applications of thermonuclear energy for peaceful and constructive purposes are surveyed. Developments and problems in the release and control of fusion energy are reviewed. It is pointed out that the future of thermonuclear power reactors will depend upon the construction of a machine that produces more electric energy than it consumes. The fuel for thermonuclear reactors is cheap and practically inexhaustible. Thermonuclear reactors produce less dangerous radioactive materials than fission reactors and, when once brought under control, are not as likely to be subject to dangerous excursions. The interaction of the hot plasma with magnetic fields opens the way for the direct production of electricity. It is possible that explosive fusion energy released underground may be harnessed for the production of electricity before the same feat is accomplished in controlled fusion processes. Applications of underground detonations of fission devices in mining and for the enhancement of oil flow in large low-specific-yield formations are also suggested.

  15. Simulation of Fusion Plasmas

    ScienceCinema (OSTI)

    Holland, Chris [UC San Diego, San Diego, California, United States

    2010-01-08

    The upcoming ITER experiment (www.iter.org) represents the next major milestone in realizing the promise of using nuclear fusion as a commercial energy source, by moving into the ?burning plasma? regime where the dominant heat source is the internal fusion reactions. As part of its support for the ITER mission, the US fusion community is actively developing validated predictive models of the behavior of magnetically confined plasmas. In this talk, I will describe how the plasma community is using the latest high performance computing facilities to develop and refine our models of the nonlinear, multiscale plasma dynamics, and how recent advances in experimental diagnostics are allowing us to directly test and validate these models at an unprecedented level.

  16. Fusion welding process

    DOE Patents [OSTI]

    Thomas, Kenneth C. (Export, PA); Jones, Eric D. (Salem, PA); McBride, Marvin A. (Hempfield Township, Westmoreland County, PA)

    1983-01-01

    A process for the fusion welding of nickel alloy steel members wherein a ferrite containing pellet is inserted into a cavity in one member and melted by a welding torch. The resulting weld nugget, a fusion of the nickel containing alloy from the members to be welded and the pellet, has a composition which is sufficiently low in nickel content such that ferrite phases occur within the weld nugget, resulting in improved weld properties. The steel alloys encompassed also include alloys containing carbon and manganese, considered nickel equivalents.

  17. Atomic data for fusion

    SciTech Connect (OSTI)

    Hunter, H.T.; Kirkpatrick, M.I.; Alvarez, I.; Cisneros, C.; Phaneuf, R.A.; Barnett, C.F.

    1990-07-01

    This report provides a handbook of recommended cross-section and rate-coefficient data for inelastic collisions between hydrogen, helium and lithium atoms, molecules and ions, and encompasses more than 400 different reactions of primary interest in fusion research. Published experimental and theoretical data have been collected and evaluated, and the recommended data are presented in tabular, graphical and parametrized form. Processes include excitation and spectral line emission, charge exchange, ionization, stripping, dissociation and particle interchange reactions. The range of collision energies is appropriate to applications in fusion-energy research.

  18. Fusion Energy Division: Annual progress report, period ending December 31, 1987

    SciTech Connect (OSTI)

    Morgan, O.B. Jr.; Berry, L.A.; Sheffield, J.

    1988-11-01

    The Fusion Program of Oak Ridge National Laboratory (ORNL), a major part of the national fusion program, carries out research in nearly all areas of magnetic fusion. Collaboration among staff from ORNL, Martin Marietta Energy Systems, Inc., private industry, the academic community, and other fusion laboratories, in the United States and abroad, is directed toward the development of fusion as an energy source. This report documents the program's achievements during 1987. Issued as the annual progress report of the ORNL Fusion Energy Division, it also contains information from components of the Fusion Program that are external to the division (about 15% of the program effort). The areas addressed by the Fusion Program include the following: experimental and theoretical research on magnetic confinement concepts, engineering and physics of existing and planned devices, development and testing of diagnostic tools and techniques in support of experiments, assembly and distribution to the fusion community of databases on atomic physics and radiation effects, development and testing of technologies for heating and fueling fusion plasmas, development and testing of superconducting magnets for containing fusion plasmas, and development and testing of materials for fusion devices. Highlights from program activities are included in this report. 126 figs., 15 tabs.

  19. Fusion Energy Division progress report, 1 January 1990--31 December 1991

    SciTech Connect (OSTI)

    Sheffield, J.; Baker, C.C.; Saltmarsh, M.J.

    1994-03-01

    The Fusion Program of the Oak Ridge National Laboratory (ORNL), a major part of the national fusion program, encompasses nearly all areas of magnetic fusion research. The program is directed toward the development of fusion as an economical and environmentally attractive energy source for the future. The program involves staff from ORNL, Martin Marietta Energy systems, Inc., private industry, the academic community, and other fusion laboratories, in the US and abroad. Achievements resulting from this collaboration are documented in this report, which is issued as the progress report of the ORNL Fusion Energy Division; it also contains information from components for the Fusion Program that are external to the division (about 15% of the program effort). The areas addressed by the Fusion Program include the following: experimental and theoretical research on magnetic confinement concepts; engineering and physics of existing and planned devices, including remote handling; development and testing of diagnostic tools and techniques in support of experiments; assembly and distribution to the fusion community of databases on atomic physics and radiation effects; development and testing of technologies for heating and fueling fusion plasmas; development and testing of superconducting magnets for containing fusion plasmas; development and testing of materials for fusion devices; and exploration of opportunities to apply the unique skills, technology, and techniques developed in the course of this work to other areas (about 15% of the Division`s activities). Highlights from program activities during 1990 and 1991 are presented.

  20. Physics (selected articles). [Nuclear fusion

    SciTech Connect (OSTI)

    Shiyao, Z.; Zesheng, C.; Xiaolung, X.; Qiang, H.

    1982-09-01

    Controlled nuclear fusion as a new energy source was investigated. It will be possible in the 1980's to obtain thermal nuclear ignition, and in the early 2000's nuclear fusion may be used to supplement the energy shortage. It is predicted that in the 2000's nuclear fusion will occupy an important position as a global source of energy.

  1. Measuring Energy Achievements

    Broader source: Energy.gov [DOE]

    This presentation covers types of energy measurements essential to industrial facilities and discusses the benefits of metrics. ArcelorMittal provides examples from their experience measuring energy achievements.

  2. Advances in Inertial Confinement Fusion at the National Ignition Facility (NIF)

    SciTech Connect (OSTI)

    Moses, E

    2009-10-15

    The 192-beam National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory (LLNL) in Livermore, CA, is now operational and conducting experiments. NIF, the flagship facility of the U.S. Inertial Confinement Fusion (ICF) Program, will achieve high-energy-density conditions never previously obtained in the laboratory - temperatures over 100 million K, densities of 1,000 g/cm3, and pressures exceeding 100 billion atmospheres. Such conditions exist naturally only in the interiors of the stars and during thermonuclear burn. Demonstration of ignition and thermonuclear burn in the laboratory is a major NIF goal. To date, the NIF laser has demonstrated all pulse shape, beam quality, energy, and other specifications required to meet the ignition challenge. On March 10, 2009, the NIF laser delivered 1.1 MJ of ultraviolet laser energy to target chamber center, approximately 30 times more energy than any previous facility. The ignition program at NIF is the National Ignition Campaign (NIC), a national collaboration for ignition experimentation with participation from General Atomics, LLNL, Los Alamos National Laboratory (LANL), Sandia National Laboratories (SNL), and the University of Rochester Laboratory for Laser Energetics (LLE). The achievement of ignition at NIF will demonstrate the scientific feasibility of ICF and focus worldwide attention on fusion as a viable energy option. A particular energy concept under investigation is the LIFE (Laser Inertial Fusion Energy) scheme. The LIFE engine is inherently safe, minimizes proliferation concerns associated with the nuclear fuel cycle, and can provide a sustainable carbon-free energy generation solution in the 21st century. This talk will describe NIF and its potential as a user facility and an experimental platform for high-energy-density science, NIC, and the LIFE approach for clean, sustainable energy.

  3. Fusion pumped laser

    DOE Patents [OSTI]

    Pappas, D.S.

    1987-07-31

    The apparatus of this invention may comprise a system for generating laser radiation from a high-energy neutron source. The neutron source is a tokamak fusion reactor generating a long pulse of high-energy neutrons and having a temperature and magnetic field effective to generate a neutron flux of at least 10/sup 15/ neutrons/cm/sup 2//center dot/s. Conversion means are provided adjacent the fusion reactor at a location operable for converting the high-energy neutrons to an energy source with an intensity and energy effective to excite a preselected lasing medium. A lasing medium is spaced about and responsive to the energy source to generate a population inversion effective to support laser oscillations for generating output radiation. 2 figs., 2 tabs.

  4. Photons & Fusion Newsletter

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    1 Photons & Fusion Newsletter December 2011 MIT Plasma Science Lab Develops NIF Diagnostics A typical NIF experiment is over in a few billionths of a second. Obtaining meaningful information about what occurs during this extremely brief time period, in and around a tiny target, has required the design and development of a new breed of detectors, cameras, and other diagnostic instruments, many of which have been created through partnerships with universities and national laboratories. One of

  5. Modular Aneutronic Fusion Engine

    SciTech Connect (OSTI)

    Gary Pajer, Yosef Razin, Michael Paluszek, A.H. Glasser and Samuel Cohen

    2012-05-11

    NASA's JUNO mission will arrive at Jupiter in July 2016, after nearly five years in space. Since operational costs tend to rise with mission time, minimizing such times becomes a top priority. We present the conceptual design for a 10MW aneutronic fusion engine with high exhaust velocities that would reduce transit time for a Jupiter mission to eighteen months and enable more challenging exploration missions in the solar system and beyond. __________________________________________________

  6. for Achieving Programmatic Savings

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    1: Model for Achieving Programmatic Savings Issues: Issue 1 - EEI Allocation Methodology using TOCAs (affirmed by the group to continue with the status quo). Issue 2 - Two-Year...

  7. Cooling Fusion in a Flash | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Cooling Fusion in a Flash American Fusion News Category: U.S. Universities Link: Cooling Fusion in a Flash

  8. COLLOQUIUM: Magnetized Target Fusion Work at General Fusion | Princeton

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Plasma Physics Lab December 18, 2014, 12:30pm to 2:00pm Colloquia MBG Auditorium COLLOQUIUM: Magnetized Target Fusion Work at General Fusion Dr. Michel Laberge General Fusion FOR THIS COLLOQUIUM - PLEASE NOTE SPECIAL TIME OF 12:30PM General Fusion is working on compressing a Compact Torus in liquid metal using an acoustic wave generated by compressed gas pistons. This approach has attractive reactor engineering features: strongly reduced neutrons damage (1E-5 reduction in neutron flux with

  9. Inspection of Fusion Joints in Plastic Pipe

    SciTech Connect (OSTI)

    Connie Reichert

    2005-09-01

    The standard method of joining plastic pipe in the field is the butt fusion process. As in any pipeline application, joint quality greatly affects overall operational safety of the system. Currently no simple, reliable, cost-effective method exists for assessing the quality of fusion joints in the field. Visual examination and pressure testing are current nondestructive approaches, which do not provide any assurance about the long-term pipeline performance. This project developed, demonstrated, and validated an in-situ nondestructive inspection method for butt fusion joints in gas distribution plastic pipelines. The inspection system includes a laser-based image-recognition system that automatically generates and interprets digital images of pipe joints and assigns them a pass/fail rating, which eliminates operator bias in evaluating joint quality. An EWI-patented process, the Weld Zone Inspection Method (WZIM) was developed in which local heat is applied to the joint region to relax the residual stresses formed by the original joining operation, which reveals the surface condition of the joint. In cases where the joint is not formed under optimal conditions, and the intermolecular forces between contacting surfaces are not strong enough, the relaxation of macromolecules in the surface layer causes the material to pull back, revealing a fusion line. If the joint is sound, the bond line image does not develop. To establish initial feasibility of the approach, welds were performed under standard and nonstandard conditions. These welds were subjected to the WZIM and two destructive forms of testing: short-term tensile testing and long-term creep rupture testing. There appears to be a direct correlation between the WZIM and the destructive testing results. Although WZIM appears to be more sensitive than destructive testing can verify, the approach appears valid.

  10. Characteristics of irradiation creep in the first wall of a fusion reactor

    SciTech Connect (OSTI)

    Coghlan, W.A.; Mansur, L.K.

    1981-01-01

    A number of significant differences in the irradiation environment of a fusion reactor are expected with respect to the fission reactor irradiation environment. These differences are expected to affect the characteristics of irradiation creep in the fusion reactor. Special conditions of importance are identified as the (1) large number of defects produced per pka, (2) high helium production rate, (3) cyclic operation, (4) unique stress histories, and (5) low temperature operations. Existing experimental data from the fission reactor environment is analyzed to shed light on irradiation creep under fusion conditions. Theoretical considerations are used to deduce additional characteristics of irradiation creep in the fusion reactor environment for which no experimental data are available.

  11. Fusion Rockets for Planetary Defense

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ... and Y. Nakao, Field Reversed Configuration (FRC) Fusion Rocket,'' Proc. 11th Symp. ... 1988 Tandem Mirror 1.2 Chapman 1989 FRC -- Haloulakis 1989 Colliding Spheromaks -- ...

  12. Fusion, mechanical joining methods pros, cons--Part 2. [Natural gas pipelines use of mechanical and fusion joints

    SciTech Connect (OSTI)

    Gunther, K.M. )

    1993-10-01

    Two basic techniques accepted by gas distribution utility companies for joining polyethylene pipe underground are fusion methods and mechanical joining. Washington Gas Light Co., uses the fusion methods for the most part and uses mechanical joints for repair and final tie-ins where fusion methods are impractical or impossible to use. Fusion methods used by gas industry users of plastic pipe are: butt fusion; socket fusion; saddle fusion; electrofusion. Mechanical pipe joining techniques or procedures include: factory made mechanical joints such as meter risers and transition fittings; hydraulic compression couplings; bolted and screwed compression couplings; stab type compression couplings; interior seal couplings. Every joining method has strengths, weaknesses, pitfalls and ways they can fail in service. The key is making the best selection based on such factors as location, temperature, conditions, available equipment, personnel training level and cost. No one method will do it all or every company would be using that particular method. Part 2 focuses on strengths, weaknesses, pitfalls and failure possibilities of the five mechanical techniques.

  13. Peregrinations on cold fusion

    SciTech Connect (OSTI)

    Turner, L.

    1989-01-01

    Attention is focused on the possibility of resonance-enhanced deuteron Coulomb barrier penetration. Because of the many-body nature of the interactions of room-temperature deuterons diffusing through a lattice possessing deuterons in many of the interstitial positions, the diffusing deuterons can resonate on the atomic scale in the potential wells bounded by the ascending walls of adjacent Coulomb barriers and thereby penetrate the Coulomb barriers in a fashion vastly underestimated by two-body calculations in which wells for possible resonance are absent. Indeed, perhaps the lack of robust reproducibility in cold fusion originates from the narrowness of such transmission resonances. 4 refs., 1 fig.

  14. Fusion reactor pumped laser

    DOE Patents [OSTI]

    Jassby, Daniel L. (Princeton, NJ)

    1988-01-01

    A nuclear pumped laser capable of producing long pulses of very high power laser radiation is provided. A toroidal fusion reactor provides energetic neutrons which are slowed down by a moderator. The moderated neutrons are converted to energetic particles capable of pumping a lasing medium. The lasing medium is housed in an annular cell surrounding the reactor. The cell includes an annular reflecting mirror at the bottom and an annular output window at the top. A neutron reflector is disposed around the cell to reflect escaping neutrons back into the cell. The laser radiation from the annular window is focused onto a beam compactor which generates a single coherent output laser beam.

  15. Fusion Science to Prepare

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    DIII-D Explorations of Fusion Science to Prepare for ITER and FNSF Dr. Richard Buttery General Atomics Tuesday, Dec 10, 2013 - 11:00AM MBG AUDITORIUM Refreshments at 10:45AM The PrinceTon Plasma Physics laboraTory is a U.s. DeParTmenT of energy faciliTy Recent DIII-D research has provided significant new in- formation for the physics basis of key scientific issues for successful operation of ITER and future steady state fu- sion tokamaks, including control of edge localized modes (ELMs), plasma

  16. Council's Occupational Excellence Achievement

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    . Personnel Safety - received the National Safety Council's Occupational Excellence Achievement Award for the tenth straight year, maintained DOE Voluntary Protection Program Star status and reduced recordable injuries by 13 percent. 2. Nuclear Safety Culture - established the Nuclear Safety Culture campaign to foster an open, trusting environment and encourage technical inquisitiveness. 3. Engineering and Nuclear Safety Programs - improved criticality safety in Building 9212 through engineered

  17. Fusion Materials Research at Oak Ridge National Laboratory in Fiscal Year 2015

    SciTech Connect (OSTI)

    Wiffen, F. W.; Katoh, Yutai; Melton, Stephanie G.

    2015-12-01

    The realization of fusion energy is a formidable challenge with significant achievements resulting from close integration of the plasma physics and applied technology disciplines. Presently, the most significant technological challenge for the near-term experiments such as ITER, and next generation fusion power systems, is the inability of current materials and components to withstand the harsh fusion nuclear environment. The overarching goal of the Oak Ridge National Laboratory (ORNL) fusion materials program is to provide the applied materials science support and understanding to underpin the ongoing Department of Energy (DOE) Office of Science fusion energy program while developing materials for fusion power systems. In doing so the program continues to be integrated both with the larger United States (US) and international fusion materials communities, and with the international fusion design and technology communities.This document provides a summary of Fiscal Year (FY) 2015 activities supporting the Office of Science, Office of Fusion Energy Sciences Materials Research for Magnetic Fusion Energy (AT-60-20-10-0) carried out by ORNL. The organization of this report is mainly by material type, with sections on specific technical activities. Four projects selected in the Funding Opportunity Announcement (FOA) solicitation of late 2011 and funded in FY2012-FY2014 are identified by “FOA” in the titles. This report includes the final funded work of these projects, although ORNL plans to continue some of this work within the base program.

  18. Generalized Lawson Criteria for Inertial Confinement Fusion

    SciTech Connect (OSTI)

    Tipton, Robert E.

    2015-08-27

    The Lawson Criterion was proposed by John D. Lawson in 1955 as a general measure of the conditions necessary for a magnetic fusion device to reach thermonuclear ignition. Over the years, similar ignition criteria have been proposed which would be suitable for Inertial Confinement Fusion (ICF) designs. This paper will compare and contrast several ICF ignition criteria based on Lawson’s original ideas. Both analytical and numerical results will be presented which will demonstrate that although the various criteria differ in some details, they are closely related and perform similarly as ignition criteria. A simple approximation will also be presented which allows the inference of each ignition parameter directly from the measured data taken on most shots fired at the National Ignition Facility (NIF) with a minimum reliance on computer simulations. Evidence will be presented which indicates that the experimentally inferred ignition parameters on the best NIF shots are very close to the ignition threshold.

  19. Methodology for Scaling Fusion Power Plant Availability

    SciTech Connect (OSTI)

    Lester M. Waganer

    2011-01-04

    Normally in the U.S. fusion power plant conceptual design studies, the development of the plant availability and the plant capital and operating costs makes the implicit assumption that the plant is a 10th of a kind fusion power plant. This is in keeping with the DOE guidelines published in the 1970s, the PNL report1, "Fusion Reactor Design Studies - Standard Accounts for Cost Estimates. This assumption specifically defines the level of the industry and technology maturity and eliminates the need to define the necessary research and development efforts and costs to construct a one of a kind or the first of a kind power plant. It also assumes all the "teething" problems have been solved and the plant can operate in the manner intended. The plant availability analysis assumes all maintenance actions have been refined and optimized by the operation of the prior nine or so plants. The actions are defined to be as quick and efficient as possible. This study will present a methodology to enable estimation of the availability of the one of a kind (one OAK) plant or first of a kind (1st OAK) plant. To clarify, one of the OAK facilities might be the pilot plant or the demo plant that is prototypical of the next generation power plant, but it is not a full-scale fusion power plant with all fully validated "mature" subsystems. The first OAK facility is truly the first commercial plant of a common design that represents the next generation plant design. However, its subsystems, maintenance equipment and procedures will continue to be refined to achieve the goals for the 10th OAK power plant.

  20. Inertial Confinement Fusion R&D and Nuclear Proliferation

    SciTech Connect (OSTI)

    Robert J. Goldston

    2011-04-28

    In a few months, or a few years, the National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory may achieve fusion gain using 192 powerful lasers to generate x-rays that will compress and heat a small target containing isotopes of hydrogen. This event would mark a major milestone after decades of research on inertial confinement fusion (ICF). It might also mark the beginning of an accelerated global effort to harness fusion energy based on this science and technology. Unlike magnetic confinement fusion (ITER, 2011), in which hot fusion fuel is confined continuously by strong magnetic fields, inertial confinement fusion involves repetitive fusion explosions, taking advantage of some aspects of the science learned from the design and testing of hydrogen bombs. The NIF was built primarily because of the information it would provide on weapons physics, helping the United States to steward its stockpile of nuclear weapons without further underground testing. The U.S. National Academies' National Research Council is now hosting a study to assess the prospects for energy from inertial confinement fusion. While this study has a classified sub-panel on target physics, it has not been charged with examining the potential nuclear proliferation risks associated with ICF R&D. We argue here that this question urgently requires direct and transparent examination, so that means to mitigate risks can be assessed, and the potential residual risks can be balanced against the potential benefits, now being assessed by the NRC. This concern is not new (Holdren, 1978), but its urgency is now higher than ever before.

  1. Project ACHIEVE final report

    SciTech Connect (OSTI)

    1997-06-13

    Project ACHIEVE was a math/science academic enhancement program aimed at first year high school Hispanic American students. Four high schools -- two in El Paso, Texas and two in Bakersfield, California -- participated in this Department of Energy-funded program during the spring and summer of 1996. Over 50 students, many of whom felt they were facing a nightmare future, were given the opportunity to work closely with personal computers and software, sophisticated calculators, and computer-based laboratories -- an experience which their regular academic curriculum did not provide. Math and science projects, exercises, and experiments were completed that emphasized independent and creative applications of scientific and mathematical theories to real world problems. The most important outcome was the exposure Project ACHIEVE provided to students concerning the college and technical-field career possibilities available to them.

  2. Cellulose binding domain fusion proteins

    DOE Patents [OSTI]

    Shoseyov, O.; Yosef, K.; Shpiegl, I.; Goldstein, M.A.; Doi, R.H.

    1998-02-17

    A cellulose binding domain (CBD) having a high affinity for crystalline cellulose and chitin is disclosed, along with methods for the molecular cloning and recombinant production. Fusion products comprising the CBD and a second protein are likewise described. A wide range of applications are contemplated for both the CBD and the fusion products, including drug delivery, affinity separations, and diagnostic techniques. 16 figs.

  3. Cellulose binding domain fusion proteins

    DOE Patents [OSTI]

    Shoseyov, Oded (Karmey Yosef, IL); Shpiegl, Itai (Rehovot, IL); Goldstein, Marc A. (Davis, CA); Doi, Roy H. (Davis, CA)

    1998-01-01

    A cellulose binding domain (CBD) having a high affinity for crystalline cellulose and chitin is disclosed, along with methods for the molecular cloning and recombinant production thereof. Fusion products comprising the CBD and a second protein are likewise described. A wide range of applications are contemplated for both the CBD and the fusion products, including drug delivery, affinity separations, and diagnostic techniques.

  4. Fusion roadmapping | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Fusion roadmapping Subscribe to RSS - Fusion roadmapping The process of mapping a path to a commercial fusion reactor by planning a sequence of future machines. DOE's Ed Synakowski traces key discoveries in the quest for fusion energy The path to creating sustainable fusion energy as a clean, abundant and affordable source of electric energy has been filled with "aha moments" that have led to a point in history when the international fusion experiment, ITER, is poised to produce more

  5. Quality assurance in the Antares laser fusion construction project

    SciTech Connect (OSTI)

    Reichelt, W.H.

    1984-01-01

    The Antares CO/sub 2/ laser facility came on line in November 1983 as an experimental physics facility; it is the world's largest CO/sub 2/ laser fusion system. Antares is a major component of the Department of Energy's Inertial Confinement Fusion Program. Antares is a one-of-a-kind laser system that is used in an experimental environment. Given limited project funds and tight schedules, the quality assurance program was tailored to achieve project goals without imposing oppressive constraints. The discussion will review the Antares quality assurance program and the utility of various portions to completion of the project.

  6. CONTROL OF MECHANICALLY ACTIVATED POLYMERSOME FUSION: FACTORS...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Journal Article: CONTROL OF MECHANICALLY ACTIVATED POLYMERSOME FUSION: FACTORS AFFECTING FUSION. Citation Details In-Document Search Title: CONTROL OF MECHANICALLY ACTIVATED...

  7. CONTROL OF MECHANICALLY ACTIVATED POLYMERSOME FUSION: FACTORS...

    Office of Scientific and Technical Information (OSTI)

    MECHANICALLY ACTIVATED POLYMERSOME FUSION: FACTORS AFFECTING FUSION. Henderson, Ian M.; Paxton, Walter F Abstract not provided. Sandia National Laboratories (SNL-NM), Albuquerque,...

  8. Fusion Energy Sciences Advisory Committee (FESAC) Homepage |...

    Office of Science (SC) Website

    FESAC Home Fusion Energy Sciences Advisory Committee (FESAC) FESAC Home Meetings Members ... Print Text Size: A A A FeedbackShare Page The Fusion Energy Sciences Advisory Committee ...

  9. Plasma-material Interactions in Current Tokamaks and their Implications for Next-step Fusion Reactors

    SciTech Connect (OSTI)

    Federici, G.; Skinner, C.H.; Brooks, J.N.; Coad, J.P.; Grisolia, C.

    2001-01-10

    The major increase in discharge duration and plasma energy in a next-step DT [deuterium-tritium] fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety, and performance. Erosion will increase to a scale of several centimeters from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma-facing components. Controlling plasma wall interactions is critical to achieving high performance in present-day tokamaks and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena has stimulated an internationally coordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor (ITER) project and significant progress has been made in better under standing these issues. This paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next-step fusion reactors. Two main topical groups of interactions are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation, (ii) tritium retention and removal. The use of modeling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R and D [Research and Development] avenues for their resolution are presented.

  10. Fusion reactor pumped laser

    DOE Patents [OSTI]

    Jassby, D.L.

    1987-09-04

    A nuclear pumped laser capable of producing long pulses of very high power laser radiation is provided. A toroidal fusion reactor provides energetic neutrons which are slowed down by a moderator. The moderated neutrons are converted to energetic particles capable of pumping a lasing medium. The lasing medium is housed in an annular cell surrounding the reactor. The cell includes an annular reflecting mirror at the bottom and an annular output window at the top. A neutron reflector is disposed around the cell to reflect escaping neutrons back into the cell. The laser radiation from the annular window is focused onto a beam compactor which generates a single coherent output laser beam. 10 figs.

  11. Fusion pumped laser

    DOE Patents [OSTI]

    Pappas, Daniel S. (Los Alamos, NM)

    1989-01-01

    Apparatus is provided for generating energy in the form of laser radiation. A tokamak fusion reactor is provided for generating a long, or continuous, pulse of high-energy neutrons. The tokamak design provides a temperature and a magnetic field which is effective to generate a neutron flux of at least 10.sup.15 neutrons/cm.sup.2.s. A conversion medium receives neutrons from the tokamak and converts the high-energy neutrons to an energy source with an intensity and an energy effective to excite a preselected lasing medium. The energy source typically comprises fission fragments, alpha particles, and radiation from a fission event. A lasing medium is provided which is responsive to the energy source to generate a population inversion which is effective to support laser oscillations for generating output radiation.

  12. Fusion Power Demonstration III

    SciTech Connect (OSTI)

    Lee, J.D.

    1985-07-01

    This is the third in the series of reports covering the Fusion Power Demonstration (FPD) design study. This volume considers the FPD-III configuration that incorporates an octopole end plug. As compared with the quadrupole end-plugged designs of FPD-I and FPD-II, this octopole configuration reduces the number of end cell magnets and shortens the minimum ignition length of the central cell. The end-cell plasma length is also reduced, which in turn reduces the size and cost of the end cell magnets and shielding. As a contiuation in the series of documents covering the FPD, this report does not stand alone as a design description of FPD-III. Design details of FPD-III subsystems that do not differ significantly from those of the FPD-II configuration are not duplicated in this report.

  13. Fusion pumped light source

    DOE Patents [OSTI]

    Pappas, Daniel S. (Los Alamos, NM)

    1989-01-01

    Apparatus is provided for generating energy in the form of light radiation. A fusion reactor is provided for generating a long, or continuous, pulse of high-energy neutrons. The neutron flux is coupled directly with the lasing medium. The lasing medium includes a first component selected from Group O of the periodic table of the elements and having a high inelastic scattering cross section. Gamma radiation from the inelastic scattering reactions interacts with the first component to excite the first component, which decays by photon emission at a first output wavelength. The first output wavelength may be shifted to a second output wavelength using a second liquid component responsive to the first output wavelength. The light outputs may be converted to a coherent laser output by incorporating conventional optics adjacent the laser medium.

  14. LiWall Fusion - The New Concept of Magnetic Fusion

    SciTech Connect (OSTI)

    L.E. Zakharov

    2011-01-12

    Utilization of the outstanding abilities of a liquid lithium layer in pumping hydrogen isotopes leads to a new approach to magnetic fusion, called the LiWall Fusion. It relies on innovative plasma regimes with low edge density and high temperature. The approach combines fueling the plasma by neutral injection beams with the best possible elimination of outside neutral gas sources, which cools down the plasma edge. Prevention of cooling the plasma edge suppresses the dominant, temperature gradient related turbulence in the core. Such an approach is much more suitable for controlled fusion than the present practice, relying on high heating power for compensating essentially unlimited turbulent energy losses.

  15. Control of mechanically activated polymersome fusion: Factors affecting fusion

    SciTech Connect (OSTI)

    Henderson, Ian M.; Paxton, Walter F.

    2014-12-15

    Previously we have studied the mechanically-activated fusion of extruded (200 nm) polymer vesicles into giant polymersomes using agitation in the presence of salt. In this study we have investigated several factors contributing to this phenomenon, including the effects of (i) polymer vesicle concentration, (ii) agitation speed and duration, and iii) variation of the salt and its concentration. It was found that increasing the concentration of the polymer dramatically increases the production of giant vesicles through the increased collisions of polymersomes. Our investigations also found that increasing the frequency of agitation increased the efficiency of fusion, though ultimately limited the size of vesicle which could be produced due to the high shear involved. Finally it was determined that salt-mediation of the fusion process was not limited to NaCl, but is instead a general effect facilitated by the presence of solvated ionic compounds, albeit with different salts initiating fusion at different concentration.

  16. Control of mechanically activated polymersome fusion: Factors affecting fusion

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Henderson, Ian M.; Paxton, Walter F.

    2014-12-15

    Previously we have studied the mechanically-activated fusion of extruded (200 nm) polymer vesicles into giant polymersomes using agitation in the presence of salt. In this study we have investigated several factors contributing to this phenomenon, including the effects of (i) polymer vesicle concentration, (ii) agitation speed and duration, and iii) variation of the salt and its concentration. It was found that increasing the concentration of the polymer dramatically increases the production of giant vesicles through the increased collisions of polymersomes. Our investigations also found that increasing the frequency of agitation increased the efficiency of fusion, though ultimately limited the sizemore » of vesicle which could be produced due to the high shear involved. Finally it was determined that salt-mediation of the fusion process was not limited to NaCl, but is instead a general effect facilitated by the presence of solvated ionic compounds, albeit with different salts initiating fusion at different concentration.« less

  17. Deuterium fusion through nonequilibrium induction

    SciTech Connect (OSTI)

    Fang, P.H. )

    1991-03-01

    This paper presents a deuterium fusion system that is based on the induction of fusion through a nonequilibrium thermodynamical configuration. Mechanical excitation using ultrasound is applied to a palladium electrode with deuterium-containing liquid, a mixture of palladium powder and deuterium-containing liquid, and a system of palladium and a highly compressed deuterium gas that approximates a deuterium solid. The ultrasound, when coupled with the medium of these systems, instantaneously creates a high temperature and pressure that would induce fusion between deuterons.

  18. Socioeconomic procurement goals and achievements

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Socioeconomic procurement goals and achievements Socioeconomic procurement goals and achievements LANL ensures that a percentage of procurements are placed with small and other...

  19. Awards & Achievements | Argonne National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Awards & Achievements 2014 2014 U.S. Department of Energy, Vehicle Technologies Office, Distinguished Achievement Award, Larry Johnson 2014 U.S. Department of Energy, Vehicle...

  20. U. S. Fusion Energy Future

    SciTech Connect (OSTI)

    John A. Schmidt; Dan Jassby; Scott Larson; Maria Pueyo; Paul H. Rutherford

    2000-10-12

    Fusion implementation scenarios for the US have been developed. The dependence of these scenarios on both the fusion development and implementation paths has been assessed. A range of implementation paths has been studied. The deployment of CANDU fission reactors in Canada and the deployment of fission reactors in France have been assessed as possible models for US fusion deployment. The waste production and resource (including tritium) needs have been assessed. The conclusion that can be drawn from these studies is that it is challenging to make a significant impact on energy production during this century. However, the rapid deployment of fission reactors in Canada and France support fusion implementation scenarios for the US with significant power production during this century. If the country can meet the schedule requirements then the resource needs and waste production are found to be manageable problems.

  1. Laser fusion monthly -- August 1980

    SciTech Connect (OSTI)

    Ahlstrom, H.G.

    1980-08-01

    This report documents the monthly progress for the laser fusion research at Lawrence Livermore National Laboratory. First it gives facilities report for both the Shiva and Argus projects. Topics discussed include; laser system for the Nova Project; the fusion experiments analysis facility; optical/x-ray streak camera; Shiva Dante System temporal response; 2{omega}{sub 0} experiment; and planning for an ICF engineering test facility.

  2. Recent Accomplishments and Future Directions in US Fusion Safety & Environmental Program

    SciTech Connect (OSTI)

    David A. Petti; Brad J. Merrill; Phillip Sharpe; L. C. Cadwallader; L. El-Guebaly; S. Reyes

    2006-07-01

    The US fusion program has long recognized that the safety and environmental (S&E) potential of fusion can be attained by prudent materials selection, judicious design choices, and integration of safety requirements into the design of the facility. To achieve this goal, S&E research is focused on understanding the behavior of the largest sources of radioactive and hazardous materials in a fusion facility, understanding how energy sources in a fusion facility could mobilize those materials, developing integrated state of the art S&E computer codes and risk tools for safety assessment, and evaluating S&E issues associated with current fusion designs. In this paper, recent accomplishments are reviewed and future directions outlined.

  3. Tritium accountancy in fusion systems

    SciTech Connect (OSTI)

    Klein, J.E.; Clark, E.A.; Harvel, C.D.; Farmer, D.A.; Tovo, L.L.; Poore, A.S.; Moore, M.L.

    2015-03-15

    The US Department of Energy (DOE) has clearly defined requirements for nuclear material control and accountability (MCA) of tritium whereas the International Atomic Energy Agency (IAEA) does not since tritium is not a fissile material. MCA requirements are expected for tritium fusion machines and will be dictated by the host country or regulatory body where the machine is operated. Material Balance Areas (MBA) are defined to aid in the tracking and reporting of nuclear material movements and inventories. Material sub-accounts (MSA) are established along with key measurement points (KMP) to further subdivide a MBA to localize and minimize uncertainties in the inventory difference (ID) calculations for tritium accountancy. Fusion systems try to minimize tritium inventory which may require continuous movement of material through the MSA. The ability of making meaningful measurements of these material transfers is described in terms of establishing the MSA structure to perform and reconcile ID calculations. For fusion machines, changes to the traditional ID equation will be discussed which includes breeding, burn-up, and retention of tritium in the fusion device. The concept of 'net' tritium quantities consumed or lost in fusion devices is described in terms of inventory taking strategies and how it is used to track the accumulation of tritium in components or fusion machines. (authors)

  4. TRITIUM ACCOUNTANCY IN FUSION SYSTEMS

    SciTech Connect (OSTI)

    Klein, J. E.; Farmer, D. A.; Moore, M. L.; Tovo, L. L.; Poore, A. S.; Clark, E. A.; Harvel, C. D.

    2014-03-06

    The US Department of Energy (DOE) has clearly defined requirements for nuclear material control and accountability (MC&A) of tritium whereas the International Atomic Energy Agency (IAEA) does not since tritium is not a fissile material. MC&A requirements are expected for tritium fusion machines and will be dictated by the host country or regulatory body where the machine is operated. Material Balance Areas (MBAs) are defined to aid in the tracking and reporting of nuclear material movements and inventories. Material subaccounts (MSAs) are established along with key measurement points (KMPs) to further subdivide a MBA to localize and minimize uncertainties in the inventory difference (ID) calculations for tritium accountancy. Fusion systems try to minimize tritium inventory which may require continuous movement of material through the MSAs. The ability of making meaningful measurements of these material transfers is described in terms of establishing the MSA structure to perform and reconcile ID calculations. For fusion machines, changes to the traditional ID equation will be discussed which includes breading, burn-up, and retention of tritium in the fusion device. The concept of net tritium quantities consumed or lost in fusion devices is described in terms of inventory taking strategies and how it is used to track the accumulation of tritium in components or fusion machines.

