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1

Report of the FESAC Inertial Fusion Energy Review Panel  

SciTech Connect (OSTI)

This article is a response to the Office of Energy Research of the US DOE from the Fusion Energy Advisory Committee on a review of the Inertial Fusion Energy Program. This response was solicited in response to one of the suggestions made as part of the advisory report `A Restructured Fusion Energy Sciences Program` submitted to the US DOE in early 1996. The charge directed that the committee provide an assessment of the content of an inertial fusion energy program that advances the scientific elements of the program and is consistent with the Fusion Energy Sciences Program, and budget projections over the next several years.

Sheffield, J.; Abdou, M.; Briggs, R. [and others

1996-12-01T23:59:59.000Z

2

Journal of Fusion Energy, Vol. 18, No. 4, 1999 Report of the FEAC Inertial Fusion Energy Review Panel  

E-Print Network [OSTI]

participation in the of the Fusion Energy Sciences Program of the Office of International Thermonuclear ReactorJournal of Fusion Energy, Vol. 18, No. 4, 1999 Report of the FEAC Inertial Fusion Energy Review. S. Department of Energy Fusion Energy Advisory Committee (FEAC) review of its Inertial Fusion Energy

Abdou, Mohamed

3

Developing inertial fusion energy - Where do we go from here?  

SciTech Connect (OSTI)

Development of inertial fusion energy (IFE) will require continued R&D in target physics, driver technology, target production and delivery systems, and chamber technologies. It will also require the integration of these technologies in tests and engineering demonstrations of increasing capability and complexity. Development needs in each of these areas are discussed. It is shown how IFE development will leverage off the DOE Defense Programs funded inertial confinement fusion (ICF) work.

Meier, W.R.; Logan, G.

1996-06-11T23:59:59.000Z

4

Journal of Fusion Energy, Vol. 15, Nos. 3/4, 1996 Report of the FESAC Inertial Fusion Energy Review Panel  

E-Print Network [OSTI]

Journal of Fusion Energy, Vol. 15, Nos. 3/4, 1996 Report of the FESAC Inertial Fusion Energy Review on a specific recommendation made by your Committee in its report, "A Restructured Fusion Energy Sciences Pro Committee report of 1990, we had taken as our highest priority in inertial fusion energy the development

Abdou, Mohamed

5

Timely Delivery of Laser Inertial Fusion Energy Presentation prepared for  

E-Print Network [OSTI]

plant design · Delivery soon enough to make a difference to global energy imperatives. · Design basedTimely Delivery of Laser Inertial Fusion Energy Presentation prepared for Town Hall meeting must directly address the end-user requirement for commercial power 3 Plant Primary Criteria (partial

6

Chamber Design for the Laser Inertial Fusion Energy (LIFE) Engine  

SciTech Connect (OSTI)

The Laser Inertial Fusion Energy (LIFE) concept is being designed to operate as either a pure fusion or hybrid fusion-fission system. The present work focuses on the pure fusion option. A key component of a LIFE engine is the fusion chamber subsystem. It must absorb the fusion energy, produce fusion fuel to replace that burned in previous targets, and enable both target and laser beam transport to the ignition point. The chamber system also must mitigate target emissions, including ions, x-rays and neutrons and reset itself to enable operation at 10-15 Hz. Finally, the chamber must offer a high level of availability, which implies both a reasonable lifetime and the ability to rapidly replace damaged components. An integrated design that meets all of these requirements is described herein.

Latkowski, J F; Abbott, R P; Aceves, S; Anklam, T; Badders, D; Cook, A W; DeMuth, J; Divol, L; El-Dasher, B; Farmer, J C; Flowers, D; Fratoni, M; ONeil, R G; Heltemes, T; Kane, J; Kramer, K J; Kramer, R; Lafuente, A; Loosmore, G A; Morris, K R; Moses, G A; Olson, B; Pantano, C; Reyes, S; Rhodes, M; Roe, K; Sawicki, R; Scott, H; Spaeth, M; Tabak, M; Wilks, S

2010-11-30T23:59:59.000Z

7

ORIGINAL PAPER The Rationale for an Expanded Inertial Fusion Energy Program  

E-Print Network [OSTI]

ORIGINAL PAPER The Rationale for an Expanded Inertial Fusion Energy Program Stephen O. Dean for an expanded effort on the development of inertial fusion as an energy source is dis- cussed. It is argued that there should be a two-pronged, complementary approach to fusion energy development over the next two to three

8

Fusion Energy Advisory Committee (FEAC): Panel 7 report on Inertial Fusion Energy  

SciTech Connect (OSTI)