  5. Comments on the model for coherent deuteron-deuteron fusion in crystalline Pd-D lattice

    SciTech Connect (OSTI)

    Vaidya, S.N. )

    1993-08-01

    The enhancement of the deuteron-deuteron fusion rate is estimated for a coherent interaction mechanism under realistic experimental conditions. The extension of this mechanism to (n,[gamma]) reactions is outlined. 19 refs., 2 figs.

  6. Perspective on occupational radiation exposures at a hypothetical fusion power station

    SciTech Connect (OSTI)

    Easterly, C.E.; Cannon, J.B.

    1983-01-01

    If current technology were used, several major sources of potential occupational radiation exposure at fusion power stations would be quite similar to those at current light water reactor power stations. Based upon this similarity, crude estimates of doses received from various maintenance operations at fusion power reactors are made. The dose estimates reinforce the need for concurrent development of sophisticated remote maintenance devices and low-activation materials for fusion reactors. It is concluded that minimization of occupational doses can be best achieved by developing an overall maintenance strategy that combines the best features of remote techniques and low activation materials as opposed to developing one or the other exclusively.

  7. Kinetic advantage of controlled intermediate nuclear fusion

    SciTech Connect (OSTI)

    Guo Xiaoming

    2012-09-26

    The dominated process of controlled fusion is to let nuclei gain enough kinetic energy to overcome Coulomb barrier. As a result, a fusion scheme can consider two factors in its design: to increase kinetic energy of nuclei and to alter the Coulomb barrier. Cold Fusion and Hot fusion are all one-factor schemes while Intermediate Fusion is a twofactors scheme. This made CINF kinetically superior. Cold Fusion reduces deuteron-deuteron distance, addressing Coulomb barrier, and Hot Fusion heat up plasma into extreme high temperature, addressing kinetic energy. Without enough kinetic energy made Cold Fusion skeptical. Extreme high temperature made Hot Fusion very difficult to engineer. Because CIFN addresses both factors, CIFN is a more promising technique to be industrialized.

  8. Fusion Welding of AerMet 100 Alloy

    SciTech Connect (OSTI)

    ENGLEHART, DAVID A.; MICHAEL, JOSEPH R.; NOVOTNY, PAUL M.; ROBINO, CHARLES V.

    1999-08-01

    A database of mechanical properties for weldment fusion and heat-affected zones was established for AerMet{reg_sign}100 alloy, and a study of the welding metallurgy of the alloy was conducted. The properties database was developed for a matrix of weld processes (electron beam and gas-tungsten arc) welding parameters (heat inputs) and post-weld heat treatment (PWHT) conditions. In order to insure commercial utility and acceptance, the matrix was commensurate with commercial welding technology and practice. Second, the mechanical properties were correlated with fundamental understanding of microstructure and microstructural evolution in this alloy. Finally, assessments of optimal weld process/PWHT combinations for cotildent application of the alloy in probable service conditions were made. The database of weldment mechanical properties demonstrated that a wide range of properties can be obtained in welds in this alloy. In addition, it was demonstrated that acceptable welds, some with near base metal properties, could be produced from several different initial heat treatments. This capability provides a means for defining process parameters and PWHT's to achieve appropriate properties for different applications, and provides useful flexibility in design and manufacturing. The database also indicated that an important region in welds is the softened region which develops in the heat-affected zone (HAZ) and analysis within the welding metallurgy studies indicated that the development of this region is governed by a complex interaction of precipitate overaging and austenite formation. Models and experimental data were therefore developed to describe overaging and austenite formation during thermal cycling. These models and experimental data can be applied to essentially any thermal cycle, and provide a basis for predicting the evolution of microstructure and properties during thermal processing.

  9. Summary of Assessment of Prospects for Inertial Fusion Energy...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Summary of Assessment of Prospects for Inertial Fusion Energy American Fusion News Category: National Ignition Facility Link: Summary of Assessment of Prospects for Inertial Fusion...

  10. Using Radio Waves to Control Fusion Plasma Density

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Using Radio Waves to Control Fusion Plasma Density Using Radio Waves to Control Fusion Plasma Density Simulations Run at NERSC Support Fusion Experiments at MIT, General Atomics ...

  11. Plasma Blobs and Filaments: Fusion Scientists Discover Secrets...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Plasma Blobs and Filaments: Fusion Scientists Discover Secrets of Turbulent Edge Transport American Fusion News Category: U.S. Universities Link: Plasma Blobs and Filaments: Fusion...

  12. Placing Fusion Power on a Pedestal | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Placing Fusion Power on a Pedestal American Fusion News Category: Massachusetts Institute of Technology (MIT) Link: Placing Fusion Power on a Pedestal

  13. Applying physics, teamwork to fusion energy science | Princeton Plasma

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Physics Lab Applying physics, teamwork to fusion energy science American Fusion News Category: Massachusetts Institute of Technology (MIT) Link: Applying physics, teamwork to fusion energy science

  14. Present Status of Vanadium Alloys for Fusion Applications

    SciTech Connect (OSTI)

    Muroga, Takeo; Chen, J. M.; Chernov, V. M.; Kurtz, Richard J.; Le Flem, M.

    2014-12-01

    Vanadium alloys are advanced options for low activation structural materials. After more than two decades of research, V-4Cr-4Ti has been emerged as the leading candidate, and technological progress has been made in reducing the number of critical issues for application of vanadium alloys to fusion reactors. Notable progress has been made in fabricating alloy products and weld joints without degradation of properties. Various efforts are also being made to improve high temperature strength and creep-rupture resistance, low temperature ductility after irradiation, and corrosion resistance in blanket conditions. Future research should focus on clarifying remaining uncertainty in the operating temperature window of V-4Cr-4Ti for application to near to middle term fusion blanket systems, and on further exploration of advanced materials for improved performance for longer-term fusion reactor systems.

  15. Experimental demonstration of fusion-relevant conditions in magnetized...

    Office of Scientific and Technical Information (OSTI)

    You are accessing a document from the Department of Energy's (DOE) Public Access Gateway ... Plasmas 17, 056303 (2010), in which a cylinder of deuterium gas with a preimposed axial ...

  16. Experimental demonstration of fusion-relevant conditions in magnetized...

    Office of Scientific and Technical Information (OSTI)

    the fuel reaches a stagnation temperature of approximately 3 keV, with Te Ti, and produces up to 2e12 thermonuclear DD neutrons. In this study, X-ray emission indicates a hot ...

  17. Ignition and Inertial Confinement Fusion at The National Ignition Facility

    SciTech Connect (OSTI)

    Moses, E

    2009-10-01

    The National Ignition Facility (NIF), the world's largest and most powerful laser system for inertial confinement fusion (ICF) and for studying high-energy-density (HED) science, is now operational at Lawrence Livermore National Laboratory (LLNL). The NIF is now conducting experiments to commission the laser drive, the hohlraum and the capsule and to develop the infrastructure needed to begin the first ignition experiments in FY 2010. Demonstration of ignition and thermonuclear burn in the laboratory is a major NIF goal. NIF will achieve this by concentrating the energy from the 192 beams into a mm{sup 3}-sized target and igniting a deuterium-tritium mix, liberating more energy than is required to initiate the fusion reaction. NIF's ignition program is a national effort managed via the National Ignition Campaign (NIC). The NIC has two major goals: execution of DT ignition experiments starting in FY2010 with the goal of demonstrating ignition and a reliable, repeatable ignition platform by the conclusion of the NIC at the end of FY2012. The NIC will also develop the infrastructure and the processes required to operate NIF as a national user facility. The achievement of ignition at NIF will demonstrate the scientific feasibility of ICF and focus worldwide attention on laser fusion as a viable energy option. A laser fusion-based energy concept that builds on NIF, known as LIFE (Laser Inertial Fusion Energy), is currently under development. LIFE is inherently safe and can provide a global carbon-free energy generation solution in the 21st century. This paper describes recent progress on NIF, NIC, and the LIFE concept.

  18. Collection of solid and gaseous samples to diagnose inertial confinement fusion implosions

    SciTech Connect (OSTI)

    Stoyer, M. A.; Velsko, C. A.; Spears, B. K.; Hicks, D. G.; Hudson, G. B.; Sangster, T. C.; Freeman, C. G.

    2012-02-15

    Collection of representative samples of debris following inertial confinement fusion implosions in order to diagnose implosion conditions and efficacy is a challenging endeavor because of the unique conditions within the target chamber such as unconverted laser light, intense pulse of x-rays, physical chunks of debris, and other ablative effects. We present collection of gas samples following an implosion for the first time. High collection fractions for noble gases were achieved. We also present collection of solid debris samples on flat plate collectors. Geometrical collection efficiencies for Au hohlraum material were achieved and collection of capsule debris (Be and Cu) was also observed. Asymmetric debris distributions were observed for Au and Be samples. Collection of Be capsule debris was higher for solid collectors viewing the capsule through the laser entrance hole in the hohlraum than for solid collectors viewing the capsule around the waist of the hohlraum. Collection of Au hohlraum material showed the opposite pattern: more Au debris was collected around the waist than through the laser entrance hole. The solid debris collectors were not optimized for minimal Cu backgrounds, which limited the conclusions about the symmetry of the Cu debris. The quality of the data limited conclusions on chemical fractionation effects within the burning, expanding, and then cooling plasma.

  19. Exploring Plasma Science Advances from Fusion Findings to Astrophysical

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Achievements | Princeton Plasma Physics Lab Exploring Plasma Science Advances from Fusion Findings to Astrophysical Achievements By John Greenwald December 4, 2012 Tweet Widget Google Plus One Share on Facebook The latest advances in plasma physics were the focus of more than 1,000 scientists from around the world who gathered in Providence, R.I., from Oct. 29 through Nov. 2 for the 54th Annual Meeting of the American Physical Society's Division of Plasma Physics (APS-DPP). Papers, posters

  20. Who We Are - Achievements - JCAP

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    0-Achievements-Hero_v2.jpg Our Achievements Who We Are Overview Achievements Our People Who we are Overview JCAP Mission JCAP At A Glance Fact Sheets Organizational Chart Our Achievements Recent Science Technology Transfer Awards & Honors Our People Senior Management Scientific Leadership Researchers Governance & Advisory Boards Operations & Administration Summary of JCAP Accomplishments and Capabilities: Protective coatings for photoelectrodes High-throughput material discovery New

  1. Preface to Special Topic: Advances in Radio Frequency Physics in Fusion Plasmas

    SciTech Connect (OSTI)

    Tuccillo, Angelo A.; Ceccuzzi, Silvio; Phillips, Cynthia K.

    2014-06-15

    It has long been recognized that auxiliary plasma heating will be required to achieve the high temperature, high density conditions within a magnetically confined plasma in which a fusion burn may be sustained by copious fusion reactions. Consequently, the application of radio and microwave frequency electromagnetic waves to magnetically confined plasma, commonly referred to as RF, has been a major part of the program almost since its inception in the 1950s. These RF waves provide heating, current drive, plasma profile control, and Magnetohydrodynamics (MHD) stabilization. Fusion experiments employ electromagnetic radiation in a wide range of frequencies, from tens of MHz to hundreds of GHz. The fusion devices containing the plasma are typically tori, axisymmetric or non, in which the equilibrium magnetic fields are composed of a strong toroidal magnetic field generated by external coils, and a poloidal field created, at least in the symmetric configurations, by currents flowing in the plasma. The waves are excited in the peripheral regions of the plasma, by specially designed launching structures, and subsequently propagate into the core regions, where resonant wave-plasma interactions produce localized heating or other modification of the local equilibrium profiles. Experimental studies coupled with the development of theoretical models and advanced simulation codes over the past 40+ years have led to an unprecedented understanding of the physics of RF heating and current drive in the core of magnetic fusion devices. Nevertheless, there are serious gaps in our knowledge base that continue to have a negative impact on the success of ongoing experiments and that must be resolved as the program progresses to the next generation devices and ultimately to demo and fusion power plant. A serious gap, at least in the ion cyclotron (IC) range of frequencies and partially in the lower hybrid frequency ranges, is the difficulty in coupling large amount of power to the plasma while minimizing the interaction between the plasma and launching structures. These potentially harmful interactions between the plasma and the vessel and launching structures are challenging: (i) significant and variable loss of power in the edge regions of confined plasmas and surrounding vessel structures adversely affect the core plasma performance and lifetime of a device; (ii) the launcher design is partly trial and error, with the consequence that launchers may have to be reconfigured after initial tests in a given device, at an additional cost. Over the broader frequency range, another serious gap is a quantitative lack of understanding of the combined effects of nonlinear wave-plasma processes, energetic particle interactions and non-axisymmetric equilibrium effects on determining the overall efficiency of plasma equilibrium and stability profile control techniques using RF waves. This is complicated by a corresponding lack of predictive understanding of the time evolution of transport and stability processes in fusion plasmas.

  2. Fusion bonding and alignment fixture

    DOE Patents [OSTI]

    Ackler, Harold D.; Swierkowski, Stefan P.; Tarte, Lisa A.; Hicks, Randall K.

    2000-01-01

    An improved vacuum fusion bonding structure and process for aligned bonding of large area glass plates, patterned with microchannels and access holes and slots, for elevated glass fusion temperatures. Vacuum pumpout of all the components is through the bottom platform which yields an untouched, defect free top surface which greatly improves optical access through this smooth surface. Also, a completely non-adherent interlayer, such as graphite, with alignment and location features is located between the main steel platform and the glass plate pair, which makes large improvements in quality, yield, and ease of use, and enables aligned bonding of very large glass structures.

  3. Method for vacuum fusion bonding

    DOE Patents [OSTI]

    Ackler, Harold D.; Swierkowski, Stefan P.; Tarte, Lisa A.; Hicks, Randall K.

    2001-01-01

    An improved vacuum fusion bonding structure and process for aligned bonding of large area glass plates, patterned with microchannels and access holes and slots, for elevated glass fusion temperatures. Vacuum pumpout of all components is through the bottom platform which yields an untouched, defect free top surface which greatly improves optical access through this smooth surface. Also, a completely non-adherent interlayer, such as graphite, with alignment and location features is located between the main steel platform and the glass plate pair, which makes large improvements in quality, yield, and ease of use, and enables aligned bonding of very large glass structures.

  4. Generic magnetic fusion reactor cost assessment

    SciTech Connect (OSTI)

    Sheffield, J.

    1984-01-01

    A generic D-T burning magnetic fusion reactor model shows that within the constraints set by generic limitations it is possible for magnetic fusion to be a competitive source of electricity in the 21st century.

  5. Exo-endo cellulase fusion protein

    DOE Patents [OSTI]

    Bower, Benjamin S.; Larenas, Edmund A.; Mitchinson, Colin

    2012-01-17

    The present invention relates to a heterologous exo-endo cellulase fusion construct, which encodes a fusion protein having cellulolytic activity comprising a catalytic domain derived from a fungal exo-cellobiohydrolase and a catalytic domain derived from an endoglucanase. The invention also relates to vectors and fungal host cells comprising the heterologous exo-endo cellulase fusion construct as well as methods for producing a cellulase fusion protein and enzymatic cellulase compositions.

  6. Z-Pinch Fusion for Energy Applications

    SciTech Connect (OSTI)

    SPIELMAN,RICK B.

    2000-01-01

    Z pinches, the oldest fusion concept, have recently been revisited in light of significant advances in the fields of plasma physics and pulsed power engineering. The possibility exists for z-pinch fusion to play a role in commercial energy applications. We report on work to develop z-pinch fusion concepts, the result of an extensive literature search, and the output for a congressionally-mandated workshop on fusion energy held in Snowmass, Co July 11-23,1999.

  7. Fusion reactor design | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    reactor design Subscribe to RSS - Fusion reactor design The design of devices that use powerful magnetic fields to control plasma so fusion can take place. The most widely used magnetic confinement device is the tokamak, followed by the stellarator. DOE's Ed Synakowski traces key discoveries in the quest for fusion energy The path to creating sustainable fusion energy as a clean, abundant and affordable source of electric energy has been filled with "aha moments" that have led to a

  8. 1994 International Sherwood Fusion Theory Conference

    SciTech Connect (OSTI)

    1994-04-01

    This report contains the abstracts of the paper presented at the 1994 International Sherwood Fusion Theory Conference.

  9. Breakthrough: Neutron Science for the Fusion Mission

    SciTech Connect (OSTI)

    McGreevy, Robert

    2012-04-24

    How Oak Ridge National Laboratory is helping to solve the world's energy problems through fusion energy research.

  10. Breakthrough: Neutron Science for the Fusion Mission

    ScienceCinema (OSTI)

    McGreevy, Robert

    2014-06-03

    How Oak Ridge National Laboratory is helping to solve the world's energy problems through fusion energy research.

  11. American Fusion News | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    American Fusion News General Atomics (GA) December 4, 2012 The Scorpion's Strategy: "Catch and Subdue" December 4, 2012 Frozen Bullets Tame Unruly Edge Plasmas in Fusion Experiment February 15, 2012 General Atomics (GA) Fusion News: A New Spin on Understanding Plasma Confinement See All Massachusetts Institute of Technology (MIT) April 5, 2013 Applying physics, teamwork to fusion energy science February 22, 2013 A Tour of Plasma Physics in Downtown Cambridge December 4, 2012 Placing

  12. Theoretical Fusion Research | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Theory & Computational Department Weekly Highlights Weekly Seminars Basic Plasma Science Plasma Astrophysics Other Physics and Engineering Research PPPL Technical Reports NSTX-U Education Organization Contact Us Overview Experimental Fusion Research Theoretical Fusion Research Theory & Computational Department Weekly Highlights Weekly Seminars Basic Plasma Science Plasma Astrophysics Other Physics and Engineering Research PPPL Technical Reports NSTX-U Theoretical Fusion Research About

  13. Senate targets fusion, backs NIF

    SciTech Connect (OSTI)

    Lawler, A.

    1995-08-01

    This article discusses a budget approved by the Senate Appropriations Committee which funds the fusion program even lower than the drastically reduced level the House approved in July. Work on the International Thermonuclear Experimental Reactor (ITER) would continue but the Tokamak Physics Experiment would be halted. At the same time, the Senate bill allots money to start work on the National Ignition Facility (NIF).

  14. A1.5 Fusion Performance

    SciTech Connect (OSTI)

    Amendt, P

    2011-03-31

    Analysis and radiation hydrodynamics simulations for expected high-gain fusion target performance on a demonstration 1-GWe Laser Inertial Fusion Energy (LIFE) power plant in the mid-2030s timeframe are presented. The required laser energy driver is 2.2 MJ at a 0.351-{micro}m wavelength, and a fusion target gain greater than 60 at a repetition rate of 16 Hz is the design goal for economic and commercial attractiveness. A scaling-law analysis is developed to benchmark the design parameter space for hohlraum-driven central hot-spot ignition. A suite of integrated hohlraum simulations is presented to test the modeling assumptions and provide a basis for a near-term experimental resolution of the key physics uncertainties on the National Ignition Facility (NIF). The NIF is poised to demonstrate ignition by 2012 based on the central hot spot (CHS) mode of ignition and propagating thermonuclear burn [1]. This immediate prospect underscores the imperative and timeliness of advancing inertial fusion as a carbon-free, virtually limitless source of energy by the mid-21st century to substantially offset fossil fuel technologies. To this end, an intensive effort is underway to leverage success at the NIF and to provide the foundations for a prototype 'LIFE.1' engineering test facility by {approx}2025, followed by a commercially viable 'LIFE.2' demonstration power plant operating at 1 GWe by {approx}2035. The current design goal for LIFE.2 is to accommodate {approx}2.2 MJ of laser energy (entering the high-Z radiation enclosure or 'hohlraum') at a 0.351-{micro}m wavelength operating at a repetition rate of 16 Hz and to provide a fusion target yield of 132 MJ. To achieve this design goal first requires a '0-d' analytic gain model that allows convenient exploration of parameter space and target optimization. This step is then followed by 2- and 3-dimensional radiation-hydrodynamics simulations that incorporate laser beam transport, x-ray radiation transport, atomic physics, and thermonuclear burn [2]. These simulations form the basis for assessing the susceptibility to hydrodynamic instability growth, target performance margins, laser backscatter induced by plasma density fluctuations within the hohlraum, and the threat spectrum emerging from the igniting capsule, e.g., spectra, fluences and anisotropy of the x rays and ions, for input into the chamber survivability calculations. The simulations follow the guidelines of a 'point design' methodology, which formally designates a well-defined milestone in concept development that meets established criteria for experimental testing. In Section 2, the 0-d analytic gain model to survey gain versus laser energy parameter space is discussed. Section 3 looks at the status of integrated hohlraum simulations and the needed improvements in laser-hohlraum coupling efficiency to meet the LIFE.2 threshold (net) target gain of {approx}60. Section 4 considers advanced hohlraum designs to well exceed the LIFE.2 design goal for satisfactory performance margins. We summarize in Sec. 5.

  15. Proceedings of the Office of Fusion Energy/DOE workshop on ceramic matrix composites for structural applications in fusion reactors

    SciTech Connect (OSTI)

    Jones, R.H. ); Lucas, G.E. )

    1990-11-01

    A workshop to assess the potential application of ceramic matrix composites (CMCs) for structural applications in fusion reactors was held on May 21--22, 1990, at University of California, Santa Barbara. Participants included individuals familiar with materials and design requirements in fusion reactors, ceramic composite processing and properties and radiation effects. The primary focus was to list the feasibility issues that might limit the application of these materials in fusion reactors. Clear advantages for the use of CMCs are high-temperature operation, which would allow a high-efficiency Rankine cycle, and low activation. Limitations to their use are material costs, fabrication complexity and costs, lack of familiarity with these materials in design, and the lack of data on radiation stability at relevant temperatures and fluences. Fusion-relevant feasibility issues identified at this workshop include: hermetic and vacuum properties related to effects of matrix porosity and matrix microcracking; chemical compatibility with coolant, tritium, and breeder and multiplier materials, radiation effects on compatibility; radiation stability and integrity; and ability to join CMCs in the shop and at the reactor site, radiation stability and integrity of joints. A summary of ongoing CMC radiation programs is also given. It was suggested that a true feasibility assessment of CMCs for fusion structural applications could not be completed without evaluation of a material tailored'' to fusion conditions or at least to radiation stability. It was suggested that a follow-up workshop be held to design a tailored composite after the results of CMC radiation studies are available and the critical feasibility issues are addressed.

  16. How Fusion Energy Works | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Fusion Energy Works How Energy Works 33 likes How Fusion Energy Works Fusion energy is the energy source of the sun and all of the stars. In fusion, two light atomic nuclei are fused together to create energy (as opposed to fission where the nucleus of an atom is split apart). The scientific basis underlying fusion energy is known as plasma physics. Plasma is one of the one of the four fundamental states of matter and makes up 99 percent of the visible universe. On a basic level, a plasma is a

  17. Fusion energy | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    energy Subscribe to RSS - Fusion energy The energy released when two atomic nuclei fuse together. This process powers the sun and stars. Read more DOE's Ed Synakowski traces key discoveries in the quest for fusion energy The path to creating sustainable fusion energy as a clean, abundant and affordable source of electric energy has been filled with "aha moments" that have led to a point in history when the international fusion experiment, ITER, is poised to produce more fusion energy

  18. Establishment of an Institute for Fusion Studies. Technical progress report, 1 November 1993--31 October 1994

    SciTech Connect (OSTI)

    Hazeltine, R.D.

    1994-07-01

    The Institute for Fusion Studies is a national center for theoretical fusion plasma physics research. Its purposes are: (1) to conduct research on theoretical questions concerning the achievement of controlled fusion energy by means of magnetic confinement--including both fundamental problems of long-range significance, as well as shorter-term issues; (2) to serve as a national and international center for information exchange by hosting exchange visits, conferences, and workshops; (3) and to train students and postdoctoral research personnel for the fusion energy program and plasma physics research areas. The theoretical research results obtained by the Institute contribute to the progress of nuclear fusion research, whose goal is the development of fusion power as a basic energy source. Close collaborative relationships have been developed with other university and national laboratory fusion groups, both in the US and abroad. In addition to its primary focus on mainstream fusion physics, the Institute is also involved with research in fusion-sidestream fields, such as advanced computing techniques, nonlinear dynamics, space plasmas and astrophysics, statistical mechanics, fluid dynamics, and accelerator physics. Important research discoveries are briefly described.

  19. Particle beam fusion progress report for 1989

    SciTech Connect (OSTI)

    Sweeney, M.A.

    1994-08-01

    This report summarizes the progress on the pulsed power approach to inertial confinement fusion. In 1989, the authors achieved a proton focal intensity of 5 TW/cm{sup 2} on PBFA-II in a 15-cm-radius applied magnetic-field (applied-B) ion diode. This is an improvement by a factor of 4 compared to previous PBFA-II experiments. They completed development of the three-dimensional (3-D), electromagnetic, particle-in-cell code QUICKSILVER and obtained the first 3-D simulations of an applied-B ion diode. The simulations, together with analytic theory, suggest that control of electromagnetic instabilities could reduce ion divergence. In experiments using a lithium fluoride source, they delivered 26 kJ of lithium energy to the diode axis. Rutherford-scattered ion diagnostics have been developed and tested using a conical foil located inside the diode. They can now obtain energy density profiles by using range filters and recording ion images on nuclear track recording film. Timing uncertainties in power flow experiments on PBFA-II have been reduced by a factor of 5. They are investigating three plasma opening switches that use magnetic fields to control and confine the injected plasma. These new switches provide better power flow than the standard plasma erosion switch. Advanced pulsed-power fusion drivers will require extraction-geometry applied-B ion diodes. During this reporting period, progress was made in evaluating the generation, transport, and focus of multiple ion beams in an extraction geometry and in assessing the probable damage to a target chamber first wall.

  20. Experimental investigation of muon-catalyzed t + t fusion

    SciTech Connect (OSTI)

    Bogdanova, L. N.; Bom, V. R.; Demin, A. M.; Demin, D. L.; Eijk, C. W. E. van; Filchagin, S. V.; Filchenkov, V. V.; Grafov, N. N. Grishechkin, S. K.; Gritsaj, K. I.; Konin, A. D.; Kuryakin, A. V.; Medved', S. V.; Musyaev, R. K.; Rudenko, A. I.; Tumkin, D. P.; Vinogradov, Yu. I.; Yukhimchuk, A. A.; Yukhimchuk, S. A.; Zinov, V. G.

    2009-02-15

    The muon-catalyzed fusion ({mu}CF) process in tritium was studied by the {mu}CF collaboration on the muon beam of the JINR Phasotron. The measurements were carried out with a liquid tritium target at the temperature 22 K and density approximately 1.25 of the liquid hydrogen density (LHD). Parameters of the {mu}CF cycle were determined: the tt{mu} muonic molecule formation rate {lambda}{sub tt{mu}} = 2.84(0.32) {mu}s{sup -1}, the tt{mu} fusion reaction rate {lambda}{sub f} = 15.6(2.0) {mu}s{sup -1}, and the probability of muon sticking to helium {omega}{sub tt}= 13.9(1.5)%. The results agree with those obtained earlier by other groups, but better accuracy was achieved due to our unique experimental method.

  1. Electron kinetic effects on interferometry and polarimetry in high temperature fusion plasmas

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    196 This content was downloaded on 12/12/2013 at 20:27 Please note that terms and conditions apply. Electron kinetic effects on interferometry and polarimetry in high temperature fusion plasmas View the table of contents for this issue, or go to the journal homepage for more Home Search Collections Journals About Contact us My IOPscience IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 53 (2013) 113005 (9pp) doi:10.1088/0029-5515/53/11/113005 Electron kinetic

  2. Establishment of an Institute for Fusion Studies. Technical progress report, November 1, 1994--October 31, 1995

    SciTech Connect (OSTI)

    1995-07-01

    The Institute for Fusion Studies is a national center for theoretical fusion plasma physics research. Its purposes are to (1) conduct research on theoretical questions concerning the achievement of controlled fusion energy by means of magnetic confinement--including both fundamental problems of long-range significance, as well as shorter-term issues; (2) serve as a national and international center for information exchange by hosting exchange visits, conferences, and workshops; and (3) train students and postdoctoral research personnel for the fusion energy program and plasma physics research areas. During FY 1995, a number of significant scientific advances were achieved at the IFS, both in long-range fundamental problems as well as in near-term strategic issues, consistent with the Institute`s mandate. Examples of these achievements include, for example, tokamak edge physics, analytical and computational studies of ion-temperature-gradient-driven turbulent transport, alpha-particle-excited toroidal Alfven eigenmode nonlinear behavior, sophisticated simulations for the Numerical Tokamak Project, and a variety of non-tokamak and non-fusion basic plasma physics applications. Many of these projects were done in collaboration with scientists from other institutions. Research discoveries are briefly described in this report.

  3. LANL researchers simulate helium bubble behavior in fusion reactors

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Researchers simulate helium bubble behavior LANL researchers simulate helium bubble behavior in fusion reactors A team performed simulations to understand more fully how tungsten behaves in such harsh conditions, particularly in the presence of implanted helium that forms bubbles in the material. August 4, 2015 Simulation snapshots of the helium bubble just before bursting. Colors indicate tungsten atoms (red) and helium atoms (blue). Simulation snapshots of the helium bubble just before

  4. Koel applies science of surface chemistry to fusion research at PPPL |

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Princeton Plasma Physics Lab Koel applies science of surface chemistry to fusion research at PPPL By Catherine Zandonella March 26, 2012 Tweet Widget Google Plus One Share on Facebook To study the interactions of lithium under conditions similar to what might be found in a fusion reactor, lithium on a sample of TZM molybdenum, which is an alloy of molybdenum, titanium, zirconium and carbon known for its high strength and temperature properties, is heated inside an ultrahigh vacuum chamber

  5. Photons & Fusion Newsletter - 2014

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    news Photons & Fusion Newsletter - 2014 May ARC Beamlet Profiles NIF Petawatt Laser Is on Track to Completion The Advanced Radiographic Capability (ARC), a petawatt-class laser now being developed for NIF, is moving rapidly along the path to completion and commissioning.... April Star-forming Pillars of Creation in the Eagle Nebula Discovery Science on NIF: Exploring the Physics of Star Formation For the past several years, astronomers at the University of Maryland and theorists and

  6. fusion | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    fusion | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog Home /

  7. Fusion Institutions | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    Fusion Institutions Fusion Energy Sciences (FES) FES Home About Research Fusion Institutions Fusion Links International Activities Facilities Science Highlights Benefits of FES Funding Opportunities Fusion Energy Sciences Advisory Committee (FESAC) Community Resources Contact Information Fusion Energy Sciences U.S. Department of Energy SC-24/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-4941 F: (301) 903-8584 E: Email Us More Information » Research Fusion

  8. Fusion Nuclear Science Pathways Assessment

    SciTech Connect (OSTI)

    C.E. Kessel, et. al.

    2012-02-23

    With the strong commitment of the US to the success of the ITER burning plasma mission, and the project overall, it is prudent to consider how to take the most advantage of this investment. The production of energy from fusion has been a long sought goal, and the subject of several programmatic investigations and time line proposals [1]. The nuclear aspects of fusion research have largely been avoided experimentally for practical reasons, resulting in a strong emphasis on plasma science. Meanwhile, ITER has brought into focus how the interface between the plasma and engineering/technology, presents the most challenging problems for design. In fact, this situation is becoming the rule and no longer the exception. ITER will demonstrate the deposition of 0.5 GW of neutron heating to the blanket, deliver a heat load of 10-20 MW/m2 or more on the divertor, inject 50-100 MW of heating power to the plasma, all at the expected size scale of a power plant. However, in spite of this, and a number of other technologies relevant power plant, ITER will provide a low neutron exposure compared to the levels expected to a fusion power plant, and will purchase its tritium entirely from world reserves accumulated from decades of CANDU reactor operations. Such a decision for ITER is technically well founded, allowing the use of conventional materials and water coolant, avoiding the thick tritium breeding blankets required for tritium self-sufficiency, and allowing the concentration on burning plasma and plasma-engineering interface issues. The neutron fluence experienced in ITER over its entire lifetime will be ~ 0.3 MW-yr/m2, while a fusion power plant is expected to experience 120-180 MW-yr/m2 over its lifetime. ITER utilizes shielding blanket modules, with no tritium breeding, except in test blanket modules (TBM) located in 3 ports on the midplane [2], which will provide early tests of the fusion nuclear environment with very low tritium production (a few g per year).

  9. NERSC Achievement Award Recipient Presentations

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Achievement Awards NERSC Achievement Award Recipient Presentations February 4, 2014 Downloads vonug14.pdf | Adobe Acrobat PDF file Conformational change in biology: from amino acids to enzymes and molecular motors, Victor Ovchinnikov, Harvard University JainNERSCUserDay2.pdf | Adobe Acrobat PDF file Innovative use of High Performance Computing through the Modeling of Particle Accelerators, Jean-Luc Vay, Berkeley Lab JainNERSCUserDay2.pdf | Adobe Acrobat PDF file The Materials Project, FireWorks,

  10. 2013 HPC Achievement Award Recipients

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    2013 Recipients 2013 HPC Achievement Award Recipients 2013 Award Recipients The Department of Energy's National Energy Research Scientific Computing Center (NERSC) announced the winners of their inaugural High Performance Computing (HPC) Achievement Awards on Wednesday at the annual NERSC User Group meeting at the Lawrence Berkeley National Laboratory (Berkeley Lab). The awardees are all NERSC users who have either demonstrated an innovative use of HPC resources to solve a scientific problem, or

  11. Lithium As Plasma Facing Component for Magnetic Fusion Research

    SciTech Connect (OSTI)

    Masayuki Ono

    2012-09-10

    The use of lithium in magnetic fusion confinement experiments started in the 1990's in order to improve tokamak plasma performance as a low-recycling plasma-facing component (PFC). Lithium is the lightest alkali metal and it is highly chemically reactive with relevant ion species in fusion plasmas including hydrogen, deuterium, tritium, carbon, and oxygen. Because of the reactive properties, lithium can provide strong pumping for those ions. It was indeed a spectacular success in TFTR where a very small amount (~ 0.02 gram) of lithium coating of the PFCs resulted in the fusion power output to improve by nearly a factor of two. The plasma confinement also improved by a factor of two. This success was attributed to the reduced recycling of cold gas surrounding the fusion plasma due to highly reactive lithium on the wall. The plasma confinement and performance improvements have since been confirmed in a large number of fusion devices with various magnetic configurations including CDX-U/LTX (US), CPD (Japan), HT-7 (China), EAST (China), FTU (Italy), NSTX (US), T-10, T-11M (Russia), TJ-II (Spain), and RFX (Italy). Additionally, lithium was shown to broaden the plasma pressure profile in NSTX, which is advantageous in achieving high performance H-mode operation for tokamak reactors. It is also noted that even with significant applications (up to 1,000 grams in NSTX) of lithium on PFCs, very little contamination (< 0.1%) of lithium fraction in main fusion plasma core was observed even during high confinement modes. The lithium therefore appears to be a highly desirable material to be used as a plasma PFC material from the magnetic fusion plasma performance and operational point of view. An exciting development in recent years is the growing realization of lithium as a potential solution to solve the exceptionally challenging need to handle the fusion reactor divertor heat flux, which could reach 60 MW/m2 . By placing the liquid lithium (LL) surface in the path of the main divertor heat flux (divertor strike point), the lithium is evaporated from the surface. The evaporated lithium is quickly ionized by the plasma and the ionized lithium ions can provide a strongly radiative layer of plasma ("radiative mantle"), thus could significantly reduce the heat flux to the divertor strike point surfaces, thus protecting the divertor surface. The protective effects of LL have been observed in many experiments and test stands. As a possible reactor divertor candidate, a closed LL divertor system is described. Finally, it is noted that the lithium applications as a PFC can be quite flexible and broad. The lithium application should be quite compatible with various divertor configurations, and it can be also applied to protecting the presently envisioned tungsten based solid PFC surfaces such as the ones for ITER. Lithium based PFCs therefore have the exciting prospect of providing a cost effective flexible means to improve the fusion reactor performance, while providing a practical solution to the highly challenging divertor heat handling issue confronting the steadystate magnetic fusion reactors.

  12. Using LGI experiments to achieve better understanding of pedestal-edge coupling in NSTX-U

    SciTech Connect (OSTI)

    Wang, Zhehui

    2015-02-23

    PowerPoint presentation. Latest advances in granule or dust injection technologies, fast and high-resolution imaging, together with micro-/nano-structured material fabrication, provide new opportunities to examine plasma-material interaction (PMI) in magnetic fusion environment. Some of our previous work in these areas is summarized. The upcoming LGI experiments in NSTX-U will shed new light on granular matter transport in the pedestal-edge region. In addition to particle control, these results can also be used for code validation and achieving better understanding of pedestal-edge coupling in fusion plasmas in both NSTX-U and others.

  13. PPPL Races Ahead with Fusion Research

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    the Power... PPPL Races Ahead with Fusion Research RESEARCH NEWS FROM PPPL uest Summer 2013, Issue 1 Contents 02 New Paths to Fusion Energy 09 ADVANCING FUSION THEORY 12 ADVANCING PLASMA SCIENCE 15 PARTNERSHIPS & COLLABORATIONS 19 EDUCATION & OUTREACH AWARDS Inside back cover Letter from the Director W elcome to the premiere issue of Quest, the annual magazine of the U.S. Department of Energy's Princeton Plasma Physics Laboratory (PPPL). We are pleased to provide this news of our strides

  14. Tritium Gas Processing for Magnetic Fusion

    Office of Environmental Management (EM)

    Processing for Magnetic Fusion SRNL-STI-2014-00168 Bernice Rogers Clean Energy - Savannah River National Laboratory April 24, 2014 The views and opinions expressed herein do not necessarily reflect those of any international organization, the US Government SRNL-STI-2014-00168 Presentation Outline * Background Information * Simplified Fusion Fuel Cycle * Select Requirements Fuel Cycle * Confinement * Process * Summary 2 3 What is Fusion? Small Atom Small Atom Large Atom ENERGY + 4 deuterium

  15. Review of alternative concepts for magnetic fusion

    SciTech Connect (OSTI)

    Krakowski, R.A.; Miller, R.L.; Hagenson, R.L.

    1980-01-01

    Although the Tokamak represents the mainstay of the world's quest for magnetic fusion power, with the tandem mirror serving as a primary backup concept in the US fusion program, a wide range of alternative fusion concepts (AFC's) have been and are being pursued. This review presents a summary of past and present reactor projections of a majority of AFC's. Whenever possible, quantitative results are given.

  16. Hydrogen Fusion An Opportunity for Global Leadership

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Process of Hydrogen Fusion Hydrogen fusion, the process that powers our sun and the stars, is the most fundamental energy source in the visible universe. Directly, it provides sunlight, while indirectly it is the driver behind all "renewable" energies (solar-thermal and photovoltaic, wind, biomass and ocean- thermal). Even the fossil fuels (oil, gas and coal), which were derived over long periods of time from ancient biomass, are by-products of hydrogen fusion. The energy released

  17. Inertial confinement fusion | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Inertial confinement fusion Subscribe to RSS - Inertial confinement fusion An experimental process that uses lasers to compress plasma to sufficiently high temperatures and densities for fusion to occur. Such experiments are carried out in places such as the National Ignition Facility at the Lawrence Livermore National Laboratory in Livermore, California. Graduate students from two British universities install a critical new diagnostic on NSTX-U A system of antennas similar to those that

  18. Laser fusion neutron source employing compression with short pulse lasers

    DOE Patents [OSTI]

    Sefcik, Joseph A; Wilks, Scott C

    2013-11-05

    A method and system for achieving fusion is provided. The method includes providing laser source that generates a laser beam and a target that includes a capsule embedded in the target and filled with DT gas. The laser beam is directed at the target. The laser beam helps create an electron beam within the target. The electron beam heats the capsule, the DT gas, and the area surrounding the capsule. At a certain point equilibrium is reached. At the equilibrium point, the capsule implodes and generates enough pressure on the DT gas to ignite the DT gas and fuse the DT gas nuclei.

  19. Research and development on vanadium alloys for fusion applications

    SciTech Connect (OSTI)

    Zinkle, S.J.; Rowcliffe, A.F.; Matsui, H.; Abe, K.; Smith, D.L.; Osch, E. van; Kazakov, V.A.

    1998-03-01

    The current status of research and development on unirradiated and irradiated V-Cr-Ti alloys intended for fusion reactor structural applications is reviewed, with particular emphasis on the flow and fracture behavior of neutron-irradiated vanadium alloys. Recent progress on fabrication, joining, oxidation behavior, and the development of insulator coatings is also summarized. Fabrication of large (>500 kg) heats of V-4Cr-4Ti with properties similar to previous small laboratory heats has now been demonstrated. Impressive advances in the joining of thick sections of vanadium alloys using GTA and electron beam welds have been achieved in the past two years, although further improvements are still needed.

  20. Method of controlling fusion reaction rates

    DOE Patents [OSTI]

    Kulsrud, R.M.; Furth, H.P.; Valeo, E.J.; Goldhaber, M.

    1983-05-09

    This invention relates to a method of controlling the reaction rates in a nuclear fusion reactor; and more particularly, to the use of polarized nuclear fuel.

  1. Fusion materials science and technology research opportunities...

    Office of Scientific and Technical Information (OSTI)

    the ITER era Citation Details In-Document Search Title: Fusion materials science and technology research opportunities now and during the ITER era Several high-priority...

  2. PPPL Races Ahead with Fusion Research

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    of unprecedented size and power that is under construction in France, and cooperation with other ... Goldston's model, published in the journal Nuclear Fusion, predicts the ...

  3. How Fusion Energy Works | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    3 likes How Fusion Energy Works Fusion energy is the energy source of the sun and all of the stars. In fusion, two light atomic nuclei are fused together to create energy (as opposed to fission where the nucleus of an atom is split apart). The scientific basis underlying fusion energy is known as plasma physics. Plasma is one of the one of the four fundamental states of matter and makes up 99 percent of the visible universe. On a basic level, a plasma is a hot ionized gas. The ultimate goal of

  4. Cold nuclear fusion and muon-catalyzed fusion. (Latest citations from the INSPEC database). Published Search

    SciTech Connect (OSTI)

    1993-12-01

    The bibliography contains citations concerning a nuclear fusion process which occurs at lower temperatures and pressures than conventional fusion reactions. The references describe theoretical and experimental results for a proposed muon-catalyzed fusion reactor, and for studies on muon sticking and reactivation. The temperature dependence of fusion rates, and resolution of some engineering challenges are also discussed. (Contains 250 citations and includes a subject term index and title list.)

  5. Response to FESAC survey, Non-Fusion Connections to Fusion Energy Sciences.

    Office of Scientific and Technical Information (OSTI)

    Long Duration Directional Drives for Star Formation and Photoionization (Technical Report) | SciTech Connect Response to FESAC survey, Non-Fusion Connections to Fusion Energy Sciences. Long Duration Directional Drives for Star Formation and Photoionization Citation Details In-Document Search Title: Response to FESAC survey, Non-Fusion Connections to Fusion Energy Sciences. Long Duration Directional Drives for Star Formation and Photoionization Due to the iconic status of the pillars of the

  6. The National Ignition Facility: The Path to Ignition, High Energy Density Science and Inertial Fusion Energy

    SciTech Connect (OSTI)

    Moses, E

    2011-03-25

    The National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory (LLNL) in Livermore, CA, is a Nd:Glass laser facility capable of producing 1.8 MJ and 500 TW of ultraviolet light. This world's most energetic laser system is now operational with the goals of achieving thermonuclear burn in the laboratory and exploring the behavior of matter at extreme temperatures and energy densities. By concentrating the energy from its 192 extremely energetic laser beams into a mm{sup 3}-sized target, NIF can produce temperatures above 100 million K, densities of 1,000 g/cm{sup 3}, and pressures 100 billion times atmospheric pressure - conditions that have never been created in a laboratory and emulate those in the interiors of planetary and stellar environments. On September 29, 2010, NIF performed the first integrated ignition experiment which demonstrated the successful coordination of the laser, the cryogenic target system, the array of diagnostics and the infrastructure required for ignition. Many more experiments have been completed since. In light of this strong progress, the U.S. and the international communities are examining the implication of achieving ignition on NIF for inertial fusion energy (IFE). A laser-based IFE power plant will require a repetition rate of 10-20 Hz and a 10% electrical-optical efficiency laser, as well as further advances in large-scale target fabrication, target injection and tracking, and other supporting technologies. These capabilities could lead to a prototype IFE demonstration plant in 10- to 15-years. LLNL, in partnership with other institutions, is developing a Laser Inertial Fusion Energy (LIFE) baseline design and examining various technology choices for LIFE power plant This paper will describe the unprecedented experimental capabilities of the NIF, the results achieved so far on the path toward ignition, the start of fundamental science experiments and plans to transition NIF to an international user facility providing access to researchers around the world. The paper will conclude with a discussion of LIFE, its development path and potential to enable a carbon-free clean energy future.

  7. Property:Achievement Date | Open Energy Information

    Open Energy Info (EERE)

    Achievement Date Jump to: navigation, search Property Name Achievement Date Property Type String Retrieved from "http:en.openei.orgwindex.php?titleProperty:AchievementDate&ol...

  8. Magnetized Target Fusion project with high density FRC at Los Alamos National Laboratory.

    SciTech Connect (OSTI)

    Intrator, T.; Park, J. Y.; Wurden, G. A.; Taccetti, J. M.; Tuszewski, M.; Zhang, S. Y.; Waganaar, W.; Furno, I.; Hsu, S.; Tejero, E.; Leonard, M.; Bass, C.; Grabowski, C.; Degnan, J. H.

    2003-08-13

    We describe a program to demonstrate the scientific basis of Magnetized Target Fusion (MTF). MTF is a potentially low cost path to fusion which is intermediate in plasma regime between magnetic (MFE) and inertial fusion energy (IFE). MTF involves the compression of a magnetized target plasma and PdV heating to fusion relevant conditions inside a converging flux conserving boundary. We have chosen to demonstrate MTF by using a field-reversed configuration (FRC) as our magnetized target plasma and an imploding metal liner for compression. These choices take advantage of significant past scientific and technical accomplishments in MFE and Defense Programs research and should yield substantial plasma performance (n{tau}>10{sup 13}s-cm{sup -3}>5 keV) using an available pulsed-power implosion facility at modest cost. We have recently shown this FRC to be within a factor of 2-3 of required pressure and lifetime.

  9. Diamond neutral particle spectrometer for fusion reactor ITER

    SciTech Connect (OSTI)

    Krasilnikov, V.; Amosov, V.; Kaschuck, Yu.; Skopintsev, D.

    2014-08-21

    A compact diamond neutral particle spectrometer with digital signal processing has been developed for fast charge-exchange atoms and neutrons measurements at ITER fusion reactor conditions. This spectrometer will play supplementary role for Neutral Particle Analyzer providing 10 ms time and 30 keV energy resolutions for fast particle spectra in non-tritium ITER phase. These data will also be implemented for independent studies of fast ions distribution function evolution in various plasma scenarios with the formation of a single fraction of high-energy ions. In tritium ITER phase the DNPS will measure 14 MeV neutrons spectra. The spectrometer with digital signal processing can operate at peak counting rates reaching a value of 10{sup 6} cps. Diamond neutral particle spectrometer is applicable to future fusion reactors due to its high radiation hardness, fast response and high energy resolution.

  10. fusion

    National Nuclear Security Administration (NNSA)

    in size from a pinhead to a small pea, is filled with a mixture of two isotopes of hydrogen (deuterium (D) and tritium (T)) and is subjected to a sudden application of...

  11. fusion

    National Nuclear Security Administration (NNSA)

    in size from a pinhead to a small pea, is filled with a mixture of two isotopes of hydrogen (deuterium (D) and tritium (T)) and is subjected to a sudden application of intense...

  12. Inertial fusion energy: A clearer view of the environmental and safety perspectives

    SciTech Connect (OSTI)

    Latkowski, J.F.

    1996-11-01

    If fusion energy is to achieve its full potential for safety and environmental (S&E) advantages, the S&E characteristics of fusion power plant designs must be quantified and understood, and the resulting insights must be embodied in the ongoing process of development of fusion energy. As part of this task, the present work compares S&E characteristics of five inertial and two magnetic fusion power plant designs. For each design, a set of radiological hazard indices has been calculated with a system of computer codes and data libraries assembled for this purpose. These indices quantify the radiological hazards associated with the operation of fusion power plants with respect to three classes of hazard: accidents, occupational exposure, and waste disposal. The three classes of hazard have been qualitatively integrated to rank the best and worst fusion power plant designs with respect to S&E characteristics. From these rankings, the specific designs, and other S&E trends, design features that result in S&E advantages have been identified. Additionally, key areas for future fusion research have been identified. Specific experiments needed include the investigation of elemental release rates (expanded to include many more materials) and the verification of sequential charged-particle reactions. Improvements to the calculational methodology are recommended to enable future comparative analyses to represent more accurately the radiological hazards presented by fusion power plants. Finally, future work must consider economic effects. Trade-offs among design features will be decided not by S&E characteristics alone, but also by cost-benefit analyses. 118 refs., 35 figs., 35 tabs.

  13. Questions and answers about ITER and fusion energy

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    QA & What is fusion? Fusion, the energy source of the sun and stars, is the most efficient process for converting mass into energy (E mc 2 ). The fusion process is ...

  14. Frozen Bullets Tame Unruly Edge Plasmas in Fusion Experiment | Princeton

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Plasma Physics Lab Frozen Bullets Tame Unruly Edge Plasmas in Fusion Experiment American Fusion News Category: General Atomics (GA) Link: Frozen Bullets Tame Unruly Edge Plasmas in Fusion Experiment

  15. Modeling of Heat and Mass Transfer in Fusion Welding (Book) ...

    Office of Scientific and Technical Information (OSTI)

    Book: Modeling of Heat and Mass Transfer in Fusion Welding Citation Details In-Document Search Title: Modeling of Heat and Mass Transfer in Fusion Welding In fusion welding, parts...

  16. Secretary's 2014 Achievement Awards | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Secretary's 2014 Achievement Awards Secretary's 2014 Achievement Awards PDF icon Energy Sciences Building (ESB) Project (Office of Science) More Documents & Publications 2014 Awards for Project Management Secretary's 2013 Achievement Awards Secretary's 2014 Achievement Awards

  17. Secretary's Achievment Award | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Achievment Award Secretary's Achievment Award PDF icon Office of Environmental Management K-33 gaseous Diffusion Process building Project.pdf More Documents & Publications Secretary's Achievement Award PM Workshop 2012 Awards Recognition - Secretary's Awards Secretary's Achievement Award

  18. Secretary's 2013 Achievement Awards | Department of Energy

    Energy Savers [EERE]

    Awards Secretary's 2013 Achievement Awards PDF icon Berkeley Laboratory Laser Accelerator Project (Office of Science) More Documents & Publications Secretary's 2013 Achievement Awards Secretary's 2013 Achievement Awards Secretary's 2014 Achievement Awards

  19. Secretary's Achievment Award | Department of Energy

    Energy Savers [EERE]

    Achievment Award Secretary's Achievment Award PDF icon Office of Environmental Management K-33 gaseous Diffusion Process building Project.pdf More Documents & Publications Secretary's Achievement Award PM Workshop 2012 Awards Recognition - Secretary's Awards Secretary's Achievement Award

  20. Method of controlling fusion reaction rates

    DOE Patents [OSTI]

    Kulsrud, Russell M. (Princeton, NJ); Furth, Harold P. (Princeton, NJ); Valeo, Ernest J. (Princeton Junction, NJ); Goldhaber, Maurice (Bayport, NY)

    1988-01-01

    A method of controlling the reaction rates of the fuel atoms in a fusion reactor comprises the step of polarizing the nuclei of the fuel atoms in a particular direction relative to the plasma confining magnetic field. Fusion reaction rates can be increased or decreased, and the direction of emission of the reaction products can be controlled, depending on the choice of polarization direction.

  1. Plasmas are Hot and Fusion is Cool

    SciTech Connect (OSTI)

    2011-01-01

    Plasmas are Hot and Fusion is Cold. The DOE Princeton Plasma Physics Laboratory (PPPL) collaborates to develop fusion as a safe, clean and abundant energy source for the future. This video discusses PPPL's research and development on plasma, the fourth state of matter.

  2. Fusion breeder: its potential role and prospects

    SciTech Connect (OSTI)

    Lee, J.D.

    1981-01-01

    The fusion breeder is a concept that utilizes 14 MeV neutrons from D + T ..-->.. n(14.1 MeV) + ..cap alpha..(3.5 MeV) fusion reactions to produce more fuel than the tritium (T) needed to sustain the fusion process. This excess fuel production capacity is used to produce fissile material (Pu-239 or U-233) for subsequent use in fission reactors. We are concentrating on a class of blankets we call fission suppressed. The blanket is the region surrounding the fusion plasma in which fusion neutrons interact to produce fuel and heat. The fission-suppressed blanket uses non-fission reactions (mainly (n,2n) or (n,n't)) to generate excess neutrons for the production of net fuel. This is in contrast to the fast fission class of blankets which use (n,fiss) reactions to generate excess neutrons. Fusion reactors with fast fission blankets are commony known as fusion-fission hybrids because they combine fusion and fission in the same device.

  3. Industrial Scale Demonstration of Smart Manufacturing Achieving...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Scale Demonstration of Smart Manufacturing Achieving Transformational Energy Productivity Gains Industrial Scale Demonstration of Smart Manufacturing Achieving Transformational...

  4. Highly Charged Ions in Magnetic Fusion Plasmas: Research Opportunities...

    Office of Scientific and Technical Information (OSTI)

    Highly Charged Ions in Magnetic Fusion Plasmas: Research Opportunities and Diagnostic Necessities Citation Details In-Document Search Title: Highly Charged Ions in Magnetic Fusion ...

  5. Fusion Nuclear Science and Technology Program - Status and Plans...

    Office of Environmental Management (EM)

    Plans for Tritium Research Fusion Nuclear Science and Technology Program - Status and ... Idaho on September 23-25, 2014. PDF icon Fusion Nuclear Science and Technology Program - ...

  6. Fusion Nuclear Science and Technology Program - Status and plans...

    Office of Environmental Management (EM)

    plans for tritium research Fusion Nuclear Science and Technology Program - Status and ... New Jersey on May 05-07, 2015. PDF icon Fusion Nuclear Science and Technology Program - ...

  7. Plasma Turbulence Simulations Reveal Promising Insight for Fusion...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Insight for Fusion Energy By Argonne National Laboratory March 31, 2014 Tweet Widget Google Plus One Share on Facebook Simulation of microturbulence in a tokamak fusion device. ...

  8. Scientists discuss progress toward magnetic fusion energy at...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Scientists discuss progress toward magnetic fusion energy at 2013 AAAS annual meeting ... Scientists participating in the worldwide effort to develop magnetic fusion energy for ...

  9. "Fueling method for small, steady-state, aneutronic FRC fusion...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Fueling method for small, steady-state, aneutronic FRC fusion reactors" Inventors Samuel ... of small field-reversed-configuration (FRC) fusion reactors enabling steady power ...

  10. An improvement to the global standard for modeling fusion plasmas...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    The program's updates, reported this week in Nuclear Fusion, could ... as ITER, the international experiment under construction in France to demonstrate the feasibility of fusion power. ...

  11. What Causes Electron Heat Loss in Fusion Plasma?

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Causes Heat Loss in Fusion Plasmas? What Causes Electron Heat Loss in Fusion Plasma? 3D Simulations Run at NERSC Unlock Puzzling Secret September 22, 2015 fusionplasmabelova ...

  12. DOE Science Showcase - Clean Fusion Power | OSTI, US Dept of...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Clean Fusion Power Search Results from DOE Databases View research documents, ... related to advanced systems for fusion energy and nuclear power, primary scientific challenges ...

  13. recognition for outstanding lifetime achievement

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    recognition for outstanding lifetime achievement - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste

  14. Progress in Heavy Ion Fusion

    SciTech Connect (OSTI)

    Herrmannsfeldt, W.B.

    1988-09-01

    The progress of the field of Heavy Ion Fusion has been documented in the proceedings of the series of International Symposia that, in recent years, have occurred every second year. The latest of these conferences was hosted by Gesellshaft fuer Schwerionenforshung (GSI) in Darmstadt, West Germany, June 28-30, 1988. For this report, a few highlights from the conference are selected, stressing experimental progress and prospects for future advances. A little extra time is devoted to report on the developments at the Lawrence Berkeley Laboratory (LBL) which is the center for most of the HIFAR program. The Director of the HIFAR program at LBL is Denis Keefe, who presented the HIF report at the last two of the meetings in this series, and in whose place the author is appearing now. 4 refs., 1 fig.

  15. Ion Rings for Magnetic Fusion

    SciTech Connect (OSTI)

    Greenly, John, B.

    2005-07-31

    This Final Technical Report presents the results of the program, Ion Rings for Magnetic Fusion, which was carried out under Department of Energy funding during the period August, 1993 to January, 2005. The central objective of the program was to study the properties of field-reversed configurations formed by ion rings. In order to reach this objective, our experimental program, called the Field-reversed Ion Ring Experiment, FIREX, undertook to develop an efficient, economical technology for the production of field-reversed ion rings. A field-reversed configuration (FRC) in which the azimuthal (field-reversing) current is carried by ions with gyro-radius comparable to the magnetic separatrix radius is called a field-reversed ion ring. A background plasma is required for charge neutralization of the ring, and this plasma will be confined within the ring's closed magnetic flux. Ion rings have long been of interest as the basis of compact magnetic fusion reactors, as the basis for a high-power accelerator for an inertial fusion driver, and for other applications of high power ion beams or plasmas of high energy density. Specifically, the FIREX program was intended to address the longstanding question of the contribution of large-orbit ions to the observed stability of experimental FRCs to the MHD tilt mode. Typical experimental FRCs with s {approx} 2-4, where s is the ratio of separatrix radius to ion gyro-radius, have been stable to tilting, but desired values for a fusion reactor, s > 20, should be unstable. The FIREX ring would consist of a plasma with large s for the background ions, but with s {approx} 1 for the ring ions. By varying the proportions of these two populations, the minimum proportion of large-orbit ions necessary for stability could be determined. The incorporation of large-orbit ions, perhaps by neutral-beam injection, into an FRC has been advanced for the purpose of stabilizing, heating, controlling angular momentum, and aiding the formation of a reactor-scale FRC, and the FIREX program was intended to test the ideas behind this approach. We will describe in this report the technological development path and advances in physics understanding that allowed FIREX to reach a regime in which ion rings were reproducibly created with up to about half the current necessary to produce field reversal. Unfortunately, the experiments were limited to this level by a fundamental, unanticipated aspect of the physics of strong ion rings in plasma. The FIREX ring is a strongly anisotropic, current-carrying population of ions moving faster than the Alfven speed in the background plasma. The rapidly changing ring current excites very large-amplitude Alfven waves in the plasma, and these waves strongly affect the ring, causing rapid energy loss in a way that is not compatible with the success of the ring trapping scenario around which FIREX was designed. The result was that FIREX rings were always very short-lived. We will discuss the implication of these results for possible future use of large-orbit ions in FRCs. In short, it appears that a certain range of the parameters characterizing the ring Alfven mach number and distribution function must be avoided to allow the existence of a long-lived energetic ion component in an FRC. This report will explain why FIREX experimental results cannot be directly scaled to quantitatively predict this range for a particular FRC configuration. This will require accurate, three-dimensional simulations. FIREX results do constitute a very good dataset for validating such a code, and simulations already carried out during this program provide a guide to the important physics involved.

  16. Multishell inertial confinement fusion target

    DOE Patents [OSTI]

    Holland, James R. (Butler, PA); Del Vecchio, Robert M. (Vandergrift, PA)

    1984-01-01

    A method of fabricating multishell fuel targets for inertial confinement fusion usage. Sacrificial hemispherical molds encapsulate a concentric fuel pellet which is positioned by fiber nets stretched tautly across each hemispherical mold section. The fiber ends of the net protrude outwardly beyond the mold surfaces. The joint between the sacrificial hemispheres is smoothed. A ceramic or glass cover is then deposited about the finished mold surfaces to produce an inner spherical surface having continuously smooth surface configuration. The sacrificial mold is removed by gaseous reaction accomplished through the porous ceramic cover prior to enclosing of the outer sphere by addition of an outer coating. The multishell target comprises the inner fuel pellet concentrically arranged within a surrounding coated cover or shell by fiber nets imbedded within the cover material.

  17. Multishell inertial confinement fusion target

    DOE Patents [OSTI]

    Holland, James R. (Butler, PA); Del Vecchio, Robert M. (Vandergrift, PA)

    1987-01-01

    A method of fabricating multishell fuel targets for inertial confinement fusion usage. Sacrificial hemispherical molds encapsulate a concentric fuel pellet which is positioned by fiber nets stretched tautly across each hemispherical mold section. The fiber ends of the net protrude outwardly beyond the mold surfaces. The joint between the sacrificial hemispheres is smoothed. A ceramic or glass cover is then deposited about the finished mold surfaces to produce an inner spherical surface having continuously smooth surface configuration. The sacrificial mold is removed by gaseous reactions accomplished through the porous ceramic cover prior to enclosing of the outer sphere by addition of an outer coating. The multishell target comprises the inner fuel pellet concentrically arranged within a surrounding coated cover or shell by fiber nets imbedded within the cover material.

  18. Fusion Techniques for the Oxidation of Refractory Actinide Oxides

    SciTech Connect (OSTI)

    Rudisill, T.S.

    1999-04-15

    Small-scale experiments were performed to demonstrate the feasibility of fusing refractory actinide oxides with a series of materials commonly used to decompose minerals, glasses, and other refractories as a pretreatment to dissolution and subsequent recovery operations. In these experiments, 1-2 g of plutonium or neptunium oxide (PuO2 or NpO2) were calcined at 900 degrees Celsius, mixed and heated with the fusing reagent(s), and dissolved. For refractory PuO2, the most effective material tested was a lithium carbonate (Li2CO3)/sodium tetraborate (Na2B4O7) mixture which aided in the recovery of 90 percent of the plutonium. The fused product was identified as a lithium plutonate (Li3PuO4) by x-ray diffraction. The use of a Li2CO3/Na2B4O7 mixture to solubilize high-fired NpO2 was not as effective as demonstrated for refractory PuO2. In a small-scale experiment, 25 percent of the NpO2 was oxidized to a neptunium (VI) species that dissolved in nitric acid. The remaining neptunium was then easily recovered from the residue by fusing with sodium peroxide (Na2O2). Approximately 70 percent of the neptunium dissolved in water to yield a basic solution of neptunium (VII). The remainder was recovered as a neptunium (VI) solution by dissolving the residue in 8M nitric acid. In subsequent experiments with Na2O2, the ratio of neptunium (VII) to (VI) was shown to be a function of the fusion temperature, with higher temperatures (greater than approximately 400 degrees C) favoring the formation of neptunium (VII). The fusion of an actual plutonium-containing residue with Na2O2 and subsequent dissolution was performed to demonstrate the feasibility of a pretreatment process on a larger scale. Sodium peroxide was chosen due to the potential of achieving higher actinide recoveries from refractory materials. In this experiment, nominally 10 g of a graphite-containing residue generated during plutonium casting operations was initially calcined to remove the graphite. Removal of combustible material prior to a large-scale fusion with Na2O2 is needed due to the large amount of heat liberated during oxidation. Two successive fusions using the residue from the calcination and the residue generated from the initial dissolution allowed recovery of 98 percent of the plutonium. The fusion of the residue following the first dissolution was performed at a higher temperature (600 degrees Celsius versus 450 degrees Celsius during the first fusion). The ability to recover most of the remaining plutonium from the residue suggest the oxidation efficiency of the Na2O2 fusion improves with higher temperatures similar to results observed with NpO2 fusion.

  19. Reliable clock estimation using linear weighted fusion based on pairwise broadcast synchronization

    SciTech Connect (OSTI)

    Shi, Xin Zhao, Xiangmo Hui, Fei Ma, Junyan Yang, Lan

    2014-10-06

    Clock synchronization in wireless sensor networks (WSNs) has been studied extensively in recent years and many protocols are put forward based on the point of statistical signal processing, which is an effective way to optimize accuracy. However, the accuracy derived from the statistical data can be improved mainly by sufficient packets exchange, which will consume the limited power resources greatly. In this paper, a reliable clock estimation using linear weighted fusion based on pairwise broadcast synchronization is proposed to optimize sync accuracy without expending additional sync packets. As a contribution, a linear weighted fusion scheme for multiple clock deviations is constructed with the collaborative sensing of clock timestamp. And the fusion weight is defined by the covariance of sync errors for different clock deviations. Extensive simulation results show that the proposed approach can achieve better performance in terms of sync overhead and sync accuracy.

  20. Electrochemically induced nuclear fusion of deuterium; The existence of negatively charged deuteride ions

    SciTech Connect (OSTI)

    Jorne, J. . Dept. of Chemical Engineering)

    1990-11-01

    In this paper cold fusion of deuterium by electrolysis of heavy water onto a palladium (or titanium) cathode is reported. Contrary to the assumption of Fleishmann and Pons that electrochemically compressed D{sup +} exists inside the palladium cathode, the observations of Jones et al. can be partially explained by the simultaneous presence of deuteride D{sup {minus}} and the highly mobile positive deuterium ion D{sup +}. The opposite charges reduce the intranuclear distance and enhance the tunneling fusion rate. Furthermore, alloying of lithium with palladium can stabilize a negatively charged deuteride ion due to the salinelike character of lithium deuteride. The enormous pressure (or fugacity), achieved by the applied electrochemical potential (10{sup 30} atm), is a virtual pressure that would have existed in equilibrium with palladium deuteride (PdD{sub x}). It is speculated that nuclear fusion occurs at the surface, and the PdD{sub x} serves as a reservoir for the supply of deuteride ions.

  1. Summary of the report of the Senior Committee on Environmental, Safety, and Economic Aspects of Magnetic Fusion Energy

    SciTech Connect (OSTI)

    Holdren, J.P.; Berwald, D.H.; Budnitz, R.J.; Crocker, J.G.; Delene, J.G.; Endicott, R.D.; Kazimi, M.S.; Krakowski, R.A.; Logan, B.G.; Schultz, K.R.

    1987-09-10

    The Senior Committee on Environmental, Safety, and Economic Aspects of Magnetic Fusion Energy (ESECOM) has assessed magnetic fusion energy's prospects for providing energy with economic, environmental, and safety characteristics that would be attractive compared with other energy sources (mainly fission) available in the year 2015 and beyond. ESECOM gives particular attention to the interaction of environmental, safety, and economic characteristics of a variety of magnetic fusion reactors, and compares them with a variety of fission cases. Eight fusion cases, two fusion-fission hybrid cases, and four fission cases are examined, using consistent economic and safety models. These models permit exploration of the environmental, safety, and economic potential of fusion concepts using a wide range of possible materials choices, power densities, power conversion schemes, and fuel cycles. The ESECOM analysis indicates that magnetic fusion energy systems have the potential to achieve costs-of-electricity comparable to those of present and future fission systems, coupled with significant safety and environmental advantages. 75 refs., 2 figs., 24 tabs.

  2. Fusion utility in the Knudsen layer

    SciTech Connect (OSTI)

    Davidovits, Seth; Fisch, Nathaniel J.

    2014-09-15

    In inertial confinement fusion, the loss of fast ions from the edge of the fusing hot-spot region reduces the reactivity below its Maxwellian value. The loss of fast ions may be pronounced because of the long mean free paths of fast ions, compared with those of thermal ions. We introduce a fusion utility function to demonstrate essential features of this Knudsen layer effect, in both magnetized and unmagnetized cases. The fusion utility concept is also used to evaluate the restoring reactivity in the Knudsen layer by manipulating fast ions in phase space using waves.

  3. Fusion Utility in the Knudsen Layer

    SciTech Connect (OSTI)

    Davidovits, Seth; Fisch, Nathaniel J.

    2014-08-01

    In inertial confi#12;nement fusion, the loss of fast ions from the edge of the fusing hot-spot region reduces the reactivity below its Maxwellian value. The loss of fast ions may be pronounced because of the long mean free paths of fast ions, compared to those of thermal ions. We introduce a fusion utility function to demonstrate essential features of this Knudsen layer e#11;ffect, in both magnetized and unmagnetized cases. The fusion utility concept is also used to evaluate restoring the reactivity in the Knudsen layer by manipulating fast ions in phase space using waves.

  4. Magnetohydrodynamic modes analysis and control of Fusion Advanced Studies Torus high-current scenarios

    SciTech Connect (OSTI)

    Villone, F.; Mastrostefano, S.; Calabr, G.; Vlad, G.; Crisanti, F.; Fusco, V.; Marchiori, G.; Bolzonella, T.; Marrelli, L.; Martin, P.; Liu, Y. Q.

    2014-08-15

    One of the main FAST (Fusion Advanced Studies Torus) goals is to have a flexible experiment capable to test tools and scenarios for safe and reliable tokamak operation, in order to support ITER and help the final DEMO design. In particular, in this paper, we focus on operation close to a possible border of stability related to low-q operation. To this purpose, a new FAST scenario has then been designed at I{sub p}?=?10 MA, B{sub T}?=?8.5?T, q{sub 95}???2.3. Transport simulations, carried out by using the code JETTO and the first principle transport model GLF23, indicate that, under these conditions, FAST could achieve an equivalent Q???3.5. FAST will be equipped with a set of internal active coils for feedback control, which will produce magnetic perturbation with toroidal number n?=?1 or n?=?2. Magnetohydrodynamic (MHD) mode analysis and feedback control simulations performed with the codes MARS, MARS-F, CarMa (both assuming the presence of a perfect conductive wall and using the exact 3D resistive wall structure) show the possibility of the FAST conductive structures to stabilize n?=?1 ideal modes. This leaves therefore room for active mitigation of the resistive mode (down to a characteristic time of 1?ms) for safety purposes, i.e., to avoid dangerous MHD-driven plasma disruption, when working close to the machine limits and magnetic and kinetic energy density not far from reactor values.

  5. Assessment of ion kinetic effects in shock-driven inertial confinement fusion (ICF) implosions using fusion burn imaging

    SciTech Connect (OSTI)

    Rosenberg, M. J.; Séguin, F. H.; Amendt, P. A.; Atzeni, S.; Rinderknecht, H. G.; Hoffman, N. M.; Zylstra, A. B.; Li, C. K.; Sio, H.; Gatu Johnson, M.; Frenje, J. A.; Petrasso, R. D.; Glebov, V. Yu.; Stoeckl, C.; Seka, W.; Marshall, F. J.; Delettrez, J. A.; Sangster, T. C.; Betti, R.; Wilks, S. C.; Pino, J.; Kagan, G.; Molvig, K.; Nikroo, A.

    2015-06-02

    The significance and nature of ion kinetic effects in D³He-filled, shock-driven inertial confinement fusion implosions are assessed through measurements of fusion burn profiles. Over this series of experiments, the ratio of ion-ion mean free path to minimum shell radius (the Knudsen number, NK) was varied from 0.3 to 9 in order to probe hydrodynamic-like to strongly kinetic plasma conditions; as the Knudsen number increased, hydrodynamic models increasingly failed to match measured yields, while an empirically-tuned, first-step model of ion kinetic effects better captured the observed yield trends [Rosenberg et al., Phys. Rev. Lett. 112, 185001 (2014)]. Here, spatially resolved measurements of the fusion burn are used to examine kinetic ion transport effects in greater detail, adding an additional dimension of understanding that goes beyond zero-dimensional integrated quantities to one-dimensional profiles. In agreement with the previous findings, a comparison of measured and simulated burn profiles shows that models including ion transport effects are able to better match the experimental results. In implosions characterized by large Knudsen numbers (NK ~ 3), the fusion burn profiles predicted by hydrodynamics simulations that exclude ion mean free path effects are peaked far from the origin, in stark disagreement with the experimentally observed profiles, which are centrally peaked. In contrast, a hydrodynamics simulation that includes a model of ion diffusion is able to qualitatively match the measured profile shapes. Therefore, ion diffusion or diffusion-like processes are identified as a plausible explanation of the observed trends, though further refinement of the models is needed for a more complete and quantitative understanding of ion kinetic effects.

  6. Assessment of ion kinetic effects in shock-driven inertial confinement fusion implosions using fusion burn imaging

    SciTech Connect (OSTI)

    Rosenberg, M. J. Séguin, F. H.; Rinderknecht, H. G.; Zylstra, A. B.; Li, C. K.; Sio, H.; Johnson, M. Gatu; Frenje, J. A.; Petrasso, R. D.; Amendt, P. A.; Wilks, S. C.; Pino, J.; Atzeni, S.; Hoffman, N. M.; Kagan, G.; Molvig, K.; Glebov, V. Yu.; Stoeckl, C.; Seka, W.; Marshall, F. J.; and others

    2015-06-15

    The significance and nature of ion kinetic effects in D{sup 3}He-filled, shock-driven inertial confinement fusion implosions are assessed through measurements of fusion burn profiles. Over this series of experiments, the ratio of ion-ion mean free path to minimum shell radius (the Knudsen number, N{sub K}) was varied from 0.3 to 9 in order to probe hydrodynamic-like to strongly kinetic plasma conditions; as the Knudsen number increased, hydrodynamic models increasingly failed to match measured yields, while an empirically-tuned, first-step model of ion kinetic effects better captured the observed yield trends [Rosenberg et al., Phys. Rev. Lett. 112, 185001 (2014)]. Here, spatially resolved measurements of the fusion burn are used to examine kinetic ion transport effects in greater detail, adding an additional dimension of understanding that goes beyond zero-dimensional integrated quantities to one-dimensional profiles. In agreement with the previous findings, a comparison of measured and simulated burn profiles shows that models including ion transport effects are able to better match the experimental results. In implosions characterized by large Knudsen numbers (N{sub K} ∼ 3), the fusion burn profiles predicted by hydrodynamics simulations that exclude ion mean free path effects are peaked far from the origin, in stark disagreement with the experimentally observed profiles, which are centrally peaked. In contrast, a hydrodynamics simulation that includes a model of ion diffusion is able to qualitatively match the measured profile shapes. Therefore, ion diffusion or diffusion-like processes are identified as a plausible explanation of the observed trends, though further refinement of the models is needed for a more complete and quantitative understanding of ion kinetic effects.