The charge to FEAC Panel 7 on inertial fusion energy (IFE) is encompassed in the four articles of correspondence. To briefly summarize, the scope of the panel`s review and analysis adhered to the following guidelines. (1) Consistent with previous recommendations by the Fusion Policy Advisory Committee (FPAC) and the National Academy of Science (NAS) panel on inertial fusion, the principal focus of FEAC Panel 7`s review and planning activities for next-generation experimental facilities in IFE was limited to heavy ions. (2) The panel considered the three budget cases: $5M, $10M, and $15M annual funding at constant level-of-effort (FY92 dollars), with a time horizon of about five years. (3) While limiting the analysis of next-generation experimental facilities to heavy ions, the panel assessed both the induction and rf linac approaches, and factored European plans into its considerations as well. (4) Finally, the panel identified high-priority areas in system studies and supporting IFE technologies, taking into account how IFE can benefit from related activities funded by the Office of Fusion Energy and by Defense Programs. This report presents the technical assessment, findings, and recommendations on inertial fusion energy prepared by FEAC Panel 7.

Davidson, R.; Ripin, B.; Abdou, M.; Baldwin, D.E.; Commisso, R.; Dean, S.O.; Herrmannsfeldt, W.; Lee, E.; Lindl, J.; McCrory, R. [Princeton Univ., NJ (United States)] [and others

1994-09-01T23:59:59.000Z

9

Rugged Packaging for Damage Resistant Inertial Fusion Energy Optics  

SciTech Connect (OSTI)

The development of practical fusion energy plants based on inertial confinement with ultraviolet laser beams requires durable, stable final optics that will withstand the harsh fusion environment. Aluminum-coated reflective surfaces are fragile, and require hard overcoatings resistant to contamination, with low optical losses at 248.4 nanometers for use with high-power KrF excimer lasers. This program addresses the definition of requirements for IFE optics protective coatings, the conceptual design of the required deposition equipment according to accepted contamination control principles, and the deposition and evaluation of diamondlike carbon (DLC) test coatings. DLC coatings deposited by Plasma Immersion Ion Processing were adherent and abrasion-resistant, but their UV optical losses must be further reduced to allow their use as protective coatings for IFE final optics. Deposition equipment for coating high-performance IFE final optics must be designed, constructed, and operated with contamination control as a high priority.

Stelmack, Larry

2003-11-17T23:59:59.000Z

10

Rep-Rated Target Injection for Inertial Fusion Energy  

SciTech Connect (OSTI)

Inertial Fusion Energy (IFE) with laser drivers is a pulsed power generation system that relies on repetitive, high-speed injection of targets into a fusion reactor. To produce an economically viable IFE power plant the targets must be injected into the reactor at a rate between 5 and 10 Hz.To survive the injection process, direct drive (laser fusion) targets (spherical capsules) are placed into protective sabots. The sabots separate from the target and are stripped off before entering the reactor chamber. Indirect drive (heavy ion fusion) utilizes a hohlraum surrounding the spherical capsule and enters the chamber as one piece.In our target injection demonstration system, the sabots or hohlraums are injected into a vacuum system with a light gas gun using helium as a propellant. To achieve pulsed operation a rep-rated injection system has been developed. For a viable power plant we must be able to fire continuously at 6 Hz. This demonstration system is currently set up to allow bursts of up to 12 targets at 6 Hz. Using the current system, tests have been successfully run with direct drive targets to show sabot separation under vacuum and at barrel exit velocities of {approx}400 m/s.The existing revolver system along with operational data will be presented.

Frey, D.T.; Goodin, D.T.; Stemke, R.W.; Petzoldt, R.W.; Drake, T.J.; Egli, W.; Vermillion, B.A.; Klasen, R.; Cleary, M.M

2005-05-15T23:59:59.000Z

11

Chamber technology concepts for inertial fusion energy: Three recent examples  

SciTech Connect (OSTI)

The most serious challenges in the design of chambers for inertial fusion energy (IFE) are 1) protecting the first wall from fusion energy pulses on the order of several hundred megajoules released in the form of x rays, target debris, and high energy neutrons, and 2) operating the chamber at a pulse repetition rate of 5-10 Hz (i.e., re-establishing, the wall protection and chamber conditions needed for beam propagation to the target between pulses). In meeting these challenges, designers have capitalized on the ability to separate the fusion burn physics from the geometry and environment of the fusion chamber. Most recent conceptual designs use gases or flowing liquids inside the chamber. Thin liquid layers of molten salt or metal and low pressure, high-Z gases can protect the first wall from x rays and target debris, while thick liquid layers have the added benefit of protecting structures from fusion neutrons thereby significantly reducing the radiation damage and activation. The use of thick liquid walls is predicted to 1) reduce the cost of electricity by avoiding the cost and down time of changing damaged structures, and 2) reduce the cost of development by avoiding the cost of developing a new, low-activation material. Various schemes have been proposed to assure chamber clearing and renewal of the protective features at the required pulse rate. Representative chamber concepts are described, and key technical feasibility issues are identified for each class of chamber. Experimental activities (past, current, and proposed) to address these issues and technology research and development needs are discussed.