  7. Assessment of ion kinetic effects in shock-driven inertial confinement fusion (ICF) implosions using fusion burn imaging

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Rosenberg, M. J.; Séguin, F. H.; Amendt, P. A.; Atzeni, S.; Rinderknecht, H. G.; Hoffman, N. M.; Zylstra, A. B.; Li, C. K.; Sio, H.; Gatu Johnson, M.; et al

    2015-06-02

    The significance and nature of ion kinetic effects in D³He-filled, shock-driven inertial confinement fusion implosions are assessed through measurements of fusion burn profiles. Over this series of experiments, the ratio of ion-ion mean free path to minimum shell radius (the Knudsen number, NK) was varied from 0.3 to 9 in order to probe hydrodynamic-like to strongly kinetic plasma conditions; as the Knudsen number increased, hydrodynamic models increasingly failed to match measured yields, while an empirically-tuned, first-step model of ion kinetic effects better captured the observed yield trends [Rosenberg et al., Phys. Rev. Lett. 112, 185001 (2014)]. Here, spatially resolved measurementsmore » of the fusion burn are used to examine kinetic ion transport effects in greater detail, adding an additional dimension of understanding that goes beyond zero-dimensional integrated quantities to one-dimensional profiles. In agreement with the previous findings, a comparison of measured and simulated burn profiles shows that models including ion transport effects are able to better match the experimental results. In implosions characterized by large Knudsen numbers (NK ~ 3), the fusion burn profiles predicted by hydrodynamics simulations that exclude ion mean free path effects are peaked far from the origin, in stark disagreement with the experimentally observed profiles, which are centrally peaked. In contrast, a hydrodynamics simulation that includes a model of ion diffusion is able to qualitatively match the measured profile shapes. Therefore, ion diffusion or diffusion-like processes are identified as a plausible explanation of the observed trends, though further refinement of the models is needed for a more complete and quantitative understanding of ion kinetic effects.« less

  8. Assessment of ion kinetic effects in shock-driven inertial confinement fusion (IFC) implosions using fusion burn imaging

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Rosenberg, M. J.; Sguin, F. H.; Amendt, P. A.; Atzeni, S.; Rinderknecht, H. G.; Hoffman, N. M.; Zylstra, A. B.; Li, C. K.; Sio, H.; Gatu Johnson, M.; et al

    2015-06-02

    The significance and nature of ion kinetic effects in DHe-filled, shock-driven inertial confinement fusion implosions are assessed through measurements of fusion burn profiles. Over this series of experiments, the ratio of ion-ion mean free path to minimum shell radius (the Knudsen number, NK) was varied from 0.3 to 9 in order to probe hydrodynamic-like to strongly kinetic plasma conditions; as the Knudsen number increased, hydrodynamic models increasingly failed to match measured yields, while an empirically-tuned, first-step model of ion kinetic effects better captured the observed yield trends [Rosenberg et al., Phys. Rev. Lett. 112, 185001 (2014)]. Here, spatially resolved measurementsmoreof the fusion burn are used to examine kinetic ion transport effects in greater detail, adding an additional dimension of understanding that goes beyond zero-dimensional integrated quantities to one-dimensional profiles. In agreement with the previous findings, a comparison of measured and simulated burn profiles shows that models including ion transport effects are able to better match the experimental results. In implosions characterized by large Knudsen numbers (NK ~ 3), the fusion burn profiles predicted by hydrodynamics simulations that exclude ion mean free path effects are peaked far from the origin, in stark disagreement with the experimentally observed profiles, which are centrally peaked. In contrast, a hydrodynamics simulation that includes a model of ion diffusion is able to qualitatively match the measured profile shapes. Therefore, ion diffusion or diffusion-like processes are identified as a plausible explanation of the observed trends, though further refinement of the models is needed for a more complete and quantitative understanding of ion kinetic effects.less

  9. Basics of Fusion-Fissison Research Facility (FFRF) as a Fusion Neutron Source

    SciTech Connect (OSTI)

    Leonid E. Zakharov

    2011-06-03

    FFRF, standing for the Fusion-Fission Research Facility represents an option for the next step project of ASIPP (Hefei, China) aiming to a first fusion-fission multifunctional device [1]. FFRF strongly relies on new, Lithium Wall Fusion plasma regimes, the development of which has already started in the US and China. With R/a=4/1m/m, Ipl=5 MA, Btor=4-6 T, PDT=50- 100 MW, Pfission=80-4000MW, 1 m thick blanket, FFRF has a unique fusion mission of a stationary fusion neutron source. Its pioneering mission of merging fusion and fission consists in accumulation of design, experimental, and operational data for future hybrid applications.

  10. Fusion energy development: Breakeven and beyond: Keynote address

    SciTech Connect (OSTI)

    Furth, H.P.

    1988-02-01

    The scientific feasibility, technological inevitability, and economic necessity of fusion as an energy source are discussed.

  11. COLLOQUIUM: Fusion Rockets for Planetary Defense | Princeton...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    6, 2016, 4:15pm to 5:30pm MBG AUDITORIUM COLLOQUIUM: Fusion Rockets for Planetary Defense Dr. Glen Wurden Los Alamos National Laboratory Contact Information Coordinator(s): Ms....

  12. 1995 International Sherwood Fusion Theory Conference

    SciTech Connect (OSTI)

    1995-07-01

    This book is a guide to the 1995 International Sherwood Fusion Theory Conference. It consists largely of abstracts of the oral and poster presentations that were to be made, and gives some general information about the conference and its schedule.

  13. Time-resolved compression of a capsule with a cone to high density for fast-ignition laser fusion

    SciTech Connect (OSTI)

    Theobald, W.; Solodov, A. A.; Stoeckl, C.; Anderson, K. S.; Beg, F. N.; Epstein, R.; Fiksel, G.; Giraldez, E. M.; Glebov, V. Yu.; Habara, H.; Ivancic, S.; Jarrott, L. C.; Marshall, F. J.; McKiernan, G.; McLean, H. S.; Mileham, C.; Nilson, P. M.; Patel, P. K.; Pérez, F.; Sangster, T. C.; Santos, J. J.; Sawada, H.; Shvydky, A.; Stephens, R. B.; Wei, M. S.

    2014-12-12

    The advent of high-intensity lasers enables us to recreate and study the behaviour of matter under the extreme densities and pressures that exist in many astrophysical objects. It may also enable us to develop a power source based on laser-driven nuclear fusion. Achieving such conditions usually requires a target that is highly uniform and spherically symmetric. Here we show that it is possible to generate high densities in a so-called fast-ignition target that consists of a thin shell whose spherical symmetry is interrupted by the inclusion of a metal cone. Using picosecond-time-resolved X-ray radiography, we show that we can achieve areal densities in excess of 300 mg cm#2;-2 with a nanosecond-duration compression pulse -- the highest areal density ever reported for a cone-in-shell target. Such densities are high enough to stop MeV electrons, which is necessary for igniting the fuel with a subsequent picosecond pulse focused into the resulting plasma.

  14. Secretary's Achievement Award | Department of Energy

    Energy Savers [EERE]

    Environmental Management Idaho Nuclear facility Decontamination & Decommissioning Project.pdf More Documents & Publications Secretary's Achievment Award Secretary's Achievement Award PM Workshop 2012 Awards Recognition - Secretary's Awards

  15. Fluidized wall for protecting fusion chamber walls

    DOE Patents [OSTI]

    Maniscalco, James A. (Danville, CA); Meier, Wayne R. (Livermore, CA)

    1982-01-01

    Apparatus for protecting the inner wall of a fusion chamber from microexplosion debris, x-rays, neutrons, etc. produced by deuterium-tritium (DT) targets imploded within the fusion chamber. The apparatus utilizes a fluidized wall similar to a waterfall comprising liquid lithium or solid pellets of lithium-ceramic, the waterfall forming a blanket to prevent damage of the structural materials of the chamber.

  16. Learn More about Fusion & Lasers

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Learn More about Fusion & Lasers How Lasers Work Learn how lasers were developed and how they work. Outreach NIF & Photon Science researchers take learning opportunities on the road. Glossary Don't know what something means? Find definitions of terms related to NIF, fusion, and photon science in our glossary. For Teachers LLNL's Science Education Program provides professional development instruction to in-service and pre-service teachers. For Kids See how we make giant crystals and how

  17. Cold versus hot fusion deuterium branching ratios

    SciTech Connect (OSTI)

    Fox, H.; Bass, R.

    1995-12-31

    A major source of misunderstanding of the nature of cold nuclear fusion has been the expectation that the deuterium branching ratios occurring within a palladium lattice would be consistent with the gas-plasma branching ratios. This misunderstanding has led to the concept of the dead graduate student, the 1989`s feverish but fruitless search for neutron emissions from cold fusion reactors, and the follow-on condemnation of the new science of cold fusion. The experimental facts are that in a properly loaded palladium lattice, the deuterium fusion produces neutrons at little above background, a greatly less-than-expected production of tritium (the tritium desert), and substantially more helium-4 than is observed in hot plasma physics. The experimental evidence is now compelling (800 reports of success from 30 countries) that cold nuclear fusion is a reality, that the branching ratios are unexpected, and that a new science is struggling to be recognized. Commercialization of some types of cold fusion devices has already begun.

  18. Magnet design considerations for Fusion Nuclear Science Facility

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Zhai, Yuhu; Kessel, Chuck; El-guebaly, Laila; Titus, Peter

    2016-02-25

    The Fusion Nuclear Science Facility (FNSF) is a nuclear confinement facility to provide a fusion environment with components of the reactor integrated together to bridge the technical gaps of burning plasma and nuclear science between ITER and the demonstration power plant (DEMO). Compared to ITER, the FNSF is smaller in size but generates much higher magnetic field, 30 times higher neutron fluence with 3 orders of magnitude longer plasma operation at higher operating temperatures for structures surrounding the plasma. Input parameters to the magnet design from system code analysis include magnetic field of 7.5 T at the plasma center withmore » plasma major radius of 4.8 m and minor radius of 1.2 m, and a peak field of 15.5 T on the TF coils for FNSF. Both low temperature superconductor (LTS) and high temperature superconductor (HTS) are considered for the FNSF magnet design based on the state-of-the-art fusion magnet technology. The higher magnetic field can be achieved by using the high performance ternary Restack Rod Process (RRP) Nb3Sn strands for toroidal field (TF) magnets. The circular cable-in-conduit conductor (CICC) design similar to ITER magnets and a high aspect ratio rectangular CICC design are evaluated for FNSF magnets but low activation jacket materials may need to be selected. The conductor design concept and TF coil winding pack composition and dimension based on the horizontal maintenance schemes are discussed. Neutron radiation limits for the LTS and HTS superconductors and electrical insulation materials are also reviewed based on the available materials previously tested. As a result, the material radiation limits for FNSF magnets are defined as part of the conceptual design studies for FNSF magnets.« less

  19. Fusion materials science and technology research opportunities now and during the ITER era

    SciTech Connect (OSTI)

    S.J. Zinkle; J.P. Planchard; R.W. Callis; C.E. Kessel; P.J. Lee; K.A. McCarty; Various Others

    2014-10-01

    Several high-priority near-term potential research activities to address fusion nuclear science challenges are summarized. General recommendations include: (1) Research should be preferentially focused on the most technologically advanced options (i.e., options that have been developed at least through the singleeffects concept exploration stage, technology readiness levels >3), (2) Significant near-term progress can be achieved by modifying existing facilities and/or moderate investment in new medium-scale facilities, and (3) Computational modeling for fusion nuclear sciences is generally not yet sufficiently robust to enable truly predictive results to be obtained, but large reductions in risk, cost and schedule can be achieved by careful integration of experiment and modeling.

  20. Gasification of high ash, high ash fusion temperature bituminous coals

    DOE Patents [OSTI]

    Liu, Guohai; Vimalchand, Pannalal; Peng, WanWang

    2015-11-13

    This invention relates to gasification of high ash bituminous coals that have high ash fusion temperatures. The ash content can be in 15 to 45 weight percent range and ash fusion temperatures can be in 1150.degree. C. to 1500.degree. C. range as well as in excess of 1500.degree. C. In a preferred embodiment, such coals are dealt with a two stage gasification process--a relatively low temperature primary gasification step in a circulating fluidized bed transport gasifier followed by a high temperature partial oxidation step of residual char carbon and small quantities of tar. The system to process such coals further includes an internally circulating fluidized bed to effectively cool the high temperature syngas with the aid of an inert media and without the syngas contacting the heat transfer surfaces. A cyclone downstream of the syngas cooler, operating at relatively low temperatures, effectively reduces loading to a dust filtration unit. Nearly dust- and tar-free syngas for chemicals production or power generation and with over 90%, and preferably over about 98%, overall carbon conversion can be achieved with the preferred process, apparatus and methods outlined in this invention.

  1. Self-similar structure and experimental signatures of suprathermal ion distribution in inertial confinement fusion implosions

    SciTech Connect (OSTI)

    Kagan, Grigory; Svyatskiy, D.; Rinderknecht, H. G.; Rosenberg, M. J.; Zylstra, A. B.; Huang, C. -K.; McDevitt, C. J.

    2015-09-03

    The distribution function of suprathermal ions is found to be self-similar under conditions relevant to inertial confinement fusion hot spots. By utilizing this feature, interference between the hydrodynamic instabilities and kinetic effects is for the first time assessed quantitatively to find that the instabilities substantially aggravate the fusion reactivity reduction. Thus, the ion tail depletion is also shown to lower the experimentally inferred ion temperature, a novel kinetic effect that may explain the discrepancy between the exploding pusher experiments and rad-hydro simulations and contribute to the observation that temperature inferred from DD reaction products is lower than from DT at the National Ignition Facility.

  2. Electron kinetic effects on interferometry and polarimetry in high temperature fusion plasmas

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    vvmirnov IP Address: 128.104.165.118 This content was downloaded on 09/07/2014 at 19:52 Please note that terms and conditions apply. Electron kinetic effects on interferometry and polarimetry in high temperature fusion plasmas View the table of contents for this issue, or go to the journal homepage for more 2013 Nucl. Fusion 53 113005 (http://iopscience.iop.org/0029-5515/53/11/113005) Home Search Collections Journals About Contact us My IOPscience IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY

  3. Security Conditions

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2004-07-08

    This Notice ensures that DOE uniformly meets the requirements of the Homeland Security Advisory System outlined in Homeland Security Presidential Directive-3, Threat Conditions and Associated Protective Measures, dated 3-11-02, and provides responses specified in Presidential Decision Directive 39, U.S. Policy on Counterterrorism (U), dated 6-21-95. It cancels DOE N 473.8, Security Conditions, dated 8-7-02. Extended until 7-7-06 by DOE N 251.64, dated 7-7-05 Cancels DOE N 473.8

  4. Weather Conditions at LBNL

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Weather Conditions at LBNL

  5. Meteorological Conditions at LBNL

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Meteorological Conditions at LBNL

  6. Fusion and Plasmas | U.S. DOE Office of Science (SC)

    Office of Science (SC) Website

    Fusion and Plasmas Fusion Energy Sciences (FES) FES Home About Organization Chart .pdf ... Research Facilities Science Highlights Benefits of FES Funding Opportunities Fusion Energy ...

  7. Current Activities Assessing Butt Fusion Joint Integrity in High Density Polyethylene Piping

    SciTech Connect (OSTI)

    Crawford, Susan L.; Cinson, Anthony D.; Doctor, Steven R.; Denslow, Kayte M.

    2012-09-01

    The Pacific Northwest National Laboratory (PNNL) in Richland, Washington, conducted initial studies to evaluate the effectiveness of nondestructive examinations (NDE) coupled with mechanical testing for assessing butt fusion joint integrity in high density polyethylene (HDPE) pipe. The work provided insightful information to the United States Nuclear Regulatory Commission (NRC) on the effectiveness of volumetric inspection techniques for detecting lack of fusion (LOF) conditions in the fusion joints. HDPE has been installed on a limited basis in American Society of Mechanical Engineers (ASME) Class 3, buried piping systems at several operating U.S. nuclear power plants and has been proposed for use in new construction. A comparison was made between the results from ultrasonic and microwave nondestructive examinations and the results from mechanical destructive evaluations, specifically the high-speed tensile test and the side-bend test, for determining joint integrity. The data comparison revealed that none of the NDE techniques detected all of the lack-of-fusion conditions that were revealed by the destructive tests. Follow-on work has recently been initiated at PNNL to accurately characterize the NDE responses from machined flaws of varying size and location in PE 4710 materials as well as the LOF condition. This effort is directed at quantifying the ability of volumetric NDE techniques to detect flaws in relation to the critical flaw size associated with joint integrity. A status of these latest investigations is presented.

  8. Femtosecond spectroscopy probes the folding quality of antibody fragments expressed as GFP fusions in the cytoplasm

    SciTech Connect (OSTI)

    Didier, P. [Faculte de Pharmacie, UMR 7175, 74, route du Rhin, 67412 Illkirch (France); Weiss, E.; Sibler, A.-P. [Ecole Superieure de Biotechnologie de Strasbourg, UMR 7175, Boulevard Sebastien Brant, F-67412 Illkirch (France); Philibert, P.; Martineau, P. [Centre de recherche en cancerologie de Montpellier, UMR 5160, Val d'Aurelle-Paul Lamarque, 34298 Montpellier cedex 5 (France); Bigot, J.-Y. [Institut de Physique et Chimie des Materiaux de Strasbourg, UMR 7504, 23, rue du Loess, F-67037 Strasbourg (France); Guidoni, L. [Institut de Physique et Chimie des Materiaux de Strasbourg, UMR 7504, 23, rue du Loess, F-67037 Strasbourg (France); Laboratoire Materiaux et Phenomenes Quantiques, UMR 7162, Batiment Condorcet, 10 rue Alice Domon et Leonie Duquet, 75205 Paris cedex 13 (France)], E-mail: luca.guidoni@univ-paris-diderot.fr

    2008-02-22

    Time-resolved femtosecond spectroscopy can improve the application of green fluorescent proteins (GFPs) as protein-folding reporters. The study of ultrafast excited-state dynamics (ESD) of GFP fused to single chain variable fragment (scFv) antibody fragments, allowed us to define and measure an empirical parameter that only depends on the folding quality (FQ) of the fusion. This method has been applied to the analysis of genetic fusions expressed in the bacterial cytoplasm and allowed us to distinguish folded and thus functional antibody fragments (high FQ) with respect to misfolded antibody fragments. Moreover, these findings were strongly correlated to the behavior of the same scFvs expressed in animal cells. This method is based on the sensitivity of the ESD to the modifications in the tertiary structure of the GFP induced by the aggregation state of the fusion partner. This approach may be applicable to the study of the FQ of polypeptides over-expressed under reducing conditions.

  9. DOE Handbook: Supplementary guidance and design experience for the fusion safety standards DOE-STD-6002-96 and DOE-STD-6003-96

    SciTech Connect (OSTI)

    1999-01-01

    Two standards have been developed that pertain to the safety of fusion facilities. These are DOE- STD-6002-96, Safety of Magnetic Fusion Facilities: Requirements, and DOE-STD-6003-96, Safety of Magnetic Fusion Facilities: Guidance. The first of these standards identifies requirements that subscribers to that standard must meet to achieve safety in fusion facilities. The second standard contains guidance to assist in meeting the requirements identified in the first This handbook provides additional documentation on good operations and design practices as well as lessons learned from the experiences of designers and operators of previous fusion facilities and related systems. It is intended to capture the experience gained in the various fields and pass it on to designers of future fusion facilities as a means of enhancing success and safety. The sections of this document are presented according to the physical location of the major systems of a fusion facility, beginning with the vacuum vessel and proceeding to those systems and components outside the vacuum vessel (the "Ex-vessel Systems"). The last section describes administrative procedures that cannot be localized to specific components. It has been tacitly assumed that the general structure of the fusion facilities addressed is that of a tokamak though the same principles would apply to other magnetic confinement options.

  10. HYPERFUSE: a hypervelocity inertial confinement system for fusion energy production and fission waste transmutation

    SciTech Connect (OSTI)

    Makowitz, H.; Powell, J.R.; Wiswall, R.

    1980-01-01

    Parametric system studies of an inertial confinement fusion (ICF) reactor system to transmute fission products from a LWR economy have been carried out. The ICF reactors would produce net power in addition to transmuting fission products. The particular ICF concept examined is an impact fusion approach termed HYPERFUSE, in which hypervelocity pellets, traveling on the order of 100 to 300 km/sec, collide with each other or a target block in a reactor chamber and initiate a thermonuclear reaction. The DT fusion fuel is contained in a shell of the material to be transmuted, e.g., /sup 137/Cs, /sup 90/Sr, /sup 129/I, /sup 99/Tc, etc. The 14-MeV fusion neutrons released during the pellet burn cause transmutation reactions (e.g., (n,2n), (n,..cap alpha..), (n,..gamma..), etc.) that convert the long-lived fission products (FP's) either to stable products or to species that decay with a short half-life to a stable product. The transmutation parametric studies conclude that the design of the hypervelocity projectiles should emphasize the achievement of high densities in the transmutation regions (greater than the DT fusion fuel density), as well as the DT ignition and burn criterion (rho R = 1.0 to 3.0) requirements. These studies also indicate that masses on the order of 1.0 g at densities of rho greater than or equal to 500.0 g/cm/sup 3/ are required for a practical fusion-based fission product transmutation system.

  11. Questions and answers about ITER and fusion energy

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    QA & What is fusion? Fusion, the energy source of the sun and stars, is the most efficient process for converting mass into energy (E = mc 2 ). The fusion process is environmentally benign and does not emit gases that contribute to global warming or acid rain. Abundant fuel supplies for fusion are available that could meet the needs of the world's population for more than 10,000 years if the fusion process is harnessed successfully. When will fusion successfully produce useable energy? The

  12. DOE and Fusion Links | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    DOE and Fusion Links United States Department of Energy U.S. Department of Energy Office of Science Office of Fusion Energy Sciences U.S. D.O.E. Princeton Site Office Map showing U.S. Fusion Program Participants U.S. D.O.E. Science Laboratories U.S. D.O.E. User Facilities U.S. D.O.E. Funding Opportunities Other Fusion Research Sites United States Sites General Atomics (GA) MIT Plasma Science and Fusion Center U.S. ITER National Ignition Facility (NIF) American Fusion News International Sites

  13. OMEGA Power Conditioning - Laboratory for Laser Energetics

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Power Conditioning - Laboratory for Laser Energetics Laboratory for Laser Energetics Logo Search Home Around the Lab Past Issues Past Quick Shots About Office of the Director Map to LLE LLE Tours LLE Building Map Partnerships Careers Education Undergraduate Program Graduate Program High School Program Faculty Contacts Computational Astrophysics H-E-D Physics Inertial Confinement Fusion Laser-Plasma Interaction Radiative Hydrodynamics Plasma Astrophysics Organization Director's Office Laser

  14. Palladium metallurgy and cold fusion; Some remarks

    SciTech Connect (OSTI)

    Murr, L.E. )

    1990-04-01

    In this paper the recent confusion surrounding claims for the observation of cold fusion involving palladium electrodes in electrochemical cells containing deuterium might be clarified to some extent if the palladium metallurgy, particularly in the context of fundamental microstructures, are accurately defined. Both the palladium/hydrogen and palladium/deuterium systems have been extensively investigated, and it is asserted more than two decades ago that the palladium/hydrogen system was perhaps the most extensively, experimentally investigated metal/gas system. Ordinary hydrogen absorbed in palladium fused to form helium, while in the 1940's Wilner actually observed the fusion reaction at the center of the current cold fusion controversy: d + d {yields} {sup 3}He + n (where d = {sup 2}H represents a deuteron, and n is a neutron). In the experiment by Wilner, a deuterium-saturated palladium sheet was bombarded with accelerated deuterons. The product neutrons (n) were slowed by paraffin wax and detected by the activation of silver.

  15. First wall for polarized fusion reactors

    DOE Patents [OSTI]

    Greenside, H.S.; Budny, R.V.; Post, D.E. Jr.

    1985-01-29

    A first-wall or first-wall coating for use in a fusion reactor having polarized fuel may be formed of a low-Z non-metallic material having slow spin relaxation, i.e., a depolarization rate greater than 1 sec/sup -1/. Materials having these properties include hydrogenated and deuterated amorphous semiconductors. A method for preventing the rapid depolarization of a polarized plasma in a fusion device may comprise the step of providing a first-wall or first-wall coating formed of a low-Z, non-metallic material having a depolarization rate greater than 1 sec/sup -1/.

  16. Driven reconnection in magnetic fusion experiments

    SciTech Connect (OSTI)

    Fitzpatrick, R.

    1995-11-01

    Error fields (i.e. small non-axisymmetric perturbations of the magnetic field due to coil misalignments, etc.) are a fact of life in magnetic fusion experiments. What effects do error fields have on plasma confinement? How can any detrimental effects be alleviated? These, and other, questions are explored in detail in this lecture using simple resistive magnetohydrodynamic (resistance MHD) arguments. Although the lecture concentrates on one particular type of magnetic fusion device, namely, the tokamak, the analysis is fairly general and could also be used to examine the effects of error fields on other types of device (e.g. Reversed Field Pinches, Stellerators, etc.).

  17. Magnetized liner inertial fusion (MagLIF)

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Magnetized liner inertial fusion (MagLIF) [1] is an inertial confinement fusion (ICF) scheme using cylindrical compression of magnetized, preheated DT gas. A 10 - 30 T axial magnetic field reduces electron thermal conductivity allowing near-adiabatic compression at implosion velocities of order 100 km/s, much lower than the 300 km/s or more required for conventional ICF. Preheating to at least 100 eV ensures that keV temperatures are reached with a convergence ratio no greater than 30. The

  18. NERSC Announces Second Annual HPC Achievement Awards

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    NERSC Announces Second Annual HPC Achievement Awards NERSC Announces Second Annual HPC Achievement Awards February 4, 2014 Jon Bashor, jbashor@lbl.gov, +1 510 486 5849 XBD201402-00246.jpg Ted Kisner (International Planck Collaboration), Jean-Luc Vay and Anubhav Jain accept their NERSC Achievement awards. The Department of Energy's National Energy Research Scientific Computing Center (NERSC) announced the winners of its second annual High Performance Computing (HPC) Achievement Awards on Feb. 4,

  19. Achieving Total Employee Engagement in Energy Efficiency

    Broader source: Energy.gov [DOE]

    Ratheon and GM share their experiences with employee engagement to achieve energy efficiency and sustainability goals in this presentation.

  20. Secretary's Achievement Award | Department of Energy

    Office of Environmental Management (EM)

    icon Office of Environmental Management Idaho Nuclear facility Decontamination & Decommissioning Project.pdf More Documents & Publications Secretary's Achievment Award...

  1. Current Status and Recent Research Achievements in SiC/SiC Composites

    SciTech Connect (OSTI)

    Katoh, Yutai; Snead, Lance L.; Henager, Charles H.; Nozawa, T.; Hinoki, Tetsuya; Ivekovic, Aljaz; Novak, Sasa; Gonzalez de Vicente, Sehila M.

    2014-12-01

    The development and maturation of the silicon carbide fiber-reinforced silicon carbide matrix (SiC/SiC) composite system for fusion applications has seen the evolution from fundamental development and understanding of the material system and its behavior in a hostile irradiation environment to the current effort which essentially is a broad-based program of technology, directed at moving this material class from a laboratory curiosity to an engineering material. This paper lays out the recent international scientific and technological achievements in the development of SiC/SiC composite material technologies for fusion application and will discuss future research directions. It also reviews the materials system in the larger context of progress to maturity as an engineering material for both the larger nuclear community and for general engineering applications.

  2. Achievement Award Certificate Templates | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Publications, Exhibits, & Logos » Templates » Achievement Award Certificate Templates Achievement Award Certificate Templates The Office of Energy Efficiency and Renewable Energy (EERE) has designed basic templates for awarding certificates of achievement. The templates are Microsoft Word files, and all fields are editable. Illustration of the blue certificate template Blue Certificate Template Illustration of the blue certificate template Green Certificate Template Communication Standards

  3. Advanced fission and fossil plant economics-implications for fusion

    SciTech Connect (OSTI)

    Delene, J.G.

    1994-09-01

    In order for fusion energy to be a viable option for electric power generation, it must either directly compete with future alternatives or serve as a reasonable backup if the alternatives become unacceptable. This paper discusses projected costs for the most likely competitors with fusion power for baseload electric capacity and what these costs imply for fusion economics. The competitors examined include advanced nuclear fission and advanced fossil-fired plants. The projected costs and their basis are discussed. The estimates for these technologies are compared with cost estimates for magnetic and inertial confinement fusion plants. The conclusion of the analysis is that fusion faces formidable economic competition. Although the cost level for fusion appears greater than that for fission or fossil, the costs are not so high as to preclude fusion`s potential competitiveness.

  4. Advanced fission and fossil plant economics-implications for fusion

    SciTech Connect (OSTI)

    Delene, J.G.

    1994-11-01

    In order for fusion energy to be a viable option for electric power generation, it must either directly compete with future alternatives or serve as a reasonable backup if the alternatives become unacceptable. This paper discusses projected costs for the most likely competitors with fusion power for base-load electric capacity and what these costs imply for fusion economics. The competitors examined include advanced nuclear fission and advanced fossil-fired plants. The projected costs and their basis are discussed. The estimates for these technologies are compared with cost estimates for magnetic and inertial confinement fusion plants. The conclusion of the analysis is that fusion faces formidable economic competition. Although the cost level for fusion appears greater than that for fission or fossil, the costs are not so high as to preclude fusion`s potential competitiveness.

  5. N-Terminal T4 Lysozyme Fusion Facilitates Crystallization of...

    Office of Scientific and Technical Information (OSTI)

    N-Terminal T4 Lysozyme Fusion Facilitates Crystallization of a G Protein Coupled Receptor Citation Details In-Document Search Title: N-Terminal T4 Lysozyme Fusion Facilitates...

  6. Fusion diagnostic developed at PPPL sheds light on plasma behavior...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Fusion diagnostic developed at PPPL sheds light on plasma behavior at EAST By Kitta ... (PPPL) has enabled a research team at a fusion energy experiment in China to observe--in ...

  7. PPPL engineer named winner of the 2013 Fusion Technology Award...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    engineer named winner of the 2013 Fusion Technology Award By John Greenwald May 1, 2013 ... advice is sought by engineers around the world, has won the 2013 Fusion Technology Award. ...

  8. COLLOQUIUM: Progress towards fusion on NIF and Z requires new...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    towards fusion on NIF and Z requires new plasma measurement capabilities Dr. Joe Kilkenny LLNLGA Dr. Greg Rochau SNL There is significant progress towards fusion on NIF and Z ...

  9. Accelerator Fusion Research Division 1991 summary of activities

    SciTech Connect (OSTI)

    Berkner, Klaus H.

    1991-12-01

    This report discusses research projects in the following areas: Heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; superconducting magnets; and bevalac operations.

  10. Accelerator & Fusion Research Division 1991 summary of activities

    SciTech Connect (OSTI)

    Not Available

    1991-12-01

    This report discusses research projects in the following areas: Heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; superconducting magnets; and bevalac operations.

  11. MIT's Plasma Science Fusion Center: Tokamak Experiments Come Clean about

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Impurity Transport | Princeton Plasma Physics Lab Tokamak Experiments Come Clean about Impurity Transport American Fusion News Category: Massachusetts Institute of Technology (MIT) Link: MIT's Plasma Science Fusion Center: Tokamak Experiments Come Clean about Impurity Transport

  12. Energetic Particle Physics In Fusion Research In Preparation For Burning Plasma Experiments

    SciTech Connect (OSTI)

    Gorelenkov, Nikolai N

    2013-06-01

    The area of energetic particle (EP) physics of fusion research has been actively and extensively researched in recent decades. The progress achieved in advancing and understanding EP physics has been substantial since the last comprehensive review on this topic by W.W. Heidbrink and G.J. Sadler [1]. That review coincided with the start of deuterium-tritium (DT) experiments on Tokamak Fusion Test reactor (TFTR) and full scale fusion alphas physics studies. Fusion research in recent years has been influenced by EP physics in many ways including the limitations imposed by the "sea" of Alfven eigenmodes (AE) in particular by the toroidicityinduced AEs (TAE) modes and reversed shear Alfven (RSAE). In present paper we attempt a broad review of EP physics progress in tokamaks and spherical tori since the first DT experiments on TFTR and JET (Joint European Torus) including helical/stellarator devices. Introductory discussions on basic ingredients of EP physics, i.e. particle orbits in STs, fundamental diagnostic techniques of EPs and instabilities, wave particle resonances and others are given to help understanding the advanced topics of EP physics. At the end we cover important and interesting physics issues toward the burning plasma experiments such as ITER (International Thermonuclear Experimental Reactor).

  13. Using Radio Waves to Control Fusion Plasma Density

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Using Radio Waves to Control Fusion Plasma Density Using Radio Waves to Control Fusion Plasma Density Simulations Run at NERSC Support Fusion Experiments at MIT, General Atomics October 29, 2014 Radiowavesplasma Supercomputer simulation shows turbulent density fluctuations in the core of the Alcator C-Mod tokamak during strong electron heating. Image: Darin Ernst, MIT Recent fusion experiments on the DIII-D tokamak at General Atomics and the Alcator C-Mod tokamak at Massachusetts Institute of

  14. Diagnosing magnetized liner inertial fusion experiments on Z (Journal

    Office of Scientific and Technical Information (OSTI)

    Article) | DOE PAGES Diagnosing magnetized liner inertial fusion experiments on Z This content will become publicly available on May 14, 2016 « Prev Next » Title: Diagnosing magnetized liner inertial fusion experiments on Z The Magnetized Liner Inertial Fusion experiments performed at Sandia's Z facility have demonstrated significant thermonuclear fusion neutron yields (~1012 DD neutrons) from multi-keV deuterium plasmasinertially confined by slow (~10 cm/μs), stable, cylindrical

  15. Effects of magnetization on fusion product trapping and secondary neutron

    Office of Scientific and Technical Information (OSTI)

    spectra (Journal Article) | DOE PAGES Effects of magnetization on fusion product trapping and secondary neutron spectra This content will become publicly available on May 14, 2016 « Prev Next » Title: Effects of magnetization on fusion product trapping and secondary neutron spectra In magnetizing the fusion fuel in inertial confinement fusion (ICF) systems, we found that the required stagnation pressure and density can be relaxed dramatically. This happens because the magnetic field

  16. Fusion Machines of the World | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Fusion Machines of the World NSTX-U IS ONE OF AN ELITE GROUP of magnetic fusion facilities scattered across the globe. These powerful and complex machines are advancing mankind's quest to harness fusion as a safe, clean and abundant source of energy for producing electricity. Here is a selection of major facilities. Publication File: PDF icon NSTX-U_presskit_print_FusionMachines-World

  17. MIT Plasma Science & Fusion Center: research

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Research Program Information Publications & News Meetings & Seminars Contact Information Physics Research Fusion Technology & Engineering Plasma Technology Waves & Beams Useful...

  18. Dynamic microscopic theory of fusion using DC-TDHF

    SciTech Connect (OSTI)

    Umar, A. S.; Oberacker, V. E.; Keser, R.; Maruhn, J. A.; Reinhard, P.-G.

    2012-10-20

    The density-constrained time-dependent Hartree-Fock (DC-TDHF) theory is a fully microscopic approach for calculating heavy-ion interaction potentials and fusion cross sections below and above the fusion barrier. We discuss recent applications of DC-TDHF method to fusion of light and heavy systems.

  19. Accelerator and Fusion Research Division 1989 summary of activities

    SciTech Connect (OSTI)

    Not Available

    1990-06-01

    This report discusses the research being conducted at Lawrence Berkeley Laboratory's Accelerator and Fusion Research Division. The main topics covered are: heavy-ion fusion accelerator research; magnetic fusion energy; advanced light source; center for x-ray optics; exploratory studies; high-energy physics technology; and bevalac operations.

  20. Safeguard Requirements for Fusion Power Plants

    SciTech Connect (OSTI)

    Robert J. Goldston and Alexander Glaser

    2012-08-10

    Nuclear proliferation risks from magnetic fusion energy associated with access to fissile materials can be divided into three main categories: 1) clandestine production of fissile material in an undeclared facility, 2) covert production and diversion of such material in a declared and safeguarded facility, and 3) use of a declared facility in a breakout scenario, in which a state openly produces fissile material in violation of international agreements. The degree of risk in each of these categories is assessed, taking into account both state and non-state actors, and it is found that safeguards are required for fusion energy to be highly attractive from a non-proliferation standpoint. Specific safeguard requirements and R&D needs are outlined for each category of risk, and the technical capability of the ITER experiment, under construction, to contribute to this R&D is noted. A preliminary analysis indicates a potential legal pathway for fusion power systems to be brought under the Treaty for the Non-Proliferation of Nuclear Weapons. "Vertical" proliferation risks associated with tritium and with the knowledge that can be gained from inertial fusion energy R&D are outlined.

  1. Fusion Simulation Program Definition. Final report

    SciTech Connect (OSTI)

    Cary, John R.

    2012-09-05

    We have completed our contributions to the Fusion Simulation Program Definition Project. Our contributions were in the overall planning with concentration in the definition of the area of Software Integration and Support. We contributed to the planning of multiple meetings, and we contributed to multiple planning documents.

  2. Inertial Confinement Fusion | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Inertial Confinement Fusion | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs Our Jobs

  3. Portuguese research program on nuclear fusion

    SciTech Connect (OSTI)

    Varandas, C.A.F.; Cabral, J.A.C.; Manso, M.E.

    1994-12-01

    The Portuguese research program on nuclear fusion is presented. The experimental activity associated with the tokamak ISTTOK as well as the work carried out in the frame of international collaboration are summarized. The main technological features of ISTTOK are described along with studies on microwave reflectometry. Future plans are briefly described.

  4. Accelerator-based fusion with a low temperature target

    SciTech Connect (OSTI)

    Phillips, R. E.; Ordonez, C. A.

    2013-04-19

    Neutron generators are in use in a number of scientific and commercial endeavors. They function by triggering fusion reactions between accelerated ions (usually deuterons) and a stationary cold target (e.g., containing tritium). This setup has the potential to generate energy. It has been shown that if the energy transfer between injected ions and target electrons is sufficiently small, net energy gain can be achieved. Three possible avenues are: (a) a hot target with high electron temperature, (b) a cold non-neutral target with an electron deficiency, or (c) a cold target with a high Fermi energy. A study of the third possibility is reported in light of recent research that points to a new phase of hydrogen, which is hypothesized to be related to metallic hydrogen. As such, the target is considered to be composed of nuclei and delocalized electrons. The electrons are treated as conduction electrons, with the average minimum excitation energy being approximately equal to 40% of the Fermi energy. The Fermi energy is directly related to the electron density. Preliminary results indicate that if the claimed electron densities in the new phase of hydrogen were achieved in a target, the energy transfer to electrons would be small enough to allow net energy gain.

  5. Method and apparatus for making uniform pellets for fusion reactors

    DOE Patents [OSTI]

    Budrick, Ronald G.; King, Frank T.; Martin, Alfred J.; Nolen, Jr., Robert L.; Solomon, David E.

    1977-01-01

    A method and apparatus for making uniform pellets for laser driven fusion reactors which comprises selection of a quantity of glass frit which has been accurately classified as to size within a few micrometers and contains an occluded material, such as urea, which gasifies and expands when heated. The sized particles are introduced into an apparatus which includes a heated vertical tube with temperatures ranging from 800.degree. C to 1300.degree. C. The particles are heated during the drop through the tube to molten condition wherein the occluded material gasifies to form hollow microspheres which stabilize in shape and plunge into a collecting liquid at the bottom of the tube. The apparatus includes the vertical heat resistant tube, heaters for the various zones of the tube and means for introducing the frit and collecting the formed microspheres.

  6. Deuterium concentration and cold fusion; Rate distributions in palladium

    SciTech Connect (OSTI)

    Rogers, V.C.; Sandquist, G.M.; Nielson, K.K. )

    1989-12-01

    Cold fusion reactions and excess heat production have been reported in the electrolysis of heavy water with a palladium metal cathode. Solution of the standard diffusion equation for deuterium without fusion indicates that the deuterium concentration distribution rapidly becomes constant in the palladium lattice. Solution of the nonlinear diffusion equation for deuterium undergoing fusion also gives constant deuterium concentrations, suggesting that any fusion occurs uniformly throughout the palladium lattice. The hypothesis that fusion reactions occur predominantly at the palladium surface is shown to be inconsistent with experimental data.

  7. Secretary's Achievement Award (IBL) | Department of Energy

    Energy Savers [EERE]

    IBL) Secretary's Achievement Award (IBL) Secretary’s Achievement Award (IBL) Presented to: The National Nuclear Security Administration Ion Beam Laboratory Project The Ion Beam Laboratory project team is recognized for delivering this state-of-the-art facility six months ahead of schedule and nearly $6 million dollars under budget. This was accomplished while achieving LEED Gold certification. Through the exceptionally close working relationships between all project stakeholders, the

  8. River Corridor Achievements | Department of Energy

    Energy Savers [EERE]

    Achievements River Corridor Achievements December 17, 2015 - 12:15pm Addthis Overall-RC-achievements_2015nw_756px - Copy.jpg Washington Closure Hanford and previous contractors have completed much of the cleanup work in the River Corridor, shown here. Addthis Related Articles EM Update Newsletter Spotlights River Corridor Cleanup at Hanford Site Washington Closure Hanford: Ten Years of River Corridor Cleanup The inset photo shows Hanford's 300 Area in 1982 in comparison to the area today, shown

  9. Preliminary design of a fusion reactor fuel cleanup system by the palladium-alloy membrane method

    SciTech Connect (OSTI)

    Yoshida, H.; Konishi, S.; Naruse, Y.

    1983-05-01

    A design for a palladium diffuser and fuel cleanup system for a deuterium-tritium fusion reactor is proposed. The feasibility of the palladium-alloy membrane method is discussed based on early studies by the authors. Operating conditions of the palladium diffuser are determined experimentally. Dimensions of the diffuser are estimated from computer simulation. A fuel cleanup system is designed under the feed conditions of the Tritium Systems Test Assembly at Los Alamos National Laboratory. The system is composed of palladium diffusers, catalytic oxidizer, freezer, and zinc beds and has some advantages in system layout and operation. This design can readily be extended to other conditions of plasma exhaust gases.

  10. Time-resolved compression of a capsule with a cone to high density for fast-ignition laser fusion

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Theobald, W.; Solodov, A. A.; Stoeckl, C.; Anderson, K. S.; Beg, F. N.; Epstein, R.; Fiksel, G.; Giraldez, E. M.; Glebov, V. Yu.; Habara, H.; et al

    2014-12-12

    The advent of high-intensity lasers enables us to recreate and study the behaviour of matter under the extreme densities and pressures that exist in many astrophysical objects. It may also enable us to develop a power source based on laser-driven nuclear fusion. Achieving such conditions usually requires a target that is highly uniform and spherically symmetric. Here we show that it is possible to generate high densities in a so-called fast-ignition target that consists of a thin shell whose spherical symmetry is interrupted by the inclusion of a metal cone. Using picosecond-time-resolved X-ray radiography, we show that we can achievemore » areal densities in excess of 300 mg cm#2;-2 with a nanosecond-duration compression pulse -- the highest areal density ever reported for a cone-in-shell target. Such densities are high enough to stop MeV electrons, which is necessary for igniting the fuel with a subsequent picosecond pulse focused into the resulting plasma.« less

  11. PNNL: About PNNL - Achievements and Awards

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    for PNNL. PNNL Achievements Since its creation in 1965, PNNL has produced dozens of major innovations and advances in the areas of the environment, energy, health, national...

  12. Keeping Impact As Low As Reasonably Achievable

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Long-Term Environmental Stewardship and Sustainability Strategy is to keep the impact of past, present, and future operations as low as reasonably achievable. Examples of the...

  13. Training Reciprocity Achieves Greater Consistency, Saves Time...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... in reciprocity efforts. Addthis Related Articles Training Reciprocity Achieves Greater ... near the Hanford Site. More Than 200 DOE Safety and Health Trainers Gather for Exchange

  14. NETL Scientist Earns Prestigious Technical Achievement Award

    Broader source: Energy.gov [DOE]

    NETL's Dr. Ziomek-Moroz received a 2013 Technical Achievement Award from NACE International, the Corrosion Society,in recognition of her work in corrosion science.

  15. Achieving Water-Sustainable Bioenergy Production | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Production Breakout Session 3-A: Growing a Water-Smart Bioeconomy Achieving Water-Sustainable Bioenergy Production May Wu, Principal Environmental System Analyst in the...

  16. Lab scientists recognized for their achievements

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Lab scientists recognized for their achievements Influential scientific minds, F. Albert Cotton and Ernest O. Lawrence Awards September 2, 2014 Left to right: Bette Korber,...

  17. Secretary's Achievement Award | Department of Energy

    Energy Savers [EERE]

    Science Daya Bay reactor Neutrino Detector Project.pdf More Documents & Publications 2012 Awards for Project Management PM Workshop 2012 Awards Recognition - Secretary's Awards Secretary's Achievement Award

  18. Savannah River Analytical Laboratories Achieve International...

    National Nuclear Security Administration (NNSA)

    Stockpile Stewardship Program Celebrated As One of Nation's Greatest Achievements in Science and Security NNSA Removes U.S.-Origin HEU from Jamaica, Makes the Caribbean HEU Free...

  19. Early Career. Harnessing nanotechnology for fusion plasma-material interface research in an in-situ particle-surface interaction facility

    SciTech Connect (OSTI)

    Allain, Jean Paul

    2014-08-08

    This project consisted of fundamental and applied research of advanced in-situ particle-beam interactions with surfaces/interfaces to discover novel materials able to tolerate intense conditions at the plasma-material interface (PMI) in future fusion burning plasma devices. The project established a novel facility that is capable of not only characterizing new fusion nanomaterials but, more importantly probing and manipulating materials at the nanoscale while performing subsequent single-effect in-situ testing of their performance under simulated environments in fusion PMI.

  20. Some thoughts on a simple mechanism for the [sup 2]H + [sup 2]H [yields] [sup 4]He cold fusion reaction

    SciTech Connect (OSTI)

    Park, A.E.

    1993-11-01

    A speculative mechanism for the creation of [sup 4]He using cold fusion is proposed. The nuclear transformation can be made by the fusion of two excited rotating ground states of deuterium into a highly excited rotating ground state of [sup 4]He. Under compression and relatively stable conditions, the formation of such a bound, stretched-out pnnp state of [sup 4]He would be favored (with respect to Coulomb repulsion) over other nuclear ground states without as much angular momentum. The reaction likely occurs at the surface of palladium. A more descriptive name for this reaction is compressed-rotational-shielded (CRS) fusion. Potential experimental conditions for enhancing the initiation of CRS fusion are discussed. 8 refs., 2 figs.

  1. Upside-Down Solar Cell Achieves Record Efficiencies (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2010-12-01

    The inverted metamorphic multijunction (IMM) solar cell is an exercise in efficient innovation - literally, as the technology boasted the highest demonstrated efficiency for converting sunlight into electrical energy at its debut in 2005. Scientists at the National Renewable Energy Laboratory (NREL) inverted the conventional photovoltaic (PV) structure to revolutionary effect, achieving solar conversion efficiencies of 33.8% and 40.8% under one-sun and concentrated conditions, respectively.

  2. Magneto-inertial Fusion: An Emerging Concept for Inertial Fusion and Dense Plasmas in Ultrahigh Magnetic Fields

    SciTech Connect (OSTI)

    Thio, Francis Y.C.

    2008-01-01

    An overview of the U.S. program in magneto-inertial fusion (MIF) is given in terms of its technical rationale, scientific goals, vision, research plans, needs, and the research facilities currently available in support of the program. Magneto-inertial fusion is an emerging concept for inertial fusion and a pathway to the study of dense plasmas in ultrahigh magnetic fields (magnetic fields in excess of 500 T). The presence of magnetic field in an inertial fusion target suppresses cross-field thermal transport and potentially could enable more attractive inertial fusion energy systems. A vigorous program in magnetized high energy density laboratory plasmas (HED-LP) addressing the scientific basis of magneto-inertial fusion has been initiated by the Office of Fusion Energy Sciences of the U.S. Department of Energy involving a number of universities, government laboratories and private institutions.

  3. Design and characterization of a neutralized-transport experiment for heavy-ion fusion

    SciTech Connect (OSTI)

    Henestroza, E.; Eylon, S.; Roy, P.K.; Yu, S.S.; Anders, A.; Bieniosek, F.M.; Greenway, W.G.; Logan, B.G.; MacGill, R.A.; Shuman, D.B.; Vanecek, D.L.; Waldron, W.L.; Sharp, W.M.; Houck, T.L.; Davidson, R.C.; Efthimion, P.C.; Gilson, E.P.; Sefkow, A.B.; Welch, D.R.; Rose, D.V.; Olson, C.L.

    2004-03-14

    In heavy-ion inertial-confinement fusion systems, intense beams of ions must be transported from the exit of the final focus magnet system through the fusion chamber to hit millimeter-sized spots on the target. Effective plasma neutralization of intense ion beams in this final transport is essential for a heavy-ion fusion power plant to be economically competitive. The physics of neutralized drift has been studied extensively with particle-in-cell simulations. To provide quantitative comparisons of theoretical predictions with experiment, the Virtual National Laboratory for Heavy Ion Fusion has completed the construction and has begun experimentation with the Neutralized Transport Experiment (NTX). The experiment consists of three main sections, each with its own physics issues. The injector is designed to generate a very high-brightness, space-charge-dominated potassium beam while still allowing variable perveance by a beam aperturing technique. The magnetic-focusing section, consisting of four pulsed magnetic quadrupoles, permits the study of beam tuning, as well as the effects of phase space dilution due to higher-order nonlinear fields. In the final section, the converging ion beam exiting the magnetic section is transported through a drift region with plasma sources for beam neutralization, and the final spot size is measured under various conditions of neutralization. In this paper, we discuss the design and characterization of the three sections in detail and present initial results from the experiment.

  4. The search for solid state fusion lasers

    SciTech Connect (OSTI)

    Weber, M.J. )

    1989-04-01

    Inertial confinement fusion (ICF) research puts severe demands on the laser driver. In recent years large, multibeam Nd:glass lasers have provided a flexible experimental tool for exploring fusion target physics because of their high powers, variable pulse length and shape, wavelength flexibility using harmonic generation, and adjustable that Nd:glass lasers can be scaled up to provide a single-phase, multi-megajoule, high-gain laboratory microfusion facility, and gas-cooled slab amplifiers with laser diode pump sources are viable candidates for an efficient, high repetition rate, megawatt driver for an ICF reactor. In both applications requirements for energy storage and energy extraction drastically limit the choice of lasing media. Nonlinear optical effects and optical damage are additional design constraints. New laser architectures applicable to ICF drivers and possible laser materials, both crystals and glasses, are surveyed. 20 refs., 2 figs.

  5. Multishell inertial-confinement-fusion target

    SciTech Connect (OSTI)

    Holland, J.R.; Del Vecchio, R.M.

    1981-06-01

    This disclosure relates to fusion targets. It deals particularly with the production of multishell inertial confinement fusion targets. The fuel pellet within such targets is designed to compress isentropically under laser or particle irradiation. When a short pulse at extremely high power density strikes the target containing deuterium-tritium fuel, the resulting plasma is confined briefly by its own inertia. Thermonuclear energy can be released in less time than it takes the fuel pellet to blow apart. However, efficient thermonuclear burn requires that the plasma must remain intact at extremely high temperatures and densities for a time sufficient to allow a large fraction of the nuclei to react. Development of multishell targets has been directed at this problem.

  6. First wall for polarized fusion reactors

    DOE Patents [OSTI]

    Greenside, Henry S.; Budny, Robert V.; Post, Jr., Douglass E.

    1988-01-01

    Depolarization mechanisms arising from the recycling of the polarized fuel at the limiter and the first-wall of a fusion reactor are greater than those mechanisms in the plasma. Rapid depolarization of the plasma is prevented by providing a first-wall or first-wall coating formed of a low-Z, non-metallic material having a depolarization rate greater than 1 sec.sup.-1.

  7. AN ACOUSTICALLY DRIVEN MAGNETIZED TARGET FUSION REACTOR

    SciTech Connect (OSTI)

    Laberge, Michel

    2009-07-26

    We propose a new acoustic compression scheme for a MTF power plant. A strong acoustic wave is produced by piston impacts. The wave focuses in liquid PbLi to compress a pre-formed FRC plasma. Simulations indicate the possibility of building an economical 60 MWe power plant. A proof-of-principle experiment produces a small D-D fusion yield of 2000 neutrons per shot.

  8. nuclear fusion | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    fusion | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog Home /

  9. Vacuum fusion bonding of glass plates

    DOE Patents [OSTI]

    Swierkowski, Steve P. (Livermore, CA); Davidson, James C. (Livermore, CA); Balch, Joseph W. (Livermore, CA)

    2001-01-01

    An improved apparatus and method for vacuum fusion bonding of large, patterned glass plates. One or both glass plates are patterned with etched features such as microstructure capillaries and a vacuum pumpout moat, with one plate having at least one hole therethrough for communication with a vacuum pumpout fixture. High accuracy alignment of the plates is accomplished by a temporary clamping fixture until the start of the fusion bonding heat cycle. A complete, void-free fusion bond of seamless, full-strength quality is obtained through the plates; because the glass is heated well into its softening point and because of a large, distributed force that is developed that presses the two plates together from the difference in pressure between the furnace ambient (high pressure) and the channeling and microstructures in the plates (low pressure) due to the vacuum drawn. The apparatus and method may be used to fabricate microcapillary arrays for chemical electrophoresis; for example, any apparatus using a network of microfluidic channels embedded between plates of glass or similar moderate melting point substrates with a gradual softening point curve, or for assembly of glass-based substrates onto larger substrates, such as in flat panel display systems.

  10. Vacuum fusion bonding of glass plates

    DOE Patents [OSTI]

    Swierkowski, Steve P. (Livermore, CA); Davidson, James C. (Livermore, CA); Balch, Joseph W. (Livermore, CA)

    2000-01-01

    An improved apparatus and method for vacuum fusion bonding of large, patterned glass plates. One or both glass plates are patterned with etched features such as microstructure capillaries and a vacuum pumpout moat, with one plate having at least one hole therethrough for communication with a vacuum pumpout fixture. High accuracy alignment of the plates is accomplished by a temporary clamping fixture until the start of the fusion bonding heat cycle. A complete, void-free fusion bond of seamless, full-strength quality is obtained through the plates; because the glass is heated well into its softening point and because of a large, distributed force that is developed that presses the two plates together from the difference in pressure between the furnace ambient (high pressure) and the channeling and microstructures in the plates (low pressure) due to the vacuum drawn. The apparatus and method may be used to fabricate microcapillary arrays for chemical electrophoresis; for example, any apparatus using a network of microfluidic channels embedded between plates of glass or similar moderate melting point substrates with a gradual softening point curve, or for assembly of glass-based substrates onto larger substrates, such as in flat panel display systems.

  11. A Fusion Development Facility on the Critical Path to Fusion Energy

    SciTech Connect (OSTI)

    Chan, V. S.; Stambaugh, R

    2011-01-01

    A fusion development facility (FDF) based on the tokamak approach with normal conducting magnetic field coils is presented. FDF is envisioned as a facility with the dual objective of carrying forward advanced tokamak (AT) physics and enabling the development of fusion energy applications. AT physics enables the design of a compact steady-state machine of moderate gain that can provide the neutron fluence required for FDF's nuclear science development objective. A compact device offers a uniquely viable path for research and development in closing the fusion fuel cycle because of the demand to consume only a moderate quantity of the limited supply of tritium fuel before the technology is in hand for breeding tritium.

  12. A fusion development facility on the critical path to fusion energy

    SciTech Connect (OSTI)

    Chan, Dr. Vincent; Canik, John; Peng, Yueng Kay Martin

    2011-01-01

    A fusion development facility (FDF) based on the tokamak approach with normal conducting magnetic field coils is presented. FDF is envisioned as a facility with the dual objective of carrying forward advanced tokamak (AT) physics and enabling the development of fusion energy applications. AT physics enables the design of a compact steady-state machine of moderate gain that can provide the neutron fluence required for FDF s nuclear science development objective. A compact device offers a uniquely viable path for research and development in closing the fusion fuel cycle because of the demand to consume only a moderate quantity of the limited supply of tritium fuel before the technology is in hand for breeding tritium.

  13. Nucleus-nucleus cold fusion reactions analyzed with the l-dependent 'fusion by diffusion' model

    SciTech Connect (OSTI)

    Cap, T.; Siwek-Wilczynska, K.; Wilczynski, J.

    2011-05-15

    We present a modified version of the Fusion by Diffusion (FBD) model aimed at describing the synthesis of superheavy nuclei in cold fusion reactions, in which a low excited compound nucleus emits only one neutron. The modified FBD model accounts for the angular momentum dependence of three basic factors determining the evaporation residue cross section: the capture cross section {sigma}{sub cap}(l), the fusion probability P{sub fus}(l), and the survival probability P{sub surv}(l). The fusion hindrance factor, the inverse of P{sub fus}(l), is treated in terms of thermal fluctuations in the shape degrees of freedom and is expressed as a solution of the Smoluchowski diffusion equation. The l dependence of P{sub fus}(l) results from the l-dependent potential energy surface of the colliding system. A new parametrization of the distance of starting point of the diffusion process is introduced. An analysis of a complete set of 27 excitation functions for production of superheavy nuclei in cold fusion reactions, studied in experiments at GSI Darmstadt, RIKEN Tokyo, and LBNL Berkeley, is presented. The FBD model satisfactorily reproduces shapes and absolute cross sections of all the cold fusion excitation functions. It is shown that the peak position of the excitation function for a given 1n reaction is determined by the Q value of the reaction and the height of the fission barrier of the final nucleus. This fact could possibly be used in future experiments (with well-defined beam energy) for experimental determination of the fission barrier heights.

  14. Angular momentum effects in fusion-fission and fusion-evaporation reactions

    SciTech Connect (OSTI)

    Plasil, F.

    1980-01-01

    The study of heavy-ion fusion reactions is complicated by the possible contributions of several mechanisms. The various types of heavy-ion-induced fission are discussed. Then compound-nucleus fission is considered with reference to fission barriers deduced from heavy-ion-induced fission. Next, the problems associated with measured values of evaporation-residue cross sections and the angular momentum dependence of incomplete fusion are examined. Finally, the de-excitation of compound nuclei is again taken up, this time with reference to the greatly enhanced ..cap alpha.. emission predicted on the basis of the rotating liquid drop model. 24 figures. (RWR)

  15. Failure modes and effects analysis of fusion magnet systems

    SciTech Connect (OSTI)

    Zimmermann, M; Kazimi, M S; Siu, N O; Thome, R J

    1988-12-01

    A failure modes and consequence analysis of fusion magnet system is an important contributor towards enhancing the design by improving the reliability and reducing the risk associated with the operation of magnet systems. In the first part of this study, a failure mode analysis of a superconducting magnet system is performed. Building on the functional breakdown and the fault tree analysis of the Toroidal Field (TF) coils of the Next European Torus (NET), several subsystem levels are added and an overview of potential sources of failures in a magnet system is provided. The failure analysis is extended to the Poloidal Field (PF) magnet system. Furthermore, an extensive analysis of interactions within the fusion device caused by the operation of the PF magnets is presented in the form of an Interaction Matrix. A number of these interactions may have significant consequences for the TF magnet system particularly interactions triggered by electrical failures in the PF magnet system. In the second part of this study, two basic categories of electrical failures in the PF magnet system are examined: short circuits between the terminals of external PF coils, and faults with a constant voltage applied at external PF coil terminals. An electromagnetic model of the Compact Ignition Tokamak (CIT) is used to examine the mechanical load conditions for the PF and the TF coils resulting from these fault scenarios. It is found that shorts do not pose large threats to the PF coils. Also, the type of plasma disruption has little impact on the net forces on the PF and the TF coils. 39 refs., 30 figs., 12 tabs.

  16. Achieving Water-Sustainable Bioenergy Production

    Broader source: Energy.gov [DOE]

    Breakout Session 3-A: Growing a Water-Smart Bioeconomy Achieving Water-Sustainable Bioenergy ProductionMay Wu, Principal Environmental System Analyst in the Energy Systems Division, Argonne...

  17. Cygnus Achieves Shot 3,000

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Cygnus Achieves Shot 3,000 The newest Tactical Response Force members have more than 50 years military experience. This is a milestone within the national security community. See...

  18. From Earth to Saturn: Los Alamos Achievements

    ScienceCinema (OSTI)

    McMillan, Charlie; Wilson, Cathy; Nekimkem, Howard; Martinez, Johnnie; Martz, Joe; Albright, Brian

    2014-08-13

    A compilation of some of the remarkable achievements of Los Alamos National Laboratory staff over the past 12 months. Originally aired in the June 26, 2008 Director's all-employee meeting.

  19. Achieving Water-Sustainable Bioenergy Production

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    BioEnergy 2015: Opportunities in a Changing Energy Landscape Achieving Water-Sustainable Bioenergy Production May Wu Argonne National Laboratory Session 3-A: Growing a Water-Smart ...

  20. NERSC Intern Wins Award for Computing Achievement

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Intern Wins Award for Computing Achievement NERSC Intern Wins Award for Computing Achievement March 27, 2013 Linda Vu, lvu@lbl.gov, +1 510 495 2402 ncwit1 Stephanie Cabanela, a student intern in the National Energy Research Scientific Computing Center's (NERSC) Operation Technologies Group was honored with the Bay Area Affiliate National Center for Women and Information Technology (NCWIT) Aspirations in Computing award on Saturday, March 16, 2013 in a ceremony in San Jose, CA. The award honors

  1. Our Research Achievements | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Benefits of Research » Our Research Achievements Our Research Achievements April 2, 2013 Coal Combustion Products Coal combustion products (CCPs) are solid materials produced when coal is burned to generate electricity. Since coal provides the largest segment of U.S. electricity generation (45 percent in 2010), finding a sustainable solution for CCPs is an important environmental challenge. April 2, 2013 Coalbed Methane Coalbed methane is natural gas found in coal deposits. It was once

  2. Collaboration drives achievement in protein structure research

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Collaboration drives achievement in protein structure research Alumni Link: Opportunities, News and Resources for Former Employees Latest Issue:September 2015 all issues All Issues » submit Collaboration drives achievement in protein structure research By tracking down how bacterial defense systems work, the scientists can potentially fight infectious diseases and genetic disorders November 1, 2014 Thomas Terwilliger Thomas Terwilliger Contact Linda Anderman Email When a recent print issue of

  3. FEL Achieves 10 Kilowatts | Jefferson Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    FEL Achieves 10 Kilowatts Newport News, Va. - The Free-Electron Laser (FEL), supported by the Office of Naval Research and located at the U.S. Department of Energy's Thomas Jefferson National Accelerator Facility, achieved 10 kilowatts of infrared laser light in late July, making it the most powerful tunable laser in the world. The recently upgraded laser's new capabilities will enhance defense and manufacturing technologies, and support advanced studies of chemistry, physics, biology, and more.

  4. NREL Engineer Gets Lifetime Achievement Award

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Engineer Gets Lifetime Achievement Award For more information contact: e:mail: Public Affairs Golden, Colo., May 20, 1998 — A senior engineer at the U.S. Department of Energy's National Renewable Energy Laboratory (NREL) will receive a major international award for his career-long contributions to the design of energy efficient buildings. Douglas Balcomb has been selected to receive the 1998 Lifetime Achievement Award from the Passive and Low-Energy Architecture (PLEA) network at the group's

  5. Keeping Impact As Low As Reasonably Achievable

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ALARA Keeping Impact As Low As Reasonably Achievable As low as reasonably achievable means making every reasonable effort to maintain exposures to ionizing radiation as far below the dose limits as practical. August 1, 2013 Transuranic waste shipment leaves facility bound for Waste Isolation Pilot Plant (WIPP) Transuranic waste shipment leaves facility bound for Waste Isolation Pilot Plant (WIPP) Radioactive sources are all around us: the sun and the cosmos, medical tests, building materials,

  6. Low Voltage White Phosphorescent OLED Achievements

    Broader source: Energy.gov [DOE]

    Universal Display Corporation (UDC) and its research partners at Princeton University and the University of Southern California have succeeded in developing a white phosphorescent OLED (PHOLED™) that achieved a record efficiency of 20 lumens per watt. This achievement is the result of the team's collaborative efforts to increase the efficiency of PHOLED lighting by focusing on two critical factors: lowering the drive voltages and increasing the amount of light extracted.

  7. Secretary's Achievement Award (RSF) | Department of Energy

    Energy Savers [EERE]

    RSF) Secretary's Achievement Award (RSF) Secretary’s Achievement Award (RSF) Presented to: The Office of Energy Efficiency and Renewable Energy's Research Support Facility (RSF) Project Using a state-of-the-art performance-based design-build acquisition strategy and whole building design approach, the Research Support Facility project team delivered a highly energy efficient and user friendly facility that has received national acclaim. This 222,000 square foot facility was completed ahead

  8. Experimental study of nuclear fusion reactions in muonic molecular systems

    SciTech Connect (OSTI)

    Bogdanova, L. N.

    2013-03-15

    Since the pioneering discovery of the muon catalysis by Alvarez [L. W. Alvarez, K. Brander, F. S. Crawford, et al., Phys. Rev. 105, 1127 (1957)], considerable efforts were aimed at observation of various fusion processes. Results of these studies facilitated understanding the properties of lightest nuclei and dynamics of low-energy fusion reactions. There still remain unsolved theoretical and experimental problems, especially in case of pt fusion.

  9. The Heavy Ion Fusion Science Virtual National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    The Heavy Ion Fusion Science Virtual National Laboratory Python in a Parallel Environment Dave Grote - LLNL & LBNL NUG2013 User Day Wednesday, February 15, 2013 Slide 2 The Heavy Ion Fusion Science Virtual National Laboratory Outline * Why we use Python * How we use Python * Parallel Python with pyMPI * Our graphics model with Pygist * Parallel Python drawbacks and resolutions - Start up time - Static building * Conclusions Slide 3 The Heavy Ion Fusion Science Virtual National Laboratory 3

  10. What Causes Electron Heat Loss in Fusion Plasma?

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Causes Heat Loss in Fusion Plasmas? What Causes Electron Heat Loss in Fusion Plasma? 3D Simulations Run at NERSC Unlock Puzzling Secret September 22, 2015 fusionplasmabelova Contour plots of magnetic-field perturbation for n=4. Creating controlled fusion energy entails many challenges, but one of the most basic is heating plasma-hot gas composed of electrons and charged atoms-to extremely high temperatures and then maintaining those temperatures. Now scientist Elena Belova of the U.S. Department

  11. Plasma Turbulence Simulations Reveal Promising Insight for Fusion Energy |

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Princeton Plasma Physics Lab Plasma Turbulence Simulations Reveal Promising Insight for Fusion Energy By Argonne National Laboratory March 31, 2014 Tweet Widget Google Plus One Share on Facebook Simulation of microturbulence in a tokamak fusion device. (Credit: Chad Jones and Kwan-Liu Ma, University of California, Davis; Stephane Ethier, Princeton Plasma Physics Laboratory) Simulation of microturbulence in a tokamak fusion device. (Credit: Chad Jones and Kwan-Liu Ma, University of

  12. Direct Fusion Drive for a Human Mars Orbital Mission

    SciTech Connect (OSTI)

    Paluszek, Michael; Pajer, Gary; Razin, Yosef; Slonaker, James; Cohen, Samuel; Feder, Russ; Griffin, Kevin; Walsh, Matthew

    2014-08-01

    The Direct Fusion Drive (DFD) is a nuclear fusion engine that produces both thrust and electric power. It employs a field reversed configuration with an odd-parity rotating magnetic field heating system to heat the plasma to fusion temperatures. The engine uses deuterium and helium-3 as fuel and additional deuterium that is heated in the scrape-off layer for thrust augmentation. In this way variable exhaust velocity and thrust is obtained.

  13. AVTA: 2010 Ford Fusion HEV Testing Results | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Ford Fusion HEV Testing Results AVTA: 2010 Ford Fusion HEV Testing Results The Vehicle Technologies Office's Advanced Vehicle Testing Activity carries out testing on a wide range of advanced vehicles and technologies on dynamometers, closed test tracks, and on-the-road. These results provide benchmark data that researchers can use to develop technology models and guide future research and development. The following reports describe results of testing done on a 2010 Ford Fusion hybrid-electric

  14. Physicist Zoe Martin's fusion quest: a stellar future

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Zoe Martin's fusion quest: a stellar future Physicist Zoe Martin's fusion quest: a stellar future From revealing radiation hydrodynamics to creating energy, physics student pursues science's boundaries. August 27, 2013 Zoe Martin's fusion quest: a stellar future From revealing radiation hydrodynamics to creating energy, physics student pursues science's boundaries. She also pursues gravity-defying dance in her spare time. Martin said her mentor, physicist Leslie Sherrill, takes the time to

  15. Chuck Kessel Wins the 2015 Fusion Technology Award | Princeton Plasma

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Physics Lab Chuck Kessel Wins the 2015 Fusion Technology Award By Raphael Rosen July 13, 2015 Tweet Widget Google Plus One Share on Facebook Chuck Kessel, a principal engineer at the U.S. Department of Energy's Princeton Plasma Physics Laboratory (PPPL), has won the 2015 Fusion Technology Award. The honor, from the Institute of Electrical and Electronics Engineers' (IEEE) Nuclear and Plasma Sciences Society, recognizes outstanding contributions to fusion engineering and technology.

  16. Large Scale Production Computing and Storage Requirements for Fusion Energy

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Sciences: Target 2017 Large Scale Production Computing and Storage Requirements for Fusion Energy Sciences: Target 2017 The NERSC Program Requirements Review "Large Scale Production Computing and Storage Requirements for Fusion Energy Sciences" is organized by the Department of Energy's Office of Fusion Energy Sciences (FES), Office of Advanced Scientific Computing Research (ASCR), and the National Energy Research Scientific Computing Center (NERSC). The review's goal is to

  17. Theoretical and experimental studies on the cold nuclear fusion phenomena

    SciTech Connect (OSTI)

    Harith, M.A. . Faculty of Science); Palleschi, V.; Salvetti, A.; Salvetti, G.; Singh, D.P.; Vaselli, M. )

    1990-07-01

    A realistic estimate of the interionic potential that may account for the experimentally observed fusion rates ({approx}10{sup {minus}23} deuterium-deuterium fusion/s) in palladium is presented. Moreover, some preliminary calorimetric studies on the hydrogen absorption process in palladium, performed in a cell with pressure up to 20 bars, are discussed. A detailed analysis of the sensitivity and calibration of the calorimetric system is also presented.

  18. Lab Breakthrough: Neutron Science for the Fusion Mission | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Energy Neutron Science for the Fusion Mission Lab Breakthrough: Neutron Science for the Fusion Mission May 16, 2012 - 9:52am Addthis An accelerator team lead by Robert McGreevy at Oak Ridge National Laboratory is testing material - a critical role in building an experimental fusion reactor for commercial use. As part of the international coalition, they expect to have an operational reactor by 2050. View the entire Lab Breakthrough playlist. Michael Hess Michael Hess Former Digital

  19. Note: Readout of a micromechanical magnetometer for the ITER fusion reactor

    SciTech Connect (OSTI)

    Rimminen, H.; Kyynaeraeinen, J.

    2013-05-15

    We present readout instrumentation for a MEMS magnetometer, placed 30 m away from the MEMS element. This is particularly useful when sensing is performed in high-radiation environment, where the semiconductors in the readout cannot survive. High bandwidth transimpedance amplifiers are used to cancel the cable capacitances of several nanofarads. A frequency doubling readout scheme is used for crosstalk elimination. Signal-to-noise ratio in the range of 60 dB was achieved and with sub-percent nonlinearity. The presented instrument is intended for the steady-state magnetic field measurements in the ITER fusion reactor.

  20. Possible energy gain for a plasma-liner-driven magneto-inertial fusion concept

    SciTech Connect (OSTI)

    Knapp, C. E.; Kirkpatrick, R. C.

    2014-07-15

    A one-dimensional parameter study of a Magneto-Inertial Fusion (MIF) concept indicates that significant gain may be achievable. This concept uses a dynamically formed plasma shell with inwardly directed momentum to drive a magnetized fuel to ignition, which in turn partially burns an intermediate layer of unmagnetized fuel. The concept is referred to as Plasma Jet MIF or PJMIF. The results of an adaptive mesh refinement Eulerian code (Crestone) are compared to those of a Lagrangian code (LASNEX). These are the first published results using the Crestone and LASNEX codes on the PJMIF concept.

  1. Microstructure evolution in the fusion welding of heat-treatable Al-Cu-Li alloys. Ph.D. Thesis

    SciTech Connect (OSTI)

    Hou, K.

    1994-01-01

    Aluminum alloys 2090 and 2195 and Al-2.5Cu were welded autogenously using the gas tungsten-arc (GTA) and CO2 laser beam (LB) welding processes. Relationships between microstructure and mechanical properties in the fusion zone (FZ) and the heat-affected zone (HAZ) in both the as-welded and the postweld heat-treated conditions were studied. Solute segregation due to non-equilibrium solidification in the FZ and its effect on precipitation after postweld aging was quantitatively investigated. After aging treatment, precipitates were found surrounding eutectic regions where higher solute content was measured. Fast cooling LB weld exhibited narrower solute enriched regions and narrower precipitate segregation zones (PSZ`s) adjacent to the eutectic. A partial recovery of strength and hardness in the FZ`s was achieved by postweld aging at 160 C and 190 C for 16 hours. A higher Li/Cu ratio in 2090 promoted the formation of uniformly distributed delta(prime) precipitates in the as-welded HAZ. An evident reduction in the FZ ductility occurred in the 2195 LB welds due to the existence of porosity and shrinkage cavities, and the constraint effect from narrower FZ`s. GTA welds in both 2090 and 2195 alloys exhibited a hardness recovery in the near HAZ, which was not obvious in the LB welds. Postweld aging enhanced this hardness variation. Overaging, dissolution and reprecipitation of various strengthening precipitates occurred in the different regions of the HAZ, and consequently induced the hardness variation. Higher heat inputs increased the HAZ width and enhanced the hardness increase in the near HAZ. Aged HAZ microstructure was affected by the precipitation in the as-welded condition. The formation of Li-containing precipitates in the GTA HAZ, especially alpha(prime) in Li-lean 2195, consumed Li from the matrix. Consequently, the precipitation of T1 was affected.