Meier, W.R.; Moir, R.W. [Lawrence Livermore National Lab., CA (United States); Abdou, M.A. [California Univ., Los Angeles, CA (United States)

1997-02-27T23:59:59.000Z

12

Chamber and target technology development for inertial fusion energy  

SciTech Connect (OSTI)

Fusion chambers and high pulse-rate target systems for inertial fusion energy (IFE) must: regenerate chamber conditions suitable for target injection, laser propagation, and ignition at rates of 5 to 10 Hz; extract fusion energy at temperatures high enough for efficient conversion to electricity; breed tritium and fuel targets with minimum tritium inventory; manufacture targets at low cost; inject those targets with sufficient accuracy for high energy gain; assure adequate lifetime of the chamber and beam interface (final optics); minimize radioactive waste levels and annual volumes; and minimize radiation releases under normal operating and accident conditions. The primary goal of the US IFE program over the next four years (Phase I) is to develop the basis for a Proof-of-Performance-level driver and target chamber called the Integrated Research Experiment (IRE). The IRE will explore beam transport and focusing through prototypical chamber environment and will intercept surrogate targets at high pulse rep-rate. The IRE will not have enough driver energy to ignite targets, and it will be a non-nuclear facility. IRE options are being developed for both heavy ion and laser driven IFE. Fig. 1 shows that Phase I is prerequisite to an IRE, and the IRE plus NIF (Phase II) is prerequisite to a high-pulse rate. Engineering Test Facility and DEMO for IFE, leading to an attractive fusion power plant. This report deals with the Phase-I R&D needs for the chamber, driver/chamber interface (i.e., magnets for accelerators and optics for lasers), target fabrication, and target injection; it is meant to be part of a more comprehensive IFE development plan which will include driver technology and target design R&D. Because of limited R&D funds, especially in Phase I, it is not possible to address the critical issues for all possible chamber and target technology options for heavy ion or laser fusion. On the other hand, there is risk in addressing only one approach to each technology option. Therefore, in the following description of these specific feasibility issues, we try to strike a balance between narrowing the range of recommended R&D options to minimize cost, and keeping enough R&D options to minimize risk.

Abdou, M; Besenbruch, G; Duke, J; Forman, L; Goodin, D; Gulec, K; Hoffer, J; Khater, H; Kulcinsky, G; Latkowski, J F; Logan, B G; Margevicious, B; Meier, W R; Moir, R W; Morley, N; Nobile, A; Payne, S; Peterson, P F; Peterson, R; Petzoldt, R; Schultz, K; Steckle, W; Sviatoslavsky, L; Tillack, M; Ying, A

1999-04-07T23:59:59.000Z

13

Neutronics Assessment of Blanket Options for the HAPL Laser Inertial Fusion Energy Chamber  

E-Print Network [OSTI]

-cooled lithium blanket, a helium-cooled solid breeder blanket, and a dual-coolant lithium lead blanket of the reference blanket. Keywords-Laser fusion; lithium blanket; solid breeder; lithium lead; tritium breedingNeutronics Assessment of Blanket Options for the HAPL Laser Inertial Fusion Energy Chamber M

Raffray, A. Ren

14

Neutron imaging with bubble chambers for inertial confinement fusion.  

E-Print Network [OSTI]

??One of the main methods to obtain energy from controlled thermonuclear fusion is inertial confinement fusion (ICF), a process where nuclear fusion reactions are initiated (more)

Ghilea, Marian Constantin (1973 - ); Meyerhofer, David D.

2011-01-01T23:59:59.000Z

15

Grazing incidence liquid metal mirrors (GILMM) for radiation hardened final optics for laser inertial fusion energy power plants*  

E-Print Network [OSTI]

final optics in a laser inertial fusion energy (IFE) power plant. The amount of laser light the GILMM1 Grazing incidence liquid metal mirrors (GILMM) for radiation hardened final optics for laser inertial fusion energy power plants* R. W. Moir November 29, 1999 Lawrence Livermore National Laboratory

California at Los Angeles, University of

16

LANL | Physics | Inertial Confinement Fusion and High Energy Density  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFunInfraredJeffersonJonathanMultimaterial2Recovery Act JobPhysics Inertial

17

Experimental investigation of opacity models for stellar interior, inertial fusion, and high energy density plasmasa...  