  2. Two PPPL-led teams win increased supercomputing time to study conditions

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    inside fusion plasmas | Princeton Plasma Physics Lab Two PPPL-led teams win increased supercomputing time to study conditions inside fusion plasmas By John Greenwald January 9, 2014 Tweet Widget Google Plus One Share on Facebook Computer simulation of plasma turbulence carried out in collaboration with PPPL scientists by Kwan-Liu Ma and colleagues in the Department of Computer Science at the University of California-Davis. Computer simulation of plasma turbulence carried out in collaboration

  3. Two PPPL-led teams win increased supercomputing time to study conditions

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    inside fusion plasmas | Princeton Plasma Physics Lab Two PPPL-led teams win increased supercomputing time to study conditions inside fusion plasmas By John Greenwald January 9, 2014 Tweet Widget Google Plus One Share on Facebook Computer simulation of plasma turbulence carried out in collaboration with PPPL scientists by Kwan-Liu Ma and colleagues in the Department of Computer Science at the University of California-Davis. Computer simulation of plasma turbulence carried out in collaboration

  4. Prospects for x-ray polarimetry measurements of magnetic fields in magnetized liner inertial fusion plasmas

    SciTech Connect (OSTI)

    Lynn, Alan G. Gilmore, Mark

    2014-11-15

    Magnetized Liner Inertial Fusion (MagLIF) experiments, where a metal liner is imploded to compress a magnetized seed plasma may generate peak magnetic fields ?10{sup 4} T (100 Megagauss) over small volumes (?10{sup ?10}m{sup 3}) at high plasma densities (?10{sup 28}m{sup ?3}) on 100 ns time scales. Such conditions are extremely challenging to diagnose. We discuss the possibility of, and issues involved in, using polarimetry techniques at x-ray wavelengths to measure magnetic fields under these extreme conditions.

  5. Gyrokinetic simulations of turbulent transport in fusion plasmas

    SciTech Connect (OSTI)

    Rogers, Barrett Neil

    2013-05-30

    This is the final report for a DOE award that was targeted at understanding and simulating turbulence and transport in plasma fusion devices such as tokamaks.

  6. Laser fusion experiment yields record energy at NIF | National...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Laser fusion experiment yields record energy at NIF | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

  7. Apparatus for an Inertial Fusion Reactor Inventor Abraham Massry...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Apparatus for an Inertial Fusion Reactor Inventor Abraham Massry This invention is comprised of a very large vacuum chamber capable of withstanding a very high neutron flux...

  8. PLASMA PHYSICS AND FUSION TECHNOLOGY; GRAPHITE; CREEP; PHYSICAL...

    Office of Scientific and Technical Information (OSTI)

    creep of graphite) Kennedy, C.R. 36 MATERIALS SCIENCE; 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; GRAPHITE; CREEP; PHYSICAL RADIATION EFFECTS; JAPAN; MEETINGS; TRAVEL; ASIA; CARBON;...

  9. MIT Plasma Science & Fusion Center: research>alcator>

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    of harnessing the nuclear process that powers our sun. This stellar process, called fusion, produces minimal waste and offers the hope of an almost limitless supply of safe,...

  10. MIT Plasma Science & Fusion Center: research>alcator>information

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    & Beams Technology & Engineering Francis Bitter Magnet Laboratory Useful Links What is Fusion? The nucleus of an atom consists of protons, which have a positive electrical charge,...

  11. MIT Plasma Science & Fusion Center: research>alcator>research...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Contact Information Physics Research High-Energy- Density Physics Waves & Beams Fusion Technology & Engineering Plasma Technology Useful Links Collaborations at Alcator...

  12. MIT Plasma Science & Fusion Center: research>alcator>introduction

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Contact Information Physics Research High-Energy- Density Physics Waves & Beams Fusion Technology & Engineering Francis Bitter Magnet Laboratoroy Useful Links The links...

  13. Highly Charged Ions in Magnetic Fusion Plasmas: Research Opportunities...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: Highly Charged Ions in Magnetic Fusion Plasmas: Research Opportunities and Diagnostic Necessities Citation Details In-Document Search Title: Highly Charged Ions in...

  14. AND FUSION TECHNOLOGY; MFTF DEVICES; DESIGN; DEUTERIUM; MAGNET...

    Office of Scientific and Technical Information (OSTI)

    MFTF-. cap alpha. + T progress report Nelson, W.D. (ed.) 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; MFTF DEVICES; DESIGN; DEUTERIUM; MAGNET COILS; MAINTENANCE; REACTOR FUELING;...

  15. Observation of incomplete fusion reactions at l < l {sub crit}

    SciTech Connect (OSTI)

    Yadav, Abhishek Sharma, Vijay R. Singh, Devendra P. Unnati,; Singh, B. P.; Prasad, R.; Singh, Pushpendra P.; Bala, Indu; Kumar, R.; Muralithar, S.; Singh, R. P.; Sharma, M. K.

    2014-08-14

    In order to understand the presence of incomplete fusion at low energies i.e. 4-7MeV/nucleon and also to study its dependence on various entrance-channel parameters, the two type of measurements (i) excitation function for {sup 12}C+{sup 159}Tb, and (ii) forward recoil ranges for {sup 12}C+{sup 159}Tb systems have been performed. The experimentally measured excitation functions have been analyzed within the framework of compound nucleus decay using statistical model code PACE4. Analysis of data suggests the production of xn/px)n-channels via complete fusion, as these are found to be well reproduced by PACE4 predictions, while, a significant enhancement in the excitation functions of ?-emitting channels has been observed over the theoretical ones, which has been attributed due to the incomplete fusion processes. Further, the incomplete fusion events observed in case of forward recoil range measurements have been explained on the basis of the breakup fusion model, where these events may be attributed to the fusion of {sup 8}Be and/or {sup 4}He from {sup 12}C projectile to the target nucleus. In the present work, the SUMRULE model calculations are found to highly underestimate the observed incomplete fusion cross-sections which indicate that the l-values lower than l {sub crit} (limit of complete fusion) significantly contribute to the incomplete fusion reactions.

  16. Magnetic Fusion Energy Research: A Summary of Accomplishments

    DOE R&D Accomplishments [OSTI]

    1986-12-01

    Some of the more important contributions of the research program needed to establish the scientific and technical base for fusion power production are discussed. (MOW)

  17. Physicist John Schmidt, designer of cutting-edge fusion facilities...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Energy's Princeton Plasma Physics Laboratory (PPPL) made him a highly respected leader in the worldwide quest for fusion energy, died on February 13 following a brain hemorrhage. ...

  18. Novel Approach to Plasma Facing Materials in Nuclear Fusion Reactors

    SciTech Connect (OSTI)

    Livramento, V.; Correia, J. B.; Shohoji, N.; Osawa, E.; Nunes, D.

    2008-04-07

    A novel material design in nuclear fusion reactors is proposed based on W-nDiamond nanostructured composites. Generally, a microstructure refined to the nanometer scale improves the mechanical strength due to modification of plasticity mechanisms. Moreover, highly specific grain-boundary area raises the number of sites for annihilation of radiation induced defects. However, the low thermal stability of fine-grained and nanostructured materials demands the presence of particles at the grain boundaries that can delay coarsening by a pinning effect. As a result, the concept of a composite is promising in the field of nanostructured materials. The hardness of diamond renders nanodiamond dispersions excellent reinforcing and stabilization candidates and, in addition, diamond has extremely high thermal conductivity. Consequently, W-nDiamond nanocomposites are promising candidates for thermally stable first-wall materials. The proposed design involves the production of W/W-nDiamond/W-Cu/Cu layered castellations. The W, W-nDiamond and W-Cu layers are produced by mechanical alloying followed by a consolidation route that combines hot rolling with spark plasma sintering (SPS). Layer welding is achieved by spark plasma sintering. The present work describes the mechanical alloying processsing and consolidation route used to produce W-nDiamond composites, as well as microstructural features and mechanical properties of the material produced Long term plasma exposure experiments are planned at ISTTOK and at FTU (Frascati)

  19. Diagnostic of fusion neutrons on JET tokamak using diamond detector

    SciTech Connect (OSTI)

    Nemtsev, G.; Amosov, V.; Marchenko, N.; Meshchaninov, S.; Rodionov, R.; Popovichev, S.; Collaboration: JET EFDA Conbributors

    2014-08-21

    In 2011-2012, an experimental campaign with a significant yield of fusion neutrons was carried out on the JET tokamak. During this campaign the facility was equipped with two diamond detectors based on natural and artificial CVD diamond. These detectors were designed and manufactured in State Research Center of Russian Federation TRINITI. The detectors measure the flux of fast neutrons with energies above 0.2 MeV. They have been installed in the torus hall and the distance from the center of plasma was about 3 m. For some of the JET pulses in this experiment, the neutron flux density corresponded to the operational conditions in collimator channels of ITER Vertical Neutron Camera. The main objective of diamond monitors was the measurement of total fast neutron flux at the detector location and the estimation of the JET total neutron yield. The detectors operate as threshold counters. Additionally a spectrometric measurement channel has been configured that allowed us to distinguish various energy components of the neutron spectrum. In this paper we describe the neutron signal measuring and calibration procedure of the diamond detector. Fluxes of DD and DT neutrons at the detector location were measured. It is shown that the signals of total neutron yield measured by the diamond detector correlate with signals measured by the main JET neutron diagnostic based on fission chambers with high accuracy. This experiment can be considered as a successful test of diamond detectors in ITER-like conditions.

  20. Optical coatings for laser fusion applications

    SciTech Connect (OSTI)

    Lowdermilk, W.H.; Milam, D.; Rainer, F.

    1980-04-24

    Lasers for fusion experiments use thin-film dielectric coatings for reflecting, antireflecting and polarizing surface elements. Coatings are most important to the Nd:glass laser application. The most important requirements of these coatings are accuracy of the average value of reflectance and transmission, uniformity of amplitude and phase front of the reflected or transmitted light, and laser damage threshold. Damage resistance strongly affects the laser's design and performance. The success of advanced lasers for future experiments and for reactor applications requires significant developments in damage resistant coatings for ultraviolet laser radiation.

  1. Overview of the RFX fusion science program

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    1 (2011) 094023 (12pp) doi:10.1088/0029-5515/51/9/094023 Overview of the RFX fusion science program P. Martin 1 , J. Adamek 2 , P. Agostinetti 1 , M. Agostini 1 , A. Alfier 1 , C. Angioni 3 , V. Antoni 1 , L. Apolloni 1 , F. Auriemma 1 , O. Barana 1 , S. Barison 4 , M. Baruzzo 1 , P. Bettini 1 , M. Boldrin 1 , T. Bolzonella 1 , D. Bonfiglio 1 , F. Bonomo 1 , A.H. Boozer 5,6 , M. Brombin 1 , J. Brotankova 2 , A. Buffa 1 , A. Canton 1 , S. Cappello 1 , L. Carraro 1 , R. Cavazzana 1 , M. Cavinato

  2. Packed fluidized bed blanket for fusion reactor

    DOE Patents [OSTI]

    Chi, John W. H. (Mt. Lebanon, PA)

    1984-01-01

    A packed fluidized bed blanket for a fusion reactor providing for efficient radiation absorption for energy recovery, efficient neutron absorption for nuclear transformations, ease of blanket removal, processing and replacement, and on-line fueling/refueling. The blanket of the reactor contains a bed of stationary particles during reactor operation, cooled by a radial flow of coolant. During fueling/refueling, an axial flow is introduced into the bed in stages at various axial locations to fluidize the bed. When desired, the fluidization flow can be used to remove particles from the blanket.

  3. Fusion Basics | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Fusion Basics What is Plasma? Plasma is a state of matter along with solids, liquids and gases. It consists of a partially-ionized gas, containing ions, electrons, and neutral atoms. So what does that mean? In a plasma, some electrons are freed from their atoms, allowing current and electricity to flow. In fact, one of the few naturally-occurring plasmas found here on Earth is lightning! Can you think of other plasmas? Fluorescent light bulbs contain mercury plasma. Stars, such as the sun are

  4. T-661: ColdFusion Security Hotfix | APSB11-14, ColdFusion Important Update

    Broader source: Energy.gov [DOE]

    Vulnerabilities have been identified in ColdFusion 9.0.1 and earlier versions for Windows, Macintosh and UNIX. These vulnerabilities could lead to a cross-site request forgery (CSRF) or a remote denial-of-service (DoS). Adobe recommends users update their product installation using the instructions provided below.

  5. Properties of the ion-ion hybrid resonator in fusion plasmas

    SciTech Connect (OSTI)

    Morales, George J.

    2015-10-06

    The project developed theoretical and numerical descriptions of the properties of ion-ion hybrid Alfvén resonators that are expected to arise in the operation of a fusion reactor. The methodology and theoretical concepts were successfully compared to observations made in basic experiments in the LAPD device at UCLA. An assessment was made of the excitation of resonator modes by energetic alpha particles for burning plasma conditions expected in the ITER device. The broader impacts included the generation of basic insight useful to magnetic fusion and space science researchers, defining new avenues for exploration in basic laboratory experiments, establishing broader contacts between experimentalists and theoreticians, completion of a Ph.D. dissertation, and promotion of interest in science through community outreach events and classroom instruction.

  6. Self-similar structure and experimental signatures of suprathermal ion distribution in inertial confinement fusion implosions

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Kagan, Grigory; Svyatskiy, D.; Rinderknecht, H. G.; Rosenberg, M. J.; Zylstra, A. B.; Huang, C. -K.; McDevitt, C. J.

    2015-09-03

    The distribution function of suprathermal ions is found to be self-similar under conditions relevant to inertial confinement fusion hot spots. By utilizing this feature, interference between the hydrodynamic instabilities and kinetic effects is for the first time assessed quantitatively to find that the instabilities substantially aggravate the fusion reactivity reduction. Thus, the ion tail depletion is also shown to lower the experimentally inferred ion temperature, a novel kinetic effect that may explain the discrepancy between the exploding pusher experiments and rad-hydro simulations and contribute to the observation that temperature inferred from DD reaction products is lower than from DT atmore » the National Ignition Facility.« less

  7. Expert system to control a fusion energy experiment

    SciTech Connect (OSTI)

    Johnson, R.R.; Canales, T.; Lager, D.

    1986-01-01

    This paper describes a system that automates neutral beam source conditioning. The system achieves this with artificial intelligence techniques by encoding the behavior of several experts as a set of if-then rules in an expert system. One of the functions of the expert system is to control an adaptive controller that, in turn, controls the neutral beam source. The architecture of the system is presented followed by a description of its performance.

  8. Study of Plasma Liner Driven Magnetized Target Fusion Via Advanced Simulations

    SciTech Connect (OSTI)

    Samulyak, Roman V.; Parks, Paul

    2013-08-31

    The feasibility of the plasma liner driven Magnetized Target Fusion (MTF) via terascale numerical simulations will be assessed. In the MTF concept, a plasma liner, formed by merging of a number (60 or more) of radial, highly supersonic plasma jets, implodes on the target in the form of two compact plasma toroids, and compresses it to conditions of the fusion ignition. By avoiding major difficulties associated with both the traditional laser driven inertial confinement fusion and solid liner driven MTF, the plasma liner driven MTF potentially provides a low-cost and fast R&D path towards the demonstration of practical fusion energy. High fidelity numerical simulations of full nonlinear models associated with the plasma liner MTF using state-of-art numerical algorithms and terascale computing are necessary in order to resolve uncertainties and provide guidance for future experiments. At Stony Brook University, we have developed unique computational capabilities that ideally suite the MTF problem. The FronTier code, developed in collaboration with BNL and LANL under DOE funding including SciDAC for the simulation of 3D multi-material hydro and MHD flows, has beenbenchmarked and used for fundamental and engineering problems in energy science applications. We have performed 3D simulations of converging supersonic plasma jets, their merger and the formation of the plasma liner, and a study of the corresponding oblique shock problem. We have studied the implosion of the plasma liner on the magnetized plasma target by resolving Rayleigh-Taylor instabilities in 2D and 3D and other relevant physics and estimate thermodynamic conditions of the target at the moment of maximum compression and the hydrodynamic efficiency of the method.

  9. Activation analyses for different fusion structural alloys

    SciTech Connect (OSTI)

    Attaya, H.; Smith, D.

    1991-12-31

    The leading candidate structural materials, viz., the vanadium alloys, the nickel or the manganese stabilized austenitic steels, and the ferritic steels, are analysed in terms of their induced activation in the TPSS fusion power reactor. The TPSS reactor has 1950 MW fusion power and inboard and outboard average neutron wall loading of 3.75 and 5.35 MW/m{sup 2} respectively. The results shows that, after one year of continuous operation, the vanadium alloys have the least radioactivity at reactor shutdown. The maximum difference between the induced radioactivity in the vanadium alloys and in the other iron-based alloys occurs at about 10 years after reactor shutdown. At this time, the total reactor radioactivity, using the vanadium alloys, is about two orders of magnitude less than the total reactor radioactivity utilizing any other alloy. The difference is even larger in the first wall, the FW-vanadium activation is 3 orders of magnitude less than other alloys` FW activation. 2 refs., 7 figs.

  10. Activation analyses for different fusion structural alloys

    SciTech Connect (OSTI)

    Attaya, H.; Smith, D.

    1991-01-01

    The leading candidate structural materials, viz., the vanadium alloys, the nickel or the manganese stabilized austenitic steels, and the ferritic steels, are analysed in terms of their induced activation in the TPSS fusion power reactor. The TPSS reactor has 1950 MW fusion power and inboard and outboard average neutron wall loading of 3.75 and 5.35 MW/m{sup 2} respectively. The results shows that, after one year of continuous operation, the vanadium alloys have the least radioactivity at reactor shutdown. The maximum difference between the induced radioactivity in the vanadium alloys and in the other iron-based alloys occurs at about 10 years after reactor shutdown. At this time, the total reactor radioactivity, using the vanadium alloys, is about two orders of magnitude less than the total reactor radioactivity utilizing any other alloy. The difference is even larger in the first wall, the FW-vanadium activation is 3 orders of magnitude less than other alloys' FW activation. 2 refs., 7 figs.

  11. Dust Combustion Safety Issues for Fusion Applications

    SciTech Connect (OSTI)

    L. C. Cadwallader

    2003-05-01

    This report summarizes the results of a safety research task to identify the safety issues and phenomenology of metallic dust fires and explosions that are postulated for fusion experiments. There are a variety of metal dusts that are created by plasma erosion and disruptions within the plasma chamber, as well as normal industrial dusts generated in the more conventional equipment in the balance of plant. For fusion, in-vessel dusts are generally mixtures of several elements; that is, the constituent elements in alloys and the variety of elements used for in-vessel materials. For example, in-vessel dust could be composed of beryllium from a first wall coating, tungsten from a divertor plate, copper from a plasma heating antenna or diagnostic, and perhaps some iron and chromium from the steel vessel wall or titanium and vanadium from the vessel wall. Each of these elements has its own unique combustion characteristics, and mixtures of elements must be evaluated for the mixtures combustion properties. Issues of particle size, dust temperature, and presence of other combustible materials (i.e., deuterium and tritium) also affect combustion in air. Combustion in other gases has also been investigated to determine if there are safety concerns with inert atmospheres, such as nitrogen. Several coolants have also been reviewed to determine if coolant breach into the plasma chamber would enhance the combustion threat; for example, in-vessel steam from a water coolant breach will react with metal dust. The results of this review are presented here.

  12. New Accelerator Will Study Steps on the Path to Fusion Power

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    New Accelerator Will Study Steps on the Path to Fusion Power New Accelerator Will Study Steps on the Path to Fusion Power Unusual Machine Tailor-made to Examine Heavy-ion Fusion ...

  13. ScienceLive chat page: on the future of fusion research | Princeton Plasma

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Physics Lab ScienceLive chat page: on the future of fusion research American Fusion News Category: U.S. Universities Link: ScienceLive chat page: on the future of fusion research

  14. General Atomics (GA) Fusion News: A New Spin on Understanding Plasma

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Confinement | Princeton Plasma Physics Lab General Atomics (GA) Fusion News: A New Spin on Understanding Plasma Confinement American Fusion News Category: General Atomics (GA) Link: General Atomics (GA) Fusion News: A New Spin on Understanding Plasma Confinement

  15. Fusion utility in the Knudsen layer (Journal Article) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Fusion utility in the Knudsen layer Citation Details In-Document Search Title: Fusion utility in the Knudsen layer In inertial confinement fusion, the loss of fast ions from the...

  16. Purdue Contribution of Fusion Simulation Program

    SciTech Connect (OSTI)

    Jeffrey Brooks

    2011-09-30

    The overall science goal of the FSP is to develop predictive simulation capability for magnetically confined fusion plasmas at an unprecedented level of integration and fidelity. This will directly support and enable effective U.S. participation in research related to the International Thermonuclear Experimental Reactor (ITER) and the overall mission of delivering practical fusion energy. The FSP will address a rich set of scientific issues together with experimental programs, producing validated integrated physics results. This is very well aligned with the mission of the ITER Organization to coordinate with its members the integrated modeling and control of fusion plasmas, including benchmarking and validation activities. [1]. Initial FSP research will focus on two critical areas: 1) the plasma edge and 2) whole device modeling including disruption avoidance. The first of these problems involves the narrow plasma boundary layer and its complex interactions with the plasma core and the surrounding material wall. The second requires development of a computationally tractable, but comprehensive model that describes all equilibrium and dynamic processes at a sufficient level of detail to provide useful prediction of the temporal evolution of fusion plasma experiments. The initial driver for the whole device model (WDM) will be prediction and avoidance of discharge-terminating disruptions, especially at high performance, which are a critical impediment to successful operation of machines like ITER. If disruptions prove unable to be avoided, their associated dynamics and effects will be addressed in the next phase of the FSP. The FSP plan targets the needed modeling capabilities by developing Integrated Science Applications (ISAs) specific to their needs. The Pedestal-Boundary model will include boundary magnetic topology, cross-field transport of multi-species plasmas, parallel plasma transport, neutral transport, atomic physics and interactions with the plasma wall. It will address the origins and structure of the plasma electric field, rotation, the L-H transition, and the wide variety of pedestal relaxation mechanisms. The Whole Device Model will predict the entire discharge evolution given external actuators (i.e., magnets, power supplies, heating, current drive and fueling systems) and control strategies. Based on components operating over a range of physics fidelity, the WDM will model the plasma equilibrium, plasma sources, profile evolution, linear stability and nonlinear evolution toward a disruption (but not the full disruption dynamics). The plan assumes that, as the FSP matures and demonstrates success, the program will evolve and grow, enabling additional science problems to be addressed. The next set of integration opportunities could include: 1) Simulation of disruption dynamics and their effects; 2) Prediction of core profile including 3D effects, mesoscale dynamics and integration with the edge plasma; 3) Computation of non-thermal particle distributions, self-consistent with fusion, radio frequency (RF) and neutral beam injection (NBI) sources, magnetohydrodynamics (MHD) and short-wavelength turbulence.

  17. Semiconductor Laser Diode Pumps for Inertial Fusion Energy Lasers

    SciTech Connect (OSTI)

    Deri, R J

    2011-01-03

    Solid-state lasers have been demonstrated as attractive drivers for inertial confinement fusion on the National Ignition Facility (NIF) at Lawrence Livermore National Laboratory (LLNL) and at the Omega Facility at the Laboratory for Laser Energetics (LLE) in Rochester, NY. For power plant applications, these lasers must be pumped by semiconductor diode lasers to achieve the required laser system efficiency, repetition rate, and lifetime. Inertial fusion energy (IFE) power plants will require approximately 40-to-80 GW of peak pump power, and must operate efficiently and with high system availability for decades. These considerations lead to requirements on the efficiency, price, and production capacity of the semiconductor pump sources. This document provides a brief summary of these requirements, and how they can be met by a natural evolution of the current semiconductor laser industry. The detailed technical requirements described in this document flow down from a laser ampl9ifier design described elsewhere. In brief, laser amplifiers comprising multiple Nd:glass gain slabs are face-pumped by two planar diode arrays, each delivering 30 to 40 MW of peak power at 872 nm during a {approx} 200 {micro}s quasi-CW (QCW) pulse with a repetition rate in the range of 10 to 20 Hz. The baseline design of the diode array employs a 2D mosaic of submodules to facilitate manufacturing. As a baseline, they envision that each submodule is an array of vertically stacked, 1 cm wide, edge-emitting diode bars, an industry standard form factor. These stacks are mounted on a common backplane providing cooling and current drive. Stacks are conductively cooled to the backplane, to minimize both diode package cost and the number of fluid interconnects for improved reliability. While the baseline assessment in this document is based on edge-emitting devices, the amplifier design does not preclude future use of surface emitting diodes, which may offer appreciable future cost reductions and increased reliability. The high-level requirements on the semiconductor lasers involve reliability, price points on a price-per-Watt basis, and a set of technical requirements. The technical requirements for the amplifier design in reference 1 are discussed in detail and are summarized in Table 1. These values are still subject to changes as the overall laser system continues to be optimized. Since pump costs can be a significant fraction of the overall laser system cost, it is important to achieve sufficiently low price points for these components. At this time, the price target for tenth-of-akind IFE plant is $0.007/Watt for packaged devices. At this target level, the pumps account for approximately one third of the laser cost. The pump lasers should last for the life of the power plant, leading to a target component lifetime requirement of roughly 14 Ghosts, corresponding to a 30 year plant life and 15 Hz repetition rate. An attractive path forward involes pump operation at high output power levels, on a Watts-per-bar (Watts/chip) basis. This reduces the cost of pump power (price-per-Watt), since to first order the unit price does not increase with power/bar. The industry has seen a continual improvement in power output, with current 1 cm-wide bars emitting up to 500 W QCW (quasi-continuous wave). Increased power/bar also facilitates achieving high irradiance in the array plane. On the other hand, increased power implies greater heat loads and (possibly) higher current drive, which will require increased attention to thermal management and parasitic series resistance. Diode chips containing multiple p-n junctions and quantum wells (also called nanostack structures) may provide an additional approach to reduce the peak current.

  18. Fission-suppressed hybrid reactor: the fusion breeder

    SciTech Connect (OSTI)

    Moir, R.W.; Lee, J.D.; Coops, M.S.

    1982-12-01

    Results of a conceptual design study of a /sup 233/U-producing fusion breeder are presented. The majority of the study was devoted to conceptual design and evaluation of a fission-suppressed blanket and to fuel cycle issues such as fuel reprocessing, fuel handling, and fuel management. Studies in the areas of fusion engineering, reactor safety, and economics were also performed.

  19. Methods of detection using a cellulose binding domain fusion product

    DOE Patents [OSTI]

    Shoseyov, Oded (Shimshon, IL); Shpiegl, Itai (North Gallilea, IL); Goldstein, Marc A. (Davis, CA); Doi, Roy H. (Davis, CA)

    1999-01-01

    A cellulose binding domain (CBD) having a high affinity for crystalline cellulose and chitin is disclosed, along with methods for the molecular cloning and recombinant production thereof. Fusion products comprising the CBD and a second protein are likewise described. A wide range of applications are contemplated for both the CBD and the fusion products, including drug delivery, affinity separations, and diagnostic techniques.

  20. Variable control of neutron albedo in toroidal fusion devices

    DOE Patents [OSTI]

    Jassby, D.L.; Micklich, B.J.

    1983-06-01

    This invention pertains to methods of controlling in the steady state, neutron albedo in toroidal fusion devices, and in particular, to methods of controlling the flux and energy distribution of collided neutrons which are incident on an outboard wall of a toroidal fusion device.

  1. C+C Fusion Cross Sections Measurements for Nuclear Astrophysics

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Almaraz-Calderon, S.; Carnelli, P. F. F.; Rehm, K. E.; Albers, M.; Alcorta, M.; Bertone, P. F.; Digiovine, B.; Esbensen, H.; Fernandez Niello, J. O.; Henderson, D.; et al

    2015-06-02

    Total fusion cross section of carbon isotopes were obtained using the newly developed MUSIC detector. MUSIC is a highly efficient, active target-detector system designed to measure fusion excitation functions with radioactive beams. The present measurements are relevant for understanding x-ray superbursts. The results of the first MUSIC campaign as well as the astrophysical implications are presented in this work.

  2. The TITAN reversed-field-pinch fusion reactor study

    SciTech Connect (OSTI)

    Not Available

    1990-01-01

    This report discusses research on the titan-1 fusion power core. The major topics covered are: titan-1 fusion-power-core engineering; titan-1 divertor engineering; titan-1 tritium systems; titan-1 safety design and radioactive-waste disposal; and titan-1 maintenance procedures.

  3. Joint Working Group for Fusion Safety | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Business Operations Careers/ Human Resources Directory Environment, Safety & Health Environmental Management System Joint Working Group for Fusion Safety Furth Plasma Physics Library Lab Leadership Organization Chart Technology Transfer Contact Us Business Operations Careers/ Human Resources Directory Environment, Safety & Health Environmental Management System Joint Working Group for Fusion Safety Furth Plasma Physics Library Lab Leadership Organization Chart Technology Transfer Joint

  4. Methods of detection using a cellulose binding domain fusion product

    DOE Patents [OSTI]

    Shoseyov, O.; Shpiegl, I.; Goldstein, M.A.; Doi, R.H.

    1999-01-05

    A cellulose binding domain (CBD) having a high affinity for crystalline cellulose and chitin is disclosed, along with methods for the molecular cloning and recombinant production. Fusion products comprising the CBD and a second protein are likewise described. A wide range of applications are contemplated for both the CBD and the fusion products, including drug delivery, affinity separations, and diagnostic techniques. 34 figs.

  5. Fusion safety program Annual report, Fiscal year 1995

    SciTech Connect (OSTI)

    Longhurst, G.R.; Cadwallader, L.C.; Carmack, W.J.

    1995-12-01

    This report summarizes the major activities of the Fusion Safety Program in FY-95. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory, and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions. Among the technical areas covered in this report are tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate database development, and safety code development and application to fusion safety issues. Most of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and the technical support for commercial fusion facility conceptual design studies. A final activity described is work to develop DOE Technical Standards for Safety of Fusion Test Facilities.

  6. Fusion Safety Program annual report, fiscal year 1994

    SciTech Connect (OSTI)

    Longhurst, G.R.; Cadwallader, L.C.; Dolan, T.J.; Herring, J.S.; McCarthy, K.A.; Merrill, B.J.; Motloch, C.G.; Petti, D.A.

    1995-03-01

    This report summarizes the major activities of the Fusion Safety Program in fiscal year 1994. The Idaho National Engineering Laboratory (INEL) is the designated lead laboratory and Lockheed Idaho Technologies Company is the prime contractor for this program. The Fusion Safety Program was initiated in 1979. Activities are conducted at the INEL, at other DOE laboratories, and at other institutions, including the University of Wisconsin. The technical areas covered in this report include tritium safety, beryllium safety, chemical reactions and activation product release, safety aspects of fusion magnet systems, plasma disruptions, risk assessment failure rate data base development, and thermalhydraulics code development and their application to fusion safety issues. Much of this work has been done in support of the International Thermonuclear Experimental Reactor (ITER). Also included in the report are summaries of the safety and environmental studies performed by the Fusion Safety Program for the Tokamak Physics Experiment and the Tokamak Fusion Test Reactor and of the technical support for commercial fusion facility conceptual design studies. A major activity this year has been work to develop a DOE Technical Standard for the safety of fusion test facilities.

  7. Idaho Site Contractor Achieves Treatment Project Milestone

    Broader source: Energy.gov [DOE]

    IDAHO FALLS, Idaho The Idaho sites main cleanup contractor recently achieved a major performance milestone by successfully passing an operational readiness review for a first-of-a-kind facility that will treat the remaining 900,000 gallons of liquid radioactive waste generated by the sites legacy cleanup mission.

  8. Savannah River Analytical Laboratories Achieve International Standard

    National Nuclear Security Administration (NNSA)

    Accreditation | National Nuclear Security Administration Analytical Laboratories Achieve International Standard Accreditation | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional

  9. Secretary's 2014 Achievement Awards | Department of Energy

    Energy Savers [EERE]

    Seismic Life-Safety, Modernization, and Replacement of General Purpose Buildings, Phase 2 Project (Office of Science) More Documents & Publications 2014 Awards for Project Management Acquisition and Project Management Awards Presentations - Ingrid Kolb, Director, Office of Management Secretary's 2013 Achievement Awards

  10. Inertial Confinement Fusion and the National Ignition Facility (NIF)

    SciTech Connect (OSTI)

    Ross, P.

    2012-08-29

    Inertial confinement fusion (ICF) seeks to provide sustainable fusion energy by compressing frozen deuterium and tritium fuel to extremely high densities. The advantages of fusion vs. fission are discussed, including total energy per reaction and energy per nucleon. The Lawson Criterion, defining the requirements for ignition, is derived and explained. Different confinement methods and their implications are discussed. The feasibility of creating a power plant using ICF is analyzed using realistic and feasible numbers. The National Ignition Facility (NIF) at Lawrence Livermore National Laboratory is shown as a significant step forward toward making a fusion power plant based on ICF. NIF is the worlds largest laser, delivering 1.8 MJ of energy, with a peak power greater than 500 TW. NIF is actively striving toward the goal of fusion energy. Other uses for NIF are discussed.

  11. PPPL to launch major upgrade of key fusion energy test facility...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    to launch major upgrade of key fusion energy test facility NSTX project will produce most ... of nuclear fusion as a clean, safe and abundant fuel for generating electricity. ...

  12. Fusion scientists gear up to learn how to harness plasma energy...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Living on the edge Fusion scientists gear up to learn how to harness plasma energy By ... Researchers working on an advanced experimental fusion reactor are readying experiments ...

  13. Rajesh Maingi adds a new strategic dimension to fusion and plasma...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Rajesh Maingi adds a new strategic dimension to fusion and plasma physics research By John ... gas that fuels fusion reactions in donut-shaped magnetic facilities called tokamaks. ...

  14. Construction completed, PPPL is set to resume world-class fusion...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Construction completed, PPPL is set to resume world-class fusion research later this fall ... Plasma Physics Laboratory (PPPL), world-leading fusion research resumes later this fall. ...

  15. PPPL and ITER: Lab teams support the world's largest fusion experiment...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    France. ITER is designed to demonstrate the scientific and technological feasibility of fusion power by the ... design and operation of nuclear fusion facilities, but ...

  16. Cadwallader, L.C. 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; MAGNETIC

    Office of Scientific and Technical Information (OSTI)

    Selected component failure rate values from fusion safety assessment tasks Cadwallader, L.C. 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; MAGNETIC CONFINEMENT; THERMONUCLEAR DEVICES;...

  17. U.S. Signs International Fusion Energy Agreement; Large-Scale...

    Office of Science (SC) Website

    U.S. Signs International Fusion Energy Agreement; Large-Scale, Clean Fusion Energy Project to Begin Construction News News Home Featured Articles Science Headlines 2015 2014 2013 ...

  18. Fusion Energy Sciences (FES) Homepage | U.S. DOE Office of Science...

    Office of Science (SC) Website

    Programs FES Home Fusion Energy Sciences (FES) FES Home About Research Facilities Science Highlights Benefits of FES Funding Opportunities Fusion Energy Sciences Advisory ...

  19. Laser-fusion targets for reactors

    DOE Patents [OSTI]

    Nuckolls, John H. (Livermore, CA); Thiessen, Albert R. (Livermore, CA)

    1987-01-01

    A laser target comprising a thermonuclear fuel capsule composed of a centrally located quantity of fuel surrounded by at least one or more layers or shells of material for forming an atmosphere around the capsule by a low energy laser prepulse. The fuel may be formed as a solid core or hollow shell, and, under certain applications, a pusher-layer or shell is located intermediate the fuel and the atmosphere forming material. The fuel is ignited by symmetrical implosion via energy produced by a laser, or other energy sources such as an electron beam machine or ion beam machine, whereby thermonuclear burn of the fuel capsule creates energy for applications such as generation of electricity via a laser fusion reactor.

  20. Fusion-fission energy systems evaluation

    SciTech Connect (OSTI)

    Teofilo, V.L.; Aase, D.T.; Bickford, W.E.

    1980-01-01

    This report serves as the basis for comparing the fusion-fission (hybrid) energy system concept with other advanced technology fissile fuel breeding concepts evaluated in the Nonproliferation Alternative Systems Assessment Program (NASAP). As such, much of the information and data provided herein is in a form that meets the NASAP data requirements. Since the hybrid concept has not been studied as extensively as many of the other fission concepts being examined in NASAP, the provided data and information are sparse relative to these more developed concepts. Nevertheless, this report is intended to provide a perspective on hybrids and to summarize the findings of the rather limited analyses made to date on this concept.

  1. Thermomagnetic burn control for magnetic fusion reactor

    DOE Patents [OSTI]

    Rawls, John M. (Del Mar, CA); Peuron, Unto A. (Solana Beach, CA)

    1982-01-01

    Apparatus is provided for controlling the plasma energy production rate of a magnetic-confinement fusion reactor, by controlling the magnetic field ripple. The apparatus includes a group of shield sectors (30a, 30b, etc.) formed of ferromagnetic material which has a temperature-dependent saturation magnetization, with each shield lying between the plasma (12) and a toroidal field coil (18). A mechanism (60) for controlling the temperature of the magnetic shields, as by controlling the flow of cooling water therethrough, thereby controls the saturation magnetization of the shields and therefore the amount of ripple in the magnetic field that confines the plasma, to thereby control the amount of heat loss from the plasma. This heat loss in turn determines the plasma state and thus the rate of energy production.

  2. Thermomagnetic burn control for magnetic fusion reactor

    DOE Patents [OSTI]

    Rawls, J.M.; Peuron, A.U.

    1980-07-01

    Apparatus is provided for controlling the plasma energy production rate of a magnetic-confinement fusion reactor, by controlling the magnetic field ripple. The apparatus includes a group of shield sectors formed of ferromagnetic material which has a temperature-dependent saturation magnetization, with each shield lying between the plasma and a toroidal field coil. A mechanism for controlling the temperature of the magnetic shields, as by controlling the flow of cooling water therethrough, thereby controls the saturation magnetization of the shields and therefore the amount of ripple in the magnetic field that confines the plasma, to thereby control the amount of heat loss from the plasma. This heat loss in turn determines the plasma state and thus the rate of energy production.

  3. Dynamical dipole mode in fusion reactions

    SciTech Connect (OSTI)

    Pierroutsakou, D.; Boiano, A.; Romoli, M.; Martin, B.; Inglima, G.; La Commara, M.; Sandoli, M.; Agodi, C.; Alba, R.; Coniglione, R.; Zoppo, A. Del; Maiolino, C.; Piattelli, P.; Santonocito, D.; Sapienza, P.; Baran, V.; Glodariu, T.; Cardella, G.; De Filippo, E.; Pagano, A.

    2009-05-04

    We investigated the dynamical dipole mode, related with entrance channel charge asymmetry effects, in the {sup 40}Ar+{sup 92}Zr and {sup 36}Ar+{sup 96}Zr fusion reactions at E{sub lab} = 15.1 A and 16 A MeV, respectively. These reactions populate, through entrance channels having different charge asymmetries, a compound nucleus in the A = 126 mass energy region, identical spin distribution at an average excitation energy of about 280 MeV. The compound nucleus average excitation energy and average mass were deduced by the analysis of the light charged particle energy spectra. By studying the {gamma}-ray energy spectra and the {gamma}-ray angular distributions of the considered reactions, the dynamical nature of the prompt radiation related to the dynamical dipole mode was evidenced. The data are compared with calculations based on a collective bremsstrahlung analysis of the reaction dynamics.

  4. Laser-driven fusion etching process

    DOE Patents [OSTI]

    Ashby, Carol I. H. (Edgewood, NM); Brannon, Paul J. (Albuquerque, NM); Gerardo, James B. (Albuquerque, NM)

    1989-01-01

    The surfaces of solid ionic substrates are etched by a radiation-driven chemical reaction. The process involves exposing an ionic substrate coated with a layer of a reactant material on its surface to radiation, e.g. a laser, to induce localized melting of the substrate which results in the occurrance of a fusion reaction between the substrate and coating material. The resultant reaction product and excess reactant salt are then removed from the surface of the substrate with a solvent which is relatively inert towards the substrate. The laser-driven chemical etching process is especially suitable for etching ionic salt substrates, e.g., a solid inorganic salt such as LiNbO.sub.3, such as used in electro-optical/acousto-optic devices. It is also suitable for applications wherein the etching process is required to produce an etched ionic substrate having a smooth surface morphology or when a very rapid etching rate is desired.

  5. Blanket materials for DT fusion reactors

    SciTech Connect (OSTI)

    Smith, D.L.

    1981-01-01

    This paper presents an overview of the critical materials issues that must be considered in the development of a tritium breeding blanket for a tokamak fusion reactor that operates on the D-T-Li fuel cycle. The primary requirements of the blanket system are identified and the important criteria that must be considered in the development of blanket technology are summarized. The candidate materials are listed for the different blanket components, e.g., breeder, coolant, structure and neutron multiplier. Three blanket concepts that appear to offer the most potential are: (1) liquid-metal breeder/coolant, (2) liquid-metal breeder/separate coolant, and (3) solid breeder/separate coolant. The major uncertainties associated with each of the design concepts are discussed and the key materials R and D requirements for each concept are identified.

  6. Numerical Studies of Impurities in Fusion Plasmas

    DOE R&D Accomplishments [OSTI]

    Hulse, R. A.

    1982-09-01

    The coupled partial differential equations used to describe the behavior of impurity ions in magnetically confined controlled fusion plasmas require numerical solution for cases of practical interest. Computer codes developed for impurity modeling at the Princeton Plasma Physics Laboratory are used as examples of the types of codes employed for this purpose. These codes solve for the impurity ionization state densities and associated radiation rates using atomic physics appropriate for these low-density, high-temperature plasmas. The simpler codes solve local equations in zero spatial dimensions while more complex cases require codes which explicitly include transport of the impurity ions simultaneously with the atomic processes of ionization and recombination. Typical applications are discussed and computational results are presented for selected cases of interest.

  7. Laser-driven fusion etching process

    DOE Patents [OSTI]

    Ashby, C.I.H.; Brannon, P.J.; Gerardo, J.B.

    1987-08-25

    The surfaces of solids are etched by a radiation-driven chemical reaction. The process involves exposing a substrate coated with a layer of a reactant material on its surface to radiation, e.g., a laser, to induce localized melting of the substrate which results in the occurrence of a fusion reaction between the substrate and coating material. The resultant reaction product and excess reactant salt are then removed from the surface of the substrate with a solvent which is relatively inert towards the substrate. The laser-driven chemical etching process is especially suitable for etching ionic substrates, e.g., LiNbO/sub 3/, such as used in electro-optical/acousto-optic devices. It is also suitable for applications wherein the etching process is required to produce an etched ionic substrate having a smooth surface morphology or when a very rapid etching rate is desired.

  8. Roadmap to Achieve Energy Delivery Systems Cybersecurity

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Roadmap to Achieve Energy Delivery Systems Cybersecurity ii Acknowledgements The Energy Sector Control Systems Working Group (ESCSWG) developed this roadmap in support of the Electricity Sub-sector Coordinating Council, Oil and Natural Gas Sector Coordinating Council, and the Government Coordinating Council for Energy under the Critical Infrastructure Partnership Advisory Council (CIPAC) Framework; the roadmap has been approved for release by these councils. The ESCSWG members volunteered their

  9. NREL Achieves Solar-Electric Record

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    NREL Achieves Solar-Electric Record New Technology Could Spur Growth in Photovoltaic Panels For more information contact: Gary Schmitz, 303-275-4050 email: Gary Schmitz Golden, Colo., Apr. 24, 2001 - Researchers at the U.S. Department of Energy's National Renewable Energy Laboratory have surpassed a record for electricity produced by solar cells made from cadmium telluride—a development that could help meet expanding demand for solar systems. The measurement of 16.4 percent efficiency bested

  10. Collaboration drives achievement in protein structure research

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Protein structure research Collaboration drives achievement in protein structure research By tracking down how bacterial defense systems work, the scientists can potentially fight infectious diseases and genetic disorders. September 15, 2014 Thomas Terwilliger Thomas Terwilliger Contact Nancy Ambrosiano Communications Office (505) 667-0471 Email "It is tremendously exciting working with researchers around the world, helping them apply the software and algorithms that we have developed to

  11. Secretary's Achievement Award (SING) | Department of Energy

    Energy Savers [EERE]

    SING) Secretary's Achievement Award (SING) (from left to right) Daniel Poneman; David Arakawa; Barbara Thibadeau; Phillip Kraushaar; Daniel Lehman; Ingrid Kolb (from left to right) Daniel Poneman; David Arakawa; Barbara Thibadeau; Phillip Kraushaar; Daniel Lehman; Ingrid Kolb Presented to: The Office of Science's Spallation Neutron Source Instruments - Next Generation (SING) Project The SING team capitalized on the technical and managerial efficiency gained by combining the five instruments into

  12. Fatigue cracking of a bare steel first wall in an inertial confinement fusion chamber

    SciTech Connect (OSTI)

    Hunt, R. M.; Abbott, R. P.; Havstad, M. A.; Dunne, A. M.

    2013-06-01

    Inertial confinement fusion power plants will deposit high energy X-rays onto the outer surfaces of the first wall many times a second for the lifetime of the plant. These X-rays create brief temperature spikes in the first few microns of the wall, which cause an associated highly compressive stress response on the surface of the material. The periodicity of this stress pulse is a concern due to the possibility of fatigue cracking of the wall. We have used finite element analyses to simulate the conditions present on the first wall in order to evaluate the driving force of crack propagation on fusion-facing surface cracks. Analysis results indicate that the X-ray induced plastic compressive stress creates a region of residual tension on the surface between pulses. This tension film will likely result in surface cracking upon repeated cycling. Additionally, the compressive pulse may induce plasticity ahead of the crack tip, leaving residual tension in its wake. However, the stress amplitude decreases dramatically for depths greater than 80100 ?m into the fusion-facing surface. Crack propagation models as well as stress-life estimates agree that even though small cracks may form on the surface of the wall, they are unlikely to propagate further than 100 ?m without assistance from creep or grain erosion phenomena.

  13. Midterm Summary of Japan-US Fusion Cooperation Program TITAN

    SciTech Connect (OSTI)

    Muroga, Takeo; Sze, Dai-Kai; Sokolov, Mikhail; Katoh, Yutai; Stoller, Roger E

    2011-01-01

    Japan-US cooperation program TITAN (Tritium, Irradiation and Thermofluid for America and Nippon) started in April 2007 as 6-year project. This is the summary report at the midterm of the project. Historical overview of the Japan-US cooperation programs and direction of the TITAN project in its second half are presented in addition to the technical highlights. Blankets are component systems whose principal functions are extraction of heat and tritium. Thus it is crucial to clarify the potentiality for controlling heat and tritium flow throughout the first wall, blanket and out-of-vessel recovery systems. The TITAN project continues the JUPITER-II activity but extends its scope including the first wall and the recovery systems with the title of 'Tritium and thermofluid control for magnetic and inertial confinement systems'. The objective of the program is to clarify the mechanisms of tritium and heat transfer throughout the first-wall, the blanket and the heat/tritium recovery systems under specific conditions to fusion such as irradiation, high heat flux, circulation and high magnetic fields. Based on integrated models, the breeding, transfer, inventory of tritium and heat extraction properties will be evaluated for some representative liquid breeder blankets and the necessary database will be obtained for focused research in the future.

  14. Inertial Fusion Power Plant Concept of Operations and Maintenance

    SciTech Connect (OSTI)

    Anklam, T.; Knutson, B.; Dunne, A. M.; Kasper, J.; Sheehan, T.; Lang, D.; Roberts, V.; Mau, D.

    2015-01-15

    Parsons and LLNL scientists and engineers performed design and engineering work for power plant pre-conceptual designs based on the anticipated laser fusion demonstrations at the National Ignition Facility (NIF). Work included identifying concepts of operations and maintenance (O&M) and associated requirements relevant to fusion power plant systems analysis. A laser fusion power plant would incorporate a large process and power conversion facility with a laser system and fusion engine serving as the heat source, based in part on some of the systems and technologies advanced at NIF. Process operations would be similar in scope to those used in chemical, oil refinery, and nuclear waste processing facilities, while power conversion operations would be similar to those used in commercial thermal power plants. While some aspects of the tritium fuel cycle can be based on existing technologies, many aspects of a laser fusion power plant presents several important and unique O&M requirements that demand new solutions. For example, onsite recovery of tritium; unique remote material handling systems for use in areas with high radiation, radioactive materials, or high temperatures; a five-year fusion engine target chamber replacement cycle with other annual and multi-year cycles anticipated for major maintenance of other systems, structures, and components (SSC); and unique SSC for fusion target waste recycling streams. This paper describes fusion power plant O&M concepts and requirements, how O&M requirements could be met in design, and how basic organizational and planning issues can be addressed for a safe, reliable, economic, and feasible fusion power plant.

  15. OMEGA EP Power Conditioning - Laboratory for Laser Energetics

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    EP Power Conditioning - Laboratory for Laser Energetics Laboratory for Laser Energetics Logo Search Home Around the Lab Past Issues Past Quick Shots About Office of the Director Map to LLE LLE Tours LLE Building Map Partnerships Careers Education Undergraduate Program Graduate Program High School Program Faculty Contacts Computational Astrophysics H-E-D Physics Inertial Confinement Fusion Laser-Plasma Interaction Radiative Hydrodynamics Plasma Astrophysics Organization Director's Office Laser

  16. Diagnosing magnetized liner inertial fusion experiments on Z

    SciTech Connect (OSTI)

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

    2015-05-15

    Magnetized Liner Inertial Fusion experiments performed at Sandia's Z facility have demonstrated significant thermonuclear fusion neutron yields (∼10{sup 12} DD neutrons) from multi-keV deuterium plasmas inertially confined by slow (∼10 cm/μs), stable, cylindrical implosions. Effective magnetic confinement of charged fusion reactants and products is signaled by high secondary DT neutron yields above 10{sup 10}. Analysis of extensive power, imaging, and spectroscopic x-ray measurements provides a detailed picture of ∼3 keV temperatures, 0.3 g/cm{sup 3} densities, gradients, and mix in the fuel and liner over the 1–2 ns stagnation duration.

  17. Variable control of neutron albedo in toroidal fusion devices

    DOE Patents [OSTI]

    Jassby, Daniel L. (Princeton, NJ); Micklich, Bradley J. (Princeton, NJ)

    1986-01-01

    An arrangement is provided for controlling neutron albedo in toroidal fusion devices having inboard and outboard vacuum vessel walls for containment of the neutrons of a fusion plasma. Neutron albedo material is disposed immediately adjacent the inboard wall, and is movable, preferably in vertical directions, so as to be brought into and out of neutron modifying communication with the fusion neutrons. Neutron albedo material preferably comprises a liquid form, but may also take pebble, stringer and curtain-like forms. A neutron flux valve, rotatable about a vertical axis is also disclosed.

  18. Diagnosing magnetized liner inertial fusion experiments on Z

    SciTech Connect (OSTI)

    Hansen, Stephanie B.; Gomez, Matthew R.; Sefkow, Adam B.; Slutz, Stephen A.; Sinars, Daniel Brian; Hahn, Kelly; Harding, Eric; Knapp, Patrick; Schmit, Paul; Awe, Thomas James; McBride, Ryan D.; Jennings, Christopher; Geissel, Matthias; Harvey-Thompson, Adam James; Peterson, K. J.; Rovang, Dean C.; Chandler, Gordon A.; Cooper, Gary Wayne; Cuneo, Michael Edward; Herrmann, Mark C.; Mark Harry Hess; Johns, Owen; Lamppa, Derek C.; Martin, Matthew; Porter, J. L.; Robertson, G. K.; Rochau, G. A.; Ruiz, C. L.; Savage, M. E.; Smith, I. C.; Stygar, W. A.; Vesey, R. A.; Blue, B. E.; Ryutov, D.; Schroen, Diana; Tomlinson, K.

    2015-05-14

    The Magnetized Liner Inertial Fusion experiments performed at Sandia's Z facility have demonstrated significant thermonuclear fusion neutron yields (~1012 DD neutrons) from multi-keV deuterium plasmasinertially confined by slow (~10 cm/?s), stable, cylindrical implosions. Moreover, effective magnetic confinement of charged fusion reactants and products is signaled by high secondary DT neutron yields above 1010. Further analysis of extensive power, imaging, and spectroscopicx-ray measurements provides a detailed picture of ~3 keV temperatures, 0.3 g/cm3 densities, gradients, and mix in the fuel and liner over the 12 ns stagnation duration.

  19. Fusion Energy Greg Hammett & Russell Kulsred Princeton University

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Spitzer's 100th: Founding PPPL & Pioneering Work in Fusion Energy Greg Hammett & Russell Kulsred Princeton University Wednesday, Dec 4, 2013 - 4:15PM MBG AUDITORIUM Refreshments at 4:00PM The PrinceTon Plasma Physics laboraTory is a U.s. DeParTmenT of energy faciliTy Lyman Spitzer, Jr. made major contributions in several fields of astrophysics, plasma physics, and fusion energy. He invented the novel stellarator concept for confining plasmas for fusion, and was an early proponent of

  20. COLLOQUIUM: The Many Faces of Fusion | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    April 14, 2014, 4:00pm to 5:30pm Colloquia MBG Auditorium COLLOQUIUM: The Many Faces of Fusion Mr. Dan Clery Science Magazine Dan Clery, a veteran journalist for Science magazine and author of "A Piece of the Sun," a wide-ranging account of the quest for fusion energy, will provide a whirlwind tour of the history of fusion from the 1850s to the present day and the people who made it happen. The journey will take in atom spies, superpower summits, hijackings by Palestinian terrorists,

  1. Simulations of Inertial Confinement Fusion Driven by a Novel Synchrotron Radiation-Based X-Ray Igniter

    SciTech Connect (OSTI)

    Shlyaptsev, V; Tatchyn, R

    2004-01-13

    The advantages and challenges of using a powerful x-ray source for the fast ignition of compressed Inertial Confinement Fusion (ICF) targets have been considered. The requirements for such a source together with the optics to focus the x-rays onto compressed DT cores lead to a conceptual design based on Energy Recovery Linacs (ERLs) and long wigglers to produce x-ray pulses with the appropriate phase space properties. A comparative assessment of the parameters of the igniter system indicates that the technologies for building it, although expensive, are physically achievable. Our x-ray fast ignition (XFI) scheme requires substantially smaller energy for the initiation of nuclear fusion reactions than other methods.

  2. Spallation as a dominant source of pusher-fuel and hot-spot mix in inertial confinement fusion capsules

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Orth, Charles D.

    2016-02-23

    We suggest that a potentially dominant but previously neglected source of pusher-fuel and hot-spot “mix” may have been the main degradation mechanism for fusion energy yields of modern inertial confinement fusion (ICF) capsules designed and fielded to achieve high yields — not hydrodynamic instabilities. This potentially dominant mix source is the spallation of small chunks or “grains” of pusher material into the fuel regions whenever (1) the solid material adjacent to the fuel changes its phase by nucleation, and (2) this solid material spalls under shock loading and sudden decompression. Finally, we describe this mix mechanism, support it with simulationsmore » and experimental evidence, and explain how to eliminate it and thereby allow higher yields for ICF capsules and possibly ignition at the National Ignition Facility.« less

  3. Cygnus Achieves Shot 3,000

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Cygnus Achieves Shot 3,000 The newest Tactical Response Force members have more than 50 years military experience. This is a milestone within the national security community. See page 3. See page 5. RSL Plays Key Role in Protecting the Pope during Historic U.S. Visit It's not an everyday occurrence that the religious leader of the Roman Catholic Church converges on three U.S. cities in a five-day timespan. During the week of Sept. 21, Pope Francis made his first visit to the United States, which

  4. Source term evaluation for accident transients in the experimental fusion facility ITER

    SciTech Connect (OSTI)

    Virot, F.; Barrachin, M.; Cousin, F.

    2015-03-15

    We have studied the transport and chemical speciation of radio-toxic and toxic species for an event of water ingress in the vacuum vessel of experimental fusion facility ITER with the ASTEC code. In particular our evaluation takes into account an assessed thermodynamic data for the beryllium gaseous species. This study shows that deposited beryllium dusts of atomic Be and Be(OH){sub 2} are formed. It also shows that Be(OT){sub 2} could exist in some conditions in the drain tank. (authors)

  5. Alpha particle losses from Tokamak Fusion Test Reactor deuterium-tritium plasmas

    SciTech Connect (OSTI)

    Darrow, D.S.; Zweben, S.J.; Batha, S.

    1996-01-01

    Because alpha particle losses can have a significant influence on tokamak reactor viability, the loss of deuterium-tritium alpha particles from the Tokamak Fusion Test Reactor (TFTR) has been measured under a wide range of conditions. In TFTR, first orbit loss and stochastic toroidal field ripple diffusion are always present. Other losses can arise due to magnetohydrodynamic instabilities or due to waves in the ion cyclotron range of frequencies. No alpha particle losses have yet been seen due to collective instabilities driven by alphas. Ion Bernstein waves can drive large losses of fast ions from TFTR, and details of those losses support one element of the alpha energy channeling scenario.

  6. Analysis of the neutron time-of-flight spectra from inertial confinement fusion experiments

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Hatarik, R.; Sayre, D. B.; Caggiano, J. A.; Phillips, T.; Eckart, M. J.; Bond, E. J.; Cerjan, C.; Grim, G. P.; Hartouni, E. P.; Knauer, J. P.; et al

    2015-11-12

    For a long time, neutron time-of-flight diagnostics been used to characterize the neutron spectrum produced by inertial confinement fusion experiments. The primary diagnostic goals are to extract the d+t→n+α (DT) and d+d→n+³He (DD) neutron yields and peak widths, and the amount DT scattering relative to its unscattered yield, which is also known as the down-scatter ratio (DSR). These quantities are used to infer yield weighted plasma conditions, such as ion temperature (Tion) and cold fuel areal density. We explain such novel methodologies used to determine neutron yield, apparent Tion and DSR.

  7. A DATA FUSION SYSTEM FOR THE NONDESTRUCTIVE EVALUATION OF NON-PIGGABLE PIPES

    SciTech Connect (OSTI)

    Shreekanth Mandayam; Robi Polikar; John C. Chen

    2005-05-01

    The objectives of this research project are: (1) To design sensor data fusion algorithms that can synergistically combine defect related information from heterogeneous sensors used in gas pipeline inspection for reliably and accurately predicting the condition of the pipe-wall; and (2) To develop efficient data management techniques for signals obtained during multisensor interrogation of a gas pipeline. During this reporting period, Rowan University designed, developed and exercised algorithms for the effective management of data resulting from multi-sensor interrogation of gas transmission pipelines. Specifically, advanced visualization techniques were employed for immersive, interactive and navigable data representations.

  8. Response to FESAC survey, non-fusion connections to Fusion Energy Sciences. Applications of the FES-supported beam and plasma simulation code, Warp

    SciTech Connect (OSTI)

    Friedman, A.; Grote, D. P.; Vay, J. L.

    2015-05-29

    The Fusion Energy Sciences Advisory Committee’s subcommittee on non-fusion applications (FESAC NFA) is conducting a survey to obtain information from the fusion community about non-fusion work that has resulted from their DOE-funded fusion research. The subcommittee has requested that members of the community describe recent developments connected to the activities of the DOE Office of Fusion Energy Sciences. Two questions in particular were posed by the subcommittee. This document contains the authors’ responses to those questions.

  9. Cells with dysfunctional telomeres are susceptible to reactive oxygen species hydrogen peroxide via generation of multichromosomal fusions and chromosomal fragments bearing telomeres

    SciTech Connect (OSTI)

    Woo, Seon Rang; Department of Biochemistry, College of Medicine, Korea University, Seoul 136-705 ; Park, Jeong-Eun; Juhn, Kyoung-Mi; Ju, Yeun-Jin; Jeong, Jaemin; Kang, Chang-Mo; Yun, Hyun Jin; Yun, Mi Yong; Shin, Hyun-Jin; Joo, Hyun-Yoo; Park, Eun-Ran; Park, In-Chul; Hong, Sung Hee; Hwang, Sang-Gu; Kim, Haekwon; Cho, Myung-Haing; Kim, Sang Hoon; Park, Gil Hong; Lee, Kee-Ho

    2012-01-06

    Highlights: Black-Right-Pointing-Pointer Under conditions of telomere erosion, cells become extremely sensitive to H{sub 2}O{sub 2}. Black-Right-Pointing-Pointer Chromosomal regions adjacent to telomeres are cleaved by H{sub 2}O{sub 2} under such conditions. Black-Right-Pointing-Pointer H{sub 2}O{sub 2} thus causes multichromosomal fusions and generation of small chromosomal fragments. Black-Right-Pointing-Pointer N-acetylcysteine prevents H{sub 2}O{sub 2}-induced chromosomal aberrations. -- Abstract: During genotoxic stress, reactive oxygen species hydrogen peroxide (H{sub 2}O{sub 2}) is a prime mediator of the DNA damage response. Telomeres function both to assist in DNA damage repair and to inhibit chromosomal end-to-end fusion. Here, we show that telomere dysfunction renders cells susceptible to H{sub 2}O{sub 2}, via generation of multichromosomal fusion and chromosomal fragments. H{sub 2}O{sub 2} caused formation of multichromosomal end-to-end fusions involving more than three chromosomes, preferentially when telomeres were erosive. Interestingly, extensive chromosomal fragmentation (yielding small-sized fragments) occurred only in cells exhibiting such multichromosomal fusions. Telomeres were absent from fusion points, being rather present in the small fragments, indicating that H{sub 2}O{sub 2} cleaves chromosomal regions adjacent to telomeres. Restoration of telomere function or addition of the antioxidant N-acetylcysteine prevented development of chromosomal aberrations and rescued the observed hypersensitivity to H{sub 2}O{sub 2}. Thus, chromosomal regions adjacent to telomeres become sensitive to reactive oxygen species hydrogen peroxide when telomeres are dysfunctional, and are cleaved to produce multichromosomal fusions and small chromosomal fragments bearing the telomeres.

  10. Method to Exhaust Fusion-Product Tritons and Alpha Particles Rapidly from

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    D-3He Fueled FRC Fusion Reactors | Princeton Plasma Physics Lab Exhaust Fusion-Product Tritons and Alpha Particles Rapidly from D-3He Fueled FRC Fusion Reactors A method is described how to reduce neutron production from small D-3He burning FRC fusion reactors, thereby reducing the shielding required and allowing safer operation and less maintenance. No.: M-898

  11. An important challenge in magnetic fusion research is to obtain...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    control of edge transport barriers on Alcator C-Mod A crucial challenge in magnetic fusion is to obtain high energy confinement in a stationary plasma that is compatible with...

  12. Data fusion in neutron and X-ray computed tomography

    SciTech Connect (OSTI)

    Schrapp, Michael J.; Goldammer, Matthias; Schulz, Michael; Issani, Siraj; Bhamidipati, Suryanarayana; Bni, Peter

    2014-10-28

    We present a fusion methodology between neutron and X-ray computed tomography (CT). On the one hand, the inspection by X-ray CT of a wide class of multimaterials in non-destructive testing applications suffers from limited information of object features. On the other hand, neutron imaging can provide complementary data in such a way that the combination of both data sets fully characterizes the object. In this contribution, a novel data fusion procedure, called Fusion Regularized Simultaneous Algebraic Reconstruction Technique, is developed where the X-ray reconstruction is modified to fulfill the available data from the imaging with neutrons. The experiments, which were obtained from an aluminum profile containing a steel screw, and attached carbon fiber plates demonstrate that the image quality in CT can be significantly improved when the proposed fusion method is used.

  13. The Heavy Ion Fusion Program in the USA

    SciTech Connect (OSTI)

    Bangerter, R.O.

    2000-03-17

    The U.S. Department of Energy has established a new, larger inertial fusion energy program. To manage program growth, we have developed a new inertial fusion energy research and we have established a Virtual National Laboratory for Heavy Ion Fusion. There has been significant technical progress. Improvements in target design have reduced the predicted energy requirements by approximately a factor of two. There have also been important experiments on chamber dynamics and other inertial fusion technologies. The accelerator program has completed a number of small-scale experiments. Experiments with driver-scale beams are being designed -- including experiments with driver-scale ion sources and injectors. Finally we are developing the technologies needed to build a major research facility known as the Integrated Research Experiment (IRE)

  14. New tech could be "Mr. Fusion" for biofuel | Argonne National...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    convert waste from kitchens or latrines into an alcohol that can power diesel engines. New tech could be "Mr. Fusion" for biofuel By Else Tennessen * September 13, 2013 Tweet...

  15. U.S. Signs International Fusion Energy Agreement | Department...

    Broader source: Energy.gov (indexed) [DOE]

    Large-Scale, Clean Fusion Energy Project to Begin Construction PARIS, FRANCE - ... The U.S. is proud to be part of this partnership, and to join in the pursuit of nuclear ...

  16. Virtual-state internal nuclear fusion in metal lattices

    SciTech Connect (OSTI)

    Bussard, R.W. )

    1989-09-01

    A model of deuterium-deuterium (D-D) fusion in metal lattices is presented based on two phenomena: reactions between virtual-state pairs of deuterons bound by electrons of high effective mass m and deuterium energy upscattering by fast ions from fusion or tritium reactions with virtual-state nuclear structure groups in palladium nuclei. Since m is a decreasing function of deuterium ion bulk density n/sub 0/ the exponential barrier tunneling factor decreases rapidly with m. As a result, the fusion rate reaches a maximum at a loading density above zero but less than saturation. This can explain observations of transient neutron output from the (/sup 3/He,n) branch, of D-D fusion.

  17. Composite Multilinearity, Epistemic Uncertainty and Risk Achievement Worth

    SciTech Connect (OSTI)

    E. Borgonovo; C. L. Smith

    2012-10-01

    Risk Achievement Worth is one of the most widely utilized importance measures. RAW is defined as the ratio of the risk metric value attained when a component has failed over the base case value of the risk metric. Traditionally, both the numerator and denominator are point estimates. Relevant literature has shown that inclusion of epistemic uncertainty i) induces notable variability in the point estimate ranking and ii) causes the expected value of the risk metric to differ from its nominal value. We obtain the conditions under which the equality holds between the nominal and expected values of a reliability risk metric. Among these conditions, separability and state-of-knowledge independence emerge. We then study how the presence of epistemic uncertainty aspects RAW and the associated ranking. We propose an extension of RAW (called ERAW) which allows one to obtain a ranking robust to epistemic uncertainty. We discuss the properties of ERAW and the conditions under which it coincides with RAW. We apply our findings to a probabilistic risk assessment model developed for the safety analysis of NASA lunar space missions.

  18. Scientists discuss progress toward magnetic fusion energy at 2013 AAAS

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    annual meeting | Princeton Plasma Physics Lab Scientists discuss progress toward magnetic fusion energy at 2013 AAAS annual meeting February 21, 2013 Tweet Widget Google Plus One Share on Facebook Scientists participating in the worldwide effort to develop magnetic fusion energy for generating electricity gave progress reports to the 2013 annual meeting of the American Association for the Advancement of Science in Boston. Speaking were physicists George "Hutch" Neilson of the U.S.

  19. Sandia non-fusion R&D supported by FES.

    SciTech Connect (OSTI)

    Nygren, Richard E.

    2015-06-03

    Until 2012, Sandia participated regularly in non-fusion R&D that was supported primarily through our collaborations with companies in the DOE program for Small Business Innovative Research but also in some work-for-others contracts. In this work, funds were recovered from collaborating institutions for the staff time and materials used, but FES had supported the facility itself and in doing so enabled the contributions to the non-fusion R&D below.

  20. Fusion Nuclear Science and Technology Program - Status and Plans for

    Office of Environmental Management (EM)

    Tritium Research | Department of Energy Plans for Tritium Research Fusion Nuclear Science and Technology Program - Status and Plans for Tritium Research Presentation from the 34th Tritium Focus Group Meeting held in Idaho Falls, Idaho on September 23-25, 2014. PDF icon Fusion Nuclear Science and Technology Program - Status and Plans for Tritium Research More Documents & Publications Tritium Operation Improvements at the Idaho National Laboratory (INL) Safety and Tritium Applied Research

  1. The Bleeding 'Edge' of Fusion Research | Princeton Plasma Physics Lab

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    The Bleeding 'Edge' of Fusion Research By Oak Ridge National Laboratory March 20, 2014 Tweet Widget Google Plus One Share on Facebook Part of a visualization of turbulence spreading inward from the plasma edge. To watch the visualization, click the link at the end of the article. Part of a visualization of turbulence spreading inward from the plasma edge. To watch the visualization, click the link at the end of the article. Few problems have vexed physicists like fusion, the process by which

  2. Phil Heitzenroeder named winner of the 2013 Fusion Technology Award |

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Princeton Plasma Physics Lab Phil Heitzenroeder named winner of the 2013 Fusion Technology Award By John Greenwald April 30, 2013 Tweet Widget Google Plus One Share on Facebook Phil Heitzenroeder (Photo by Elle Starkman/PPPL Office of Communications) Phil Heitzenroeder Phil Heitzenroeder, who leads the Mechanical Engineering Division at the U.S. Department of Energy's Princeton Plasma Physics Laboratory (PPPL) and whose advice is sought by engineers around the world, has won the 2013 Fusion

  3. Highly Charged Ions in Magnetic Fusion Plasmas: Research Opportunities and

    Office of Scientific and Technical Information (OSTI)

    Diagnostic Necessities (Journal Article) | SciTech Connect Highly Charged Ions in Magnetic Fusion Plasmas: Research Opportunities and Diagnostic Necessities Citation Details In-Document Search Title: Highly Charged Ions in Magnetic Fusion Plasmas: Research Opportunities and Diagnostic Necessities Authors: Beiersdorfer, P Publication Date: 2014-12-12 OSTI Identifier: 1213663 Report Number(s): LLNL-JRNL-665610 DOE Contract Number: DE-AC52-07NA27344 Resource Type: Journal Article Resource

  4. Development of aerogel-lined targets for inertial confinement fusion

    Office of Scientific and Technical Information (OSTI)

    experiments (Thesis/Dissertation) | SciTech Connect Thesis/Dissertation: Development of aerogel-lined targets for inertial confinement fusion experiments Citation Details In-Document Search Title: Development of aerogel-lined targets for inertial confinement fusion experiments Authors: Braun, T Publication Date: 2013-03-05 OSTI Identifier: 1077169 Report Number(s): LLNL-TH-631353 DOE Contract Number: W-7405-ENG-48 Resource Type: Thesis/Dissertation Research Org: Lawrence Livermore National

  5. Dynamical dipole mode in fusion reactions with exotic nuclear beams

    SciTech Connect (OSTI)

    Baran, V.; Rizzo, C.; Colonna, M.; Toro, M. Di; Pierroutsakou, D.

    2009-02-15

    We report the properties of the prompt dipole radiation, produced via a collective bremsstrahlung mechanism, in fusion reactions with exotic beams. We show that the {gamma} yield is sensitive to the density dependence of the symmetry energy below/around saturation. Moreover, we find that the angular distribution of the emitted photons from such fast collective mode can represent a sensitive probe of its excitation mechanism and of fusion dynamics in the entrance channel.

  6. Electron Proton Hydrogen Deuterium Tritium Neutron Fusion Basics

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Proton Hydrogen Deuterium Tritium Neutron Fusion Basics Throughout history, the way in which the sun and stars produce their energy remained a mystery. During the 20th century, scientists discovered that the energy is produced through the fusion of light atoms. Albert Einstein's familiar formula, E=mc 2 , provided the basis for understanding that mass can be converted into energy. With fission, heavy atoms - such as uranium - can be split to release the internal energy that holds them together.

  7. Chuck Kessel Wins the 2015 Fusion Technology Award | Princeton Plasma

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Physics Lab Chuck Kessel Wins the 2015 Fusion Technology Award By Raphael Rosen July 9, 2015 Tweet Widget Google Plus One Share on Facebook Chuck Kessel (Photo by Elle Starkman/ PPPL Office of Communications) Chuck Kessel Gallery: Chuck Kessel Chuck Kessel Chuck Kessel Chuck Kessel Chuck Kessel, a principal engineer at the U.S. Department of Energy's Princeton Plasma Physics Laboratory (PPPL), has won the 2015 Fusion Technology Award. The honor, from the Institute of Electrical and

  8. FusionOctASCR2012c.pptx

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    and Challenges for Domain-Specific Languages in Fusion Applications Alice Koniges Lawrence Berkeley National Laboratory Exascale Research Conference Arlington, VA October, 2012 A Domain-Specific Language (DSL) for Fusion/Plasma Physics? * Understanding the field - Range of scales * Opinions in the field - Well, maybe a domain-aware library? - No thank you, we do fine with MPI, Fortran and our libraries for meshing and solvers - If we can design something it can save a lot of duplicative efforts

  9. International Atomic Energy Agency holds conference on fusion roadmap |

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Princeton Plasma Physics Lab International Atomic Energy Agency holds conference on fusion roadmap By John Greenwald November 8, 2012 Tweet Widget Google Plus One Share on Facebook Hutch Neilson, third from left, chaired the four-day International Atomic Energy Agency Conference at the University of California at Los Angeles in mid-October, which drew 70 participants from 16 countries and international groups. Pictured here from left to right are Keeman Kim, National Fusion Research

  10. COLLOQUIUM: Superconductors for Fusion for Next Ten Years | Princeton

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Plasma Physics Lab October 1, 2014, 4:00pm to 5:30pm Colloquia MBG Auditorium COLLOQUIUM: Superconductors for Fusion for Next Ten Years Professor David Larbalestier Florida State University - National High Magnetic Field Laboratory Present fusion devices requiring superconductors all use Nb-Ti or Nb3Sn. But conductors for high magnetic field use are undergoing a considerable development at present, especially devices that may be made with the high temperature cuprate superconductors,

  11. COLLOQUIUM: The Lockheed Martin Compact Fusion Reactor | Princeton Plasma

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Physics Lab August 6, 2015, 4:15pm to 6:30pm Colloquia MBG Auditorium COLLOQUIUM: The Lockheed Martin Compact Fusion Reactor Dr. Thomas McGuire Lockheed Martin Lockheed Martin Skunkworks is developing a compact fusion reactor concept, CFR. The novel magnetic cusp configuration would allow for stable plasmas in a geometry amenable to economical power plants and power sources. The details of the CFR configuration will be discussed along with a status of the current plasma confinement

  12. Lab Breakthrough: Fusion Research Leads to Antiterrorism Device |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy Fusion Research Leads to Antiterrorism Device Lab Breakthrough: Fusion Research Leads to Antiterrorism Device June 26, 2012 - 12:17pm Addthis Researchers at the Princeton Plasma Physics Laboratory developed an antiterrorism device that can detect and identify sources of dangerous radiation that could be used in a dirty bomb. See the other Lab Breakthrough videos on the YouTube playlist. Michael Hess Michael Hess Former Digital Communications Specialist, Office of Public

  13. NSTX Diagnostics for Fusion Plasma Science Studies

    SciTech Connect (OSTI)

    R. Kaita; D. Johnson; L. Roquemore; M. Bitter; F. Levinton; F. Paoletti; D. Stutman; and the NSTX Team

    2001-07-05

    This paper will discuss how plasma science issues are addressed by the diagnostics for the National Spherical Torus Experiment (NSTX), the newest large-scale machine in the magnetic confinement fusion (MCF) program. The development of new schemes for plasma confinement involves the interplay of experimental results and theoretical interpretations. A fundamental requirement, for example, is a determination of the equilibria for these configurations. For MCF, this is well established in the solutions of the Grad-Shafranov equation. While it is simple to state its basis in the balance between the kinetic and magnetic pressures, what they are as functions of space and time are often not easy to obtain. Quantities like the plasma pressure and current density are not directly measurable. They are derived from data that are themselves complex products of more basic parameters. The same difficulties apply to the understanding of plasma instabilities. Not only are the needs for spatial and temporal resolution more stringent, but the wave parameters which characterize the instabilities are difficult to resolve. We will show how solutions to the problems of diagnostic design on NSTX, and the physics insight the data analysis provides, benefits both NSTX and the broader scientific community.

  14. Fusion Power Demonstrations I and II

    SciTech Connect (OSTI)

    Doggett, J.N.

    1985-01-01

    In this report we present a summary of the first phase of the Fusion Power Demonstration (FPD) design study. During this first phase, we investigated two configurations, performed detailed studies of major components, and identified and examined critical issues. In addition to these design specific studies, we also assembled a mirror-systems computer code to help optimize future device designs. The two configurations that we have studied are based on the MARS magnet configuration and are labeled FPD-I and FPD-II. The FPD-I configuration employs the same magnet set used in the FY83 FPD study, whereas the FPD-II magnets are a new, much smaller set chosen to help reduce the capital cost of the system. As part of the FPD study, we also identified and explored issues critical to the construction of an Engineering Test Reactor (ETR). These issues involve subsystems or components, which because of their cost or state of technology can have a significant impact on our ability to meet FPD's mission requirements on the assumed schedule. General Dynamics and Grumman Aerospace studied two of these systems, the high-field choke coil and the halo pump/direct converter, in great detail and their findings are presented in this report.

  15. Inertially confined fusion using heavy ion drivers

    SciTech Connect (OSTI)

    Herrmannsfeldt, W.B.; Bangerter, R.O.; Bock, R.; Hogan, W.J.; Lindl, J.D.

    1991-10-01

    The various technical issues of HIF will be briefly reviewed in this paper. It will be seen that there are numerous areas in common in all the approaches to HIF. In the recent International Symposium on Heavy Ion Inertial Fusion, the attendees met in specialized workshop sessions to consider the needs for research in each area. Each of the workshop groups considered the key questions of this report: (1) Is this an appropriate time for international collaboration in HIF? (2) Which problems are most appropriate for such collaboration? (3) Can the sharing of target design information be set aside until other driver and systems issues are better resolved, by which time it might be supposed that there could be a relaxation of classification of target issues? (4) What form(s) of collaboration are most appropriate, e.g., bilateral or multilateral? (5) Can international collaboration be sensibly attempted without significant increases in funding for HIF? The authors of this report share the conviction that collaboration on a broad scale is mandatory for HIF to have the resources, both financial and personnel, to progress to a demonstration experiment. Ultimately it may be possible for a single driver with the energy, power, focusibility, and pulse shape to satisfy the needs of the international community for target physics research. Such a facility could service multiple experimental chambers with a variety of beam geometries and target concepts.

  16. Inertially confined fusion using heavy ion drivers

    SciTech Connect (OSTI)

    Herrmannsfeldt, W.B. ); Bangerter, R.O. ); Bock, R. ); Hogan, W.J.; Lindl, J.D. )

    1991-10-01

    The various technical issues of HIF will be briefly reviewed in this paper. It will be seen that there are numerous areas in common in all the approaches to HIF. In the recent International Symposium on Heavy Ion Inertial Fusion, the attendees met in specialized workshop sessions to consider the needs for research in each area. Each of the workshop groups considered the key questions of this report: (1) Is this an appropriate time for international collaboration in HIF (2) Which problems are most appropriate for such collaboration (3) Can the sharing of target design information be set aside until other driver and systems issues are better resolved, by which time it might be supposed that there could be a relaxation of classification of target issues (4) What form(s) of collaboration are most appropriate, e.g., bilateral or multilateral (5) Can international collaboration be sensibly attempted without significant increases in funding for HIF The authors of this report share the conviction that collaboration on a broad scale is mandatory for HIF to have the resources, both financial and personnel, to progress to a demonstration experiment. Ultimately it may be possible for a single driver with the energy, power, focusibility, and pulse shape to satisfy the needs of the international community for target physics research. Such a facility could service multiple experimental chambers with a variety of beam geometries and target concepts.

  17. Radiation resistant hydrogen microsensors for fusion applications.

    SciTech Connect (OSTI)

    Bastasz, Robert J.; Lemp, Thomas Kerr; Buchenauer, Dean A.; Whaley, Josh A.

    2010-11-01

    Quantifying the flux and energy of charge exchange neutrals to the walls of fusion experiments is important to understanding wall erosion and energy balance. Quantification of these fluxes is made much more difficult because they have very strong poloidal and toroidal variations. To facilitate such measurements, we have been developing compact, palladium metal oxide semiconductor (Pd-MOS) detectors. These devices are dosemetric detectors, which can evaluate differences between plasma discharges. To become widely used, however, such detectors must be made resistant to UV and x-ray induced damage, as well as high energy particle bombardment. We report here on the fabrication of Schottky diode Pd-MOS devices in which we have minimized the oxide thickness (to reduce the production of charges from UV and x-rays) and increased the Pd overlayer (to reduce charge production from high energy particles). The fabrication has been facilitated through use of an array of metallic posts to improve the Pd film adhesion. The efficacy of the film adhesion and comparison with standard detectors will be examined. Testing and calibration of the detectors is reported as a function of hydrogen flux and energy.

  18. Photo of the Week: The Mirror Fusion Test Facility | Department of Energy

    Energy Savers [EERE]

    Mirror Fusion Test Facility Photo of the Week: The Mirror Fusion Test Facility July 19, 2013 - 4:17pm Addthis This 1981 photo shows the Mirror Fusion Test Facility (MFTF), an experimental magnetic confinement fusion device built using a magnetic mirror at Lawrence Livermore National Laboratory (LLNL). The MFTF functioned as the primary research center for mirror fusion devices. The design consisted of a 64-meter-long vacuum vessel fitted with 26 coil magnets bonding the center of the vessel and

  19. A Pilot Plant: The Fastest Path to Commercial Fusion Energy

    SciTech Connect (OSTI)

    Robert J. Goldston

    2010-03-03

    Considerable effort has been dedicated to determining the possible properties of a magneticconfinement fusion power plant, particularly in the U.S.1, Europe2 and Japan3. There has also been some effort to detail the development path to fusion energy, particularly in the U.S.4 Only limited attention has been given, in Japan5 and in China6, to the options for a specific device to form the bridge from the International Thermonuclear Experimental Reactor, ITER, to commercial fusion energy. Nor has much attention been paid, since 2003, to the synergies between magnetic and inertial fusion energy development. Here we consider, at a very high level, the possibility of a Qeng ? 1 Pilot Plant, with linear dimensions ~ 2/3 the linear dimensions of a commercial fusion power plant, as the needed bridge. As we examine the R&D needs for such a system we find significant synergies between the needs for the development of magnetic and inertial fusion energy.

  20. Metering Best Practices: A Guide to Achieving Utility Resource...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Metering Best Practices: A Guide to Achieving Utility Resource Efficiency Metering Best Practices: A Guide to Achieving Utility Resource Efficiency Guide describes information...

  1. Technology Advances Needed for Photovoltaics to Achieve Widespread...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Technology Advances Needed for Photovoltaics to Achieve Widespread Grid Price Parity Technology Advances Needed for Photovoltaics to Achieve Widespread Grid Price Parity Abstract:...

  2. Dilute Clean Diesel Combustion Achieves Low Emissions and High...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Dilute Clean Diesel Combustion Achieves Low Emissions and High Efficiency While Avoiding Control Problems of HCCI Dilute Clean Diesel Combustion Achieves Low Emissions and High...

  3. Proceedings from the Wind Manufacturing Workshop: Achieving 20...

    Office of Environmental Management (EM)

    Proceedings from the Wind Manufacturing Workshop: Achieving 20% Wind Energy in the U.S. by 2030, May 2009 Proceedings from the Wind Manufacturing Workshop: Achieving 20% Wind...

  4. Washington, D.C. and Indiana: Allison Hybrid Technology Achieves...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Washington, D.C. and Indiana: Allison Hybrid Technology Achieves Commercial Success Washington, D.C. and Indiana: Allison Hybrid Technology Achieves Commercial Success August 21,...

  5. Advanced Mixed Waste Treatment Project Achieves Impressive Safety...

    Office of Environmental Management (EM)

    Advanced Mixed Waste Treatment Project Achieves Impressive Safety and Production Marks Advanced Mixed Waste Treatment Project Achieves Impressive Safety and Production Marks June ...

  6. Los Angeles County's Green Idea House Achieves Efficient Goals...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    County's Green Idea House Achieves Efficient Goals Los Angeles County's Green Idea House Achieves Efficient Goals Photo of an energy-efficient home with modern architecture. The ...

  7. Opening Remarks - Bob Cochran - Achieving Excellence in Management...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    - Achieving Excellence in Management and Operations Presentation from the 2015 DOE National Cleanup Workshop. PDF icon Opening Remarks - Bob Cochran - Achieving Excellence...

  8. Achievements of structural genomics (Conference) | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    Conference: Achievements of structural genomics Citation Details In-Document Search Title: Achievements of structural genomics You are accessing a document from the Department...

  9. Achievements of structural genomics (Journal Article) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: Achievements of structural genomics Citation Details In-Document Search Title: Achievements of structural genomics You are accessing a document from the...

  10. 3 Ways Solar Energy Programs Are Helping Achieve President Obama...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Solar Energy Programs Are Helping Achieve President Obama's Climate Goals 3 Ways Solar Energy Programs Are Helping Achieve President Obama's Climate Goals September 8, 2015 - ...

  11. Cook Composites and Polymers Company Achieves Superior Energy...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Cook Composites and Polymers Company Achieves Superior Energy Performance Gold Certification Cook Composites and Polymers Company Achieves Superior Energy Performance Gold ...

  12. EM's Defense Waste Processing Facility Achieves Waste Cleanup...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Defense Waste Processing Facility Achieves Waste Cleanup Milestone EM's Defense Waste Processing Facility Achieves Waste Cleanup Milestone January 14, 2016 - 12:10pm Addthis The...

  13. Building America Expert Meeting: Achieving the Best Installed...

    Energy Savers [EERE]

    Expert Meeting: Achieving the Best Installed Performance from High-Efficiency Residential Gas Furnaces Building America Expert Meeting: Achieving the Best Installed Performance...

  14. On the efficacy of imploding plasma liners for magnetized fusion target compression

    SciTech Connect (OSTI)

    Parks, P. B.

    2008-06-15

    A new theoretical model is formulated to study the idea of merging a spherical array of converging plasma jets to form a 'plasma liner' that further converges to compress a magnetized plasma target to fusion conditions [Y. C. F. Thio et al., 'Magnetized target fusion in a spheroidal geometry with standoff drivers', Current Trends in International Fusion Research II, edited by E. Panarella (National Research Council Canada, Ottawa, Canada, 1999)]. For a spherically imploding plasma liner shell with high initial Mach number (M=liner speed/sound speed) the rise in liner density with decreasing radius r goes as {rho}{approx}1/r{sup 2}, for any constant adiabatic index {gamma}=d ln p/d ln {rho}. Accordingly, spherical convergence amplifies the ram pressure of the liner on target by the factor A{approx}C{sup 2}, indicating strong coupling to its radial convergence C=r{sub m}/R, where r{sub m}(R)=jet merging radius (compressed target radius), and A=compressed target pressure/initial liner ram pressure. Deuterium-tritium (DT) plasma liners with initial velocity {approx}100 km/s and {gamma}=5/3, need to be hypersonic M{approx}60 and thus cold in order to realize values of A{approx}10{sup 4} necessary for target ignition. For optically thick DT liners, T<2 eV, n>10{sup 19}-10{sup 20} cm{sup -3}, blackbody radiative cooling is appreciable and may counteract compressional heating during the later stages of the implosion. The fluid then behaves as if the adiabatic index were depressed below 5/3, which in turn means that the same amplification A=1.6x10{sup 4} can be accomplished with a reduced initial Mach number M{approx_equal}12.7({gamma}-0.3){sup 4.86}, valid in the range (10fusion {alpha}-particle heating of the collapsed liner indicates that 'spark' ignition of the DT liner fuel does not appear to be possible for magnetized fusion targets with typical threshold values of areal density {rho}R<0.02 g cm{sup -2}.

  15. Cold nuclear fusion and muon-catalyzed fusion. (Latest citations from the INSPEC: Information services for the Physics and Engineering Communities data base). Published Search

    SciTech Connect (OSTI)

    Not Available

    1992-10-01

    The bibliography contains citations concerning a nuclear fusion process which occurs at lower temperatures and pressures than conventional fusion reactions. The references describe theoretical and experimental results for a proposed muon-catalyzed fusion reactor, and for studies on muon sticking and reactivation. The temperature dependence of fusion rates, and resolution of some engineering challenges are also discussed. (Contains 250 citations and includes a subject term index and title list.)

  16. Performance of a palladium membrane reactor using a Ni catalyst for fusion fuel impurities processing

    SciTech Connect (OSTI)

    Willm, R.S. [Los Alamos National Lab., NM (United States); Okuno, K. [Japan Atomic Energy Research Inst., Ibaraki-ken (Japan)

    1994-12-31

    The palladium membrane reactor (PMR) provides a means to recover hydrogen isotopes from impurities expected to be present in fusion reactor exhaust. This recovery is based on reactions such as water gas shift and steam reforming for which conversion is equilibrium limited. By including a selectively permeable membrane such as Pd/Ag in the catalyst bed, hydrogen isotopes can be removed from the reacting environment, thus promoting the reaction to complete conversion. Such a device has been built and operated at the Tritium Systems Test Assembly (TSTA) at Los Alamos National Laboratory (LANL). For the reactions listed above, earlier study with this unit has shown that hydrogen single-pass recoveries approaching 100% can be achieved. It was also determined that a nickel catalyst is a feasible choice for use with a PMR appropriate for fusion fuel impurities processing. The purpose of this study is to systematically assess the performance of the PMR using a nickel catalyst. Reactions which will be studied include the water gas shift reaction, steam reforming and methane cracking. Extended operation will be performed to detect performance degradation if it exists. The use of methane in these tests may lead to the formation of coke on the catalyst. Methods of removing the coke such as treatment with carbon dioxide or diluted oxygen will be examined.

  17. Performance of a palladium membrane reactor using a Ni catalyst for fusion fuel impurities processing

    SciTech Connect (OSTI)

    Willms, R.S.; Wilhelm, R. [Los Alamos National Lab., NM (United States); Okuno, K. [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

    1994-07-01

    The palladium membrane reactor (PNM) provides a means to recover hydrogen isotopes from impurities expected to be present in fusion reactor exhaust. This recovery is based on reactions such as water-gas shift and steam reforming for which conversion is equilibrium limited. By including a selectively permeable membrane such as Pd/Ag in the catalyst bed, hydrogen isotopes can be removed from the reacting environment, thus promoting the reaction to complete conversion. Such a device has been built and operated at the Tritium Systems Test Assembly (TSTA) at Los Alamos National Laboratory (LANL). For the reactions listed above, earlier study with this unit has shown that hydrogen single-pass recoveries approaching 100% can be achieved. It was also determined that a nickel catalyst is a feasible choice for use with a PMR appropriate for fusion fuel impurities processing. The purpose of this study was to systematically assess the performance of the PMR using a nickel catalyst over a range of temperatures, feed compositions and flowrates. Reactions which were studied are the water-gas shift reaction and steam reforming.

  18. Deuterium-Tritium Simulations of the Enhanced Reversed Shear Mode in the Tokamak Fusion Test Reactor

    SciTech Connect (OSTI)

    Mikkelsen, D.R.; Manickam, J.; Scott, S.D.; Zarnstorff

    1997-04-01

    The potential performance, in deuterium-tritium plasmas, of a new enhanced con nement regime with reversed magnetic shear (ERS mode) is assessed. The equilibrium conditions for an ERS mode plasma are estimated by solving the plasma transport equations using the thermal and particle dif- fusivities measured in a short duration ERS mode discharge in the Tokamak Fusion Test Reactor [F. M. Levinton, et al., Phys. Rev. Letters, 75, 4417, (1995)]. The plasma performance depends strongly on Zeff and neutral beam penetration to the core. The steady state projections typically have a central electron density of {approx}2:5x10 20 m{sup -3} and nearly equal central electron and ion temperatures of {approx}10 keV. In time dependent simulations the peak fusion power, {approx} 25 MW, is twice the steady state level. Peak performance occurs during the density rise when the central ion temperature is close to the optimal value of {approx} 15 keV. The simulated pressure profiles can be stable to ideal MHD instabilities with toroidal mode number n = 1, 2, 3, 4 and {infinity} for {beta}{sub norm} up to 2.5; the simulations have {beta}{sub norm} {le} 2.1. The enhanced reversed shear mode may thus provide an opportunity to conduct alpha physics experiments in conditions imilar to those proposed for advanced tokamak reactors.

  19. Alcator C-Mod Fusion Research Program

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    40 No. 6 (2000) 1251. 6. Hawryluk R., 1979 Proc. of Course in Physics of Plasmas close to Thermonuclear Conditions, (CEC, Brussels, 1980), Vol. 1, 19. 7. Ignat D.W. , Valeo E.J....

  20. Laser Intertial Fusion Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System

    SciTech Connect (OSTI)

    Kramer, K

    2010-04-08

    This study investigates the neutronics design aspects of a hybrid fusion-fission energy system called the Laser Fusion-Fission Hybrid (LFFH). A LFFH combines current Laser Inertial Confinement fusion technology with that of advanced fission reactor technology to produce a system that eliminates many of the negative aspects of pure fusion or pure fission systems. When examining the LFFH energy mission, a significant portion of the United States and world energy production could be supplied by LFFH plants. The LFFH engine described utilizes a central fusion chamber surrounded by multiple layers of multiplying and moderating media. These layers, or blankets, include coolant plenums, a beryllium (Be) multiplier layer, a fertile fission blanket and a graphite-pebble reflector. Each layer is separated by perforated oxide dispersion strengthened (ODS) ferritic steel walls. The central fusion chamber is surrounded by an ODS ferritic steel first wall. The first wall is coated with 250-500 {micro}m of tungsten to mitigate x-ray damage. The first wall is cooled by Li{sub 17}Pb{sub 83} eutectic, chosen for its neutron multiplication and good heat transfer properties. The {sub 17}Pb{sub 83} flows in a jacket around the first wall to an extraction plenum. The main coolant injection plenum is immediately behind the Li{sub 17}Pb{sub 83}, separated from the Li{sub 17}Pb{sub 83} by a solid ODS wall. This main system coolant is the molten salt flibe (2LiF-BeF{sub 2}), chosen for beneficial neutronics and heat transfer properties. The use of flibe enables both fusion fuel production (tritium) and neutron moderation and multiplication for the fission blanket. A Be pebble (1 cm diameter) multiplier layer surrounds the coolant injection plenum and the coolant flows radially through perforated walls across the bed. Outside the Be layer, a fission fuel layer comprised of depleted uranium contained in Tristructural-isotropic (TRISO) fuel particles having a packing fraction of 20% in 2 cm diameter fuel pebbles. The fission blanket is cooled by the same radial flibe flow that travels through perforated ODS walls to the reflector blanket. This reflector blanket is 75 cm thick comprised of 2 cm diameter graphite pebbles cooled by flibe. The flibe extraction plenum surrounds the reflector bed. Detailed neutronics designs studies are performed to arrive at the described design. The LFFH engine thermal power is controlled using a technique of adjusting the {sup 6}Li/{sup 7}Li enrichment in the primary and secondary coolants. The enrichment adjusts system thermal power in the design by increasing tritium production while reducing fission. To perform the simulations and design of the LFFH engine, a new software program named LFFH Nuclear Control (LNC) was developed in C++ to extend the functionality of existing neutron transport and depletion software programs. Neutron transport calculations are performed with MCNP5. Depletion calculations are performed using Monteburns 2.0, which utilizes ORIGEN 2.0 and MCNP5 to perform a burnup calculation. LNC supports many design parameters and is capable of performing a full 3D system simulation from initial startup to full burnup. It is able to iteratively search for coolant {sup 6}Li enrichments and resulting material compositions that meet user defined performance criteria. LNC is utilized throughout this study for time dependent simulation of the LFFH engine. Two additional methods were developed to improve the computation efficiency of LNC calculations. These methods, termed adaptive time stepping and adaptive mesh refinement were incorporated into a separate stand alone C++ library name the Adaptive Burnup Library (ABL). The ABL allows for other client codes to call and utilize its functionality. Adaptive time stepping is useful for automatically maximizing the size of the depletion time step while maintaining a desired level of accuracy. Adaptive meshing allows for analysis of fixed fuel configurations that would normally require a computationally burdensome number of depletion zones. Alternatively, Adaptive M

  1. Pellet ad pellet-blanket neutronics and photonics for electron beam fusion

    SciTech Connect (OSTI)

    Ragheb, M.M.H.; Moses, G.A.; Maynard, C.W.

    1980-04-01

    Pellet and coupled pellet-blanket time-integrated neutronics and photonics calculations are reported for a representative low-gain (25), low-compression (deuterium-tritium core pr = 9.4 kg/m/sup 2/) pellet design for an electron beam fusion reactor. Tungsten, lead, and natural uranium are compared as pusher-tamper materials. In the three cases, neutron balances show that neutron multiplication in the pellet compensates for the energy losses and spectral softening due to neutron interactions. Fissile breeding cannot be achieved in the natural uranium case, since the fission reaction predominates. Substantive additonal energy can be obtained (approx. 5.5 MeV/source neutron) in the pellet if natural uranium is used as the tamper material. Neutron and gamma spectra from the pellet microexplosions are given.

  2. A lower cost development path for heavy ion fusion

    SciTech Connect (OSTI)

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

    1993-05-19

    If two features of the inertial fusion process are exploited successfully, they can lead to significantly lower costs for demonstrating the feasibility of commercial electric power production from this source of energy. First, fusion capsule ignition and burn physics is independent of reaction chamber size and hydrodynamically-equivalent capsules can be designed to perform at small yield, exactly as they do at large yield. This means that an integrated test of all power plant components and feasibility tests of various reaction chamber concepts can be done at much smaller sizes (about 1--2 m first wall radius) and much lower powers (tens of MWs) than magnetic fusion development facilities such as ITER. Second, the driver, which is the most expensive component of currently conceived IFE development facilities, can be used to support more than one experiment target chamber/reactor (simultaneously and/or sequentially). These two factors lead to lower development facility costs, modular facilities, and the planning flexibility to spread costs over time or do several things in parallel and thus shorten the total time needed for development of Inertial Fusion Energy (IFE). In this paper the authors describe the general feature of a heavy ion fusion development plan that takes advantage of upgradable accelerators and the ability to test chambers and reactor systems at small scale in order to reduce development time and costs.

  3. FIREBALL: Fusion Ignition Rocket Engine with Ballistic Ablative Lithium Liner

    SciTech Connect (OSTI)

    Martin, Adam K.; Eskridge, Richard H.; Lee, Michael H.; Fimognari, Peter J.

    2006-01-20

    Thermo-nuclear fusion may be the key to a high Isp, high specific power propulsion system. In a fusion system energy is liberated within, and imparted directly to, the propellant. In principle, this can overcome the performance limitations inherent in systems that require thermal power transfer across a material boundary, and/or multiple power conversion stages (NTR, NEP). A thermo-nuclear propulsion system, which attempts to overcome some of the problems inherent in the Orion concept, is described. A dense FRC plasmoid is accelerated to high velocity (in excess of 500 km/s) and is compressed into a detached liner (pulse unit). The kinetic energy of the FRC is converted into thermal and magnetic-field energy, igniting a fusion burn in the magnetically confined plasma. The fusion reaction serves as an ignition source for the liner, which is made out of detonable materials. The energy liberated in this process is converted to thrust by a pusher-plate, as in the classic Orion concept. However with this concept, the vehicle does not carry a magazine of autonomous pulse-units. By accelerating a second, heavier FRC, which acts as a piston, right behind the first one, the velocity required to initiate the fusion burn is greatly reduced.

  4. Conditions and Requirements

    Broader source: Energy.gov [DOE]

    Conditions and requirements for Energy Efficiency and Renewable Energy (EERE) Postdoctoral Research Awards are spelled out below:

  5. Advanced fusion MHD power conversion using the CFAR (compact fusion advanced Rankine) cycle concept

    SciTech Connect (OSTI)

    Hoffman, M.A.; Campbell, R.; Logan, B.G.; Lawrence Livermore National Lab., CA )

    1988-10-01

    The CFAR (compact fusion advanced Rankine) cycle concept for a tokamak reactor involves the use of a high-temperature Rankine cycle in combination with microwave superheaters and nonequilibrium MHD disk generators to obtain a compact, low-capital-cost power conversion system which fits almost entirely within the reactor vault. The significant savings in the balance-of-plant costs are expected to result in much lower costs of electricity than previous concepts. This paper describes the unique features of the CFAR cycle and a high- temperature blanket designed to take advantage of it as well as the predicted performance of the MHD disk generators using mercury seeded with cesium. 40 refs., 8 figs., 3 tabs.

  6. Neutronics Design of a Thorium-Fueled Fission Blanket for LIFE (Laser Inertial Fusion-based Energy)

    SciTech Connect (OSTI)

    Powers, J; Abbott, R; Fratoni, M; Kramer, K; Latkowski, J; Seifried, J; Taylor, J

    2010-03-08

    The Laser Inertial Fusion-based Energy (LIFE) project at LLNL includes development of hybrid fusion-fission systems for energy generation. These hybrid LIFE engines use high-energy neutrons from laser-based inertial confinement fusion to drive a subcritical blanket of fission fuel that surrounds the fusion chamber. The fission blanket contains TRISO fuel particles packed into pebbles in a flowing bed geometry cooled by a molten salt (flibe). LIFE engines using a thorium fuel cycle provide potential improvements in overall fuel cycle performance and resource utilization compared to using depleted uranium (DU) and may minimize waste repository and proliferation concerns. A preliminary engine design with an initial loading of 40 metric tons of thorium can maintain a power level of 2000 MW{sub th} for about 55 years, at which point the fuel reaches an average burnup level of about 75% FIMA. Acceptable performance was achieved without using any zero-flux environment 'cooling periods' to allow {sup 233}Pa to decay to {sup 233}U; thorium undergoes constant irradiation in this LIFE engine design to minimize proliferation risks and fuel inventory. Vast reductions in end-of-life (EOL) transuranic (TRU) inventories compared to those produced by a similar uranium system suggest reduced proliferation risks. Decay heat generation in discharge fuel appears lower for a thorium LIFE engine than a DU engine but differences in radioactive ingestion hazard are less conclusive. Future efforts on development of thorium-fueled LIFE fission blankets engine development will include design optimization, fuel performance analysis work, and further waste disposal and nonproliferation analyses.

  7. Experimental Investigation of Ternary Alloys for Fusion Breeding Blankets

    SciTech Connect (OSTI)

    Choi, B. William; Chiu, Ing L.

    2015-10-26

    Future fusion power plants based on the deuterium-tritium (DT) fuel cycle will be required to breed the T fuel via neutron reactions with lithium, which will be incorporated in a breeding blanket that surrounds the fusion source. Recent work by LLNL proposed the used of liquid Li as the breeder in an inertial fusion energy (IFE) power plant. Subsequently, an LDRD was initiated to develop alternatives ternary alloy liquid metal breeders that have reduced chemical reactivity with water and air compared to pure Li. Part of the work plan was to experimentally investigate the phase diagrams of ternary alloys. Of particular interest was measurement of the melt temperature, which must be low enough to be compatible with the temperature limits of the steel used in the construction of the chamber and heat transfer system.

  8. INERTIAL FUSION DRIVEN BY INTENSE HEAVY-ION BEAMS

    SciTech Connect (OSTI)

    Sharp, W. M.; Friedman, A.; Grote, D. P.; Barnard, J. J.; Cohen, R. H.; Dorf, M. A.; Lund, S. M.; Perkins, L. J.; Terry, M. R.; Logan, B. G.; Bieniosek, F. M.; Faltens, A.; Henestroza, E.; Jung, J. Y.; Kwan, J. W.; Lee, E. P.; Lidia, S. M.; Ni, P. A.; Reginato, L. L.; Roy, P. K.; Seidl, P. A.; Takakuwa, J. H.; Vay, J.-L.; Waldron, W. L.; Davidson, R. C.; Gilson, E. P.; Kaganovich, I. D.; Qin, H.; Startsev, E.; Haber, I.; Kishek, R. A.; Koniges, A. E.

    2011-03-31

    Intense heavy-ion beams have long been considered a promising driver option for inertial-fusion energy production. This paper briefly compares inertial confinement fusion (ICF) to the more-familiar magnetic-confinement approach and presents some advantages of using beams of heavy ions to drive ICF instead of lasers. Key design choices in heavy-ion fusion (HIF) facilities are discussed, particularly the type of accelerator. We then review experiments carried out at Lawrence Berkeley National Laboratory (LBNL) over the past thirty years to understand various aspects of HIF driver physics. A brief review follows of present HIF research in the US and abroad, focusing on a new facility, NDCX-II, being built at LBNL to study the physics of warm dense matter heated by ions, as well as aspects of HIF target physics. Future research directions are briefly summarized.

  9. Modeling of Heat and Mass Transfer in Fusion Welding

    SciTech Connect (OSTI)

    Zhang, Wei [ORNL

    2011-01-01

    In fusion welding, parts are joined together by melting and subsequent solidification. Although this principle is simple, complex transport phenomena take place during fusion welding, and they determine the final weld quality and performance. The heat and mass transfer in the weld pool directly affect the size and shape of the pool, the solidification microstructure, the formation of weld defects such as porosity and humping, and the temperature distribution in the fusion zone and heat-affected zone (HAZ). Furthermore, the temperature evolution affects the kinetics and extent of various solid-state phase transformations, which in turn determine the final weld microstructure and mechanical properties. The formation of residual stresses and distortion originates from the thermal expansion and contraction during welding heating and cooling, respectively.

  10. Ab initio calculations of light-ion fusion reactions

    SciTech Connect (OSTI)

    Hupin, G.; Quaglioni, S.; Navratil, P.

    2012-10-20

    The exact treatment of nuclei starting from the constituent nucleons and the fundamental interactions among them has been a long-standing goal in nuclear physics. Above all nuclear scattering and reactions, which require the solution of the many-body quantum-mechanical problem in the continuum, represent an extraordinary theoretical as well as computational challenge for ab initio approaches. The ab initio No-Core Shell Model/Resonating-Group Method (NCSM/RGM) complements a microscopic cluster technique with the use of realistic interactions, and a microscopic and consistent description of the nucleon clusters. This approach is capable of describing simultaneously both bound and scattering states in light nuclei. Recent applications to light nuclei scattering and fusion reactions relevant to energy production in stars and Earth based fusion facilities, such as the deuterium-{sup 3}He fusion, are presented. Progress toward the inclusion of the three nucleon force into the formalism is outlined.

  11. Response of nickel surface to pulsed fusion plasma radiations

    SciTech Connect (OSTI)

    Niranjan, Ram Rout, R. K. Srivastava, R. Gupta, Satish C.; Chakravarthy, Y.; Patel, N. N.; Alex, P.

    2014-04-24

    Nickel based alloys are being projected as suitable materials for some components of the next generation fusion reactor because of compatible thermal, electrical and mechanical properties. Pure nickel material is tested here for possibility of similar application purpose. Nickel samples (> 99.5 % purity) are exposed here to plasma radiations produced due to D-D fusion reaction inside an 11.5 kJ plasma focus device. The changes in the physical properties of the nickel surface at microscopic level which in turn change the mechanical properties are analyzed using scanning electron microscope, optical microscope, glancing incident X-ray diffractometer and Vicker's hardness gauge. The results are reported here.

  12. Cryogenic system operating experience review for fusion applications

    SciTech Connect (OSTI)

    Cadwallader, L.C.

    1992-01-01

    This report presents a review of cryogenic system operating experiences, from particle accelerator, fusion experiment, space research, and other applications. Safety relevant operating experiences and accident information are discussed. Quantitative order-of-magnitude estimates of cryogenic component failure rates and accident initiating event frequencies are presented for use in risk assessment, reliability, and availability studies. Safety concerns with cryogenic systems are discussed, including ozone formation, effects of spills, and modeling spill behavior. This information should be useful to fusion system designers and safety analysts, such as the team working on the International Thermonuclear Experimental Reactor design.

  13. The use of water in a fusion power core

    SciTech Connect (OSTI)

    Tillack, M. S.; Humrickhouse, P. W.; Malang, S.; Rowcliffe, A. F.

    2015-02-01

    Water has both advantages and disadvantages as a coolant in conceptual designs of future fusion power plants. In the United States, water has not been chosen as a fusion power core coolant for decades. Researchers in other countries continue to adopt water in their designs, in some cases as the leading or sole candidate. In this article, we summarize the technical challenges resulting from the choice of water coolant and the differences in approach and assumptions that lead to different design decisions amongst researchers in this field.

  14. How Close Are We to Nuclear Fusion? | GE Global Research

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Close Are We to Nuclear Fusion? Click to email this to a friend (Opens in new window) Share on Facebook (Opens in new window) Click to share (Opens in new window) Click to share on LinkedIn (Opens in new window) Click to share on Tumblr (Opens in new window) How Close Are We to Nuclear Fusion? 2012.05.15 Chief Scientist Jim Bray discusses how light atoms combine to form heavy atoms and give off energy, and how we might harness this process for use outside of nuclear weaponry. 1 Comment Comment

  15. A fusion power plant without plasma-material interactions

    SciTech Connect (OSTI)

    Cohen, S.A.

    1997-04-01

    A steady-state fusion power plant is described which avoids the deleterious plasma-material interactions found in D-T fueled tokamaks. It is based on driven p-{sup 11}B fusion in a high-beta closed-field device, the field-reversed configuration (FRC), anchored in a gas-dynamic trap (GDT). The plasma outflow on the open magnetic-field lines is cooled by radiation in the GDT, then channeled through a magnetic nozzle, promoting 3-body recombination in the expansion region. The resulting supersonic neutral exhaust stream flows through a turbine, generating electricity.

  16. Fusion Peptides Promote Formation of Bilayer Cubic Phases in Lipid

    Office of Scientific and Technical Information (OSTI)

    Dispersions. An X-Ray Diffraction Study (Journal Article) | SciTech Connect SciTech Connect Search Results Journal Article: Fusion Peptides Promote Formation of Bilayer Cubic Phases in Lipid Dispersions. An X-Ray Diffraction Study Citation Details In-Document Search Title: Fusion Peptides Promote Formation of Bilayer Cubic Phases in Lipid Dispersions. An X-Ray Diffraction Study Authors: Tenchov, Boris G. ; MacDonald, Robert C. ; Lentz, Barry R. [1] ; UNC) [2] ; Sofia-MED) [2] + Show Author

  17. COLLOQUIUM: Fusion Rockets for Planetary Defense | Princeton Plasma Physics

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Lab 6, 2016, 4:15pm to 5:30pm MBG AUDITORIUM COLLOQUIUM: Fusion Rockets for Planetary Defense Dr. Glen Wurden Los Alamos National Laboratory Fusion rocket engines could enable a rapid response capability for deflecting an incoming comet, to prevent its impact on the planet Earth, in defense of our population, infrastructure, and civilization. The problem with long period comets is that they basically arrive to the inner solar system unannounced. If one were on a collision course with Earth,

  18. Superconducting focusing quadrupoles for heavy ion fusion experiments

    SciTech Connect (OSTI)

    Sabbi, G.L.; Faltens, A.; Leitner, M.; Lietzke, A.; Seidl, P.; Barnard, J.; Lund, S.; Martovetsky, N.; Gung, C.; Minervini, J.; Radovinsky, A.; Schultz, J.; Meinke, R.

    2003-05-01

    The Heavy Ion Fusion (HIF) Program is developing superconducting focusing magnets for both near-term experiments and future driver accelerators. In particular, single bore quadrupoles have been fabricated and tested for use in the High Current Experiment (HCX) at Lawrence Berkeley National Laboratory (LBNL). The next steps involve the development of magnets for the planned Integrated Beam Experiment (IBX) and the fabrication of the first prototype multi-beam focusing arrays for fusion driver accelerators. The status of the magnet R&D program is reported, including experimental requirements, design issues and test results.

  19. Role of hydrodynamic instability growth in hot-spot mass gain and fusion performance of inertial confinement fusion implosions

    SciTech Connect (OSTI)

    Srinivasan, Bhuvana; Tang, Xian-Zhu

    2014-10-15

    In an inertial confinement fusion target, energy loss due to thermal conduction from the hot-spot will inevitably ablate fuel ice into the hot-spot, resulting in a more massive but cooler hot-spot, which negatively impacts fusion yield. Hydrodynamic mix due to Rayleigh-Taylor instability at the gas-ice interface can aggravate the problem via an increased gas-ice interfacial area across which energy transfer from the hot-spot and ice can be enhanced. Here, this mix-enhanced transport effect on hot-spot fusion-performance degradation is quantified using contrasting 1D and 2D hydrodynamic simulations, and its dependence on effective acceleration, Atwood number, and ablation speed is identified.

  20. DOE's Ed Synakowski traces key discoveries in the quest for fusion...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    the quest for fusion energy By Jeanne Jackson DeVoe March 9, 2016 Tweet Widget Google Plus One Share on Facebook The DOE's Associate Director of Science for Fusion Energy ...