E-Print Network [OSTI]

, Albuquerque, New Mexico, 87185-1196, USA 2 University of Nevada, Reno, Nevada 89557, USA 3 Lawrence Livermore for calculating energy transport in plasmas. In particular, understanding stellar interiors, inertial fusion more energy and the backlight must be bright enough to overwhelm the plasma self-emission

18

Heavy Ion Inertial Fusion Energy: Summaries of Program Elements  

SciTech Connect (OSTI)

The goal of the Heavy Ion Fusion (HIF) Program is to apply high-current accelerator technology to IFE power production. Ion beams of mass {approx}100 amu and kinetic energy {>=} 1 GeV provide efficient energy coupling into matter, and HIF enjoys R&D-supported favorable attributes of: (1) the driver, projected to be robust and efficient; see 'Heavy Ion Accelerator Drivers.'; (2) the targets, which span a continuum from full direct to full indirect drive (and perhaps fast ignition), and have metal exteriors that enable injection at {approx}10 Hz; see 'IFE Target Designs'; (3) the near-classical ion energy deposition in the targets; see 'Beam-Plasma Interactions'; (4) the magnetic final lens, robust against damage; see 'Final Optics-Heavy Ion Beams'; and (5) the fusion chamber, which may use neutronically-thick liquids; see 'Liquid-Wall Chambers.' Most studies of HIF power plants have assumed indirect drive and thick liquid wall protection, but other options are possible.

Friedman, A; Barnard, J J; Kaganovich, I; Seidl, P A; Briggs, R J; Faltens, A; Kwan, J W; Lee, E P; Logan, B G

2011-02-28T23:59:59.000Z

19

Utility of the US National Ignition Facility for development of inertial fusion energy  

SciTech Connect (OSTI)

The demonstration of inertial fusion ignition and gain in the proposed US National Ignition Facility (NIF), along with the parallel demonstration of the feasibility of an efficient, high-repetition-rate driver, would provide the basis for a follow-on Engineering Test Facility (ETF), a facility for integrated testing of the technologies needed for inertial fusion-energy (IFE) power plants. A workshop was convened at the University of California, Berkeley on February 22--24, 1994, attended by 61 participants from 17 US organizations, to identify possible NIF experiments relevant to IFE. We considered experiments in four IFE areas: Target physics, target chamber dynamics, fusion power ethnology, and target systems, as defined in the following sections.

Logan, B.G.; Anderson, A.T.; Tobin, M.T. [Lawrence Livermore National Lab., CA (United States); Schrock, V.E. [California Univ., Berkeley, CA (United States); Meier, W.R. [Schafer (W.J.) Associates, Inc., Livermore, CA (United States); Bangerter, R.O. [Lawrence Berkeley Lab., CA (United States); Tokheim, R.E. [SRI International, Menlo Park, CA (United States). Poulter Lab.; Abdou, M.A. [California Univ., Los Angeles, CA (United States); Schultz, K.R. [General Atomics, San Diego, CA (United States)

1994-08-01T23:59:59.000Z

20

Z-inertial fusion energy: power plant final report FY 2006.  

SciTech Connect (OSTI)

This report summarizes the work conducted for the Z-inertial fusion energy (Z-IFE) late start Laboratory Directed Research Project. A major area of focus was on creating a roadmap to a z-pinch driven fusion power plant. The roadmap ties ZIFE into the Global Nuclear Energy Partnership (GNEP) initiative through the use of high energy fusion neutrons to burn the actinides of spent fuel waste. Transmutation presents a near term use for Z-IFE technology and will aid in paving the path to fusion energy. The work this year continued to develop the science and engineering needed to support the Z-IFE roadmap. This included plant system and driver cost estimates, recyclable transmission line studies, flibe characterization, reaction chamber design, and shock mitigation techniques.

Anderson, Mark (University of Wisconsin, Madison, WI); Kulcinski, Gerald (University of Wisconsin, Madison, WI); Zhao, Haihua (University of California, Berkeley, CA); Cipiti, Benjamin B.; Olson, Craig Lee; Sierra, Dannelle P.; Meier, Wayne (Lawrence Livermore National Laboratories); McConnell, Paul E.; Ghiaasiaan, M. (Georgia Institute of Technology, Atlanta, GA); Kern, Brian (Georgia Institute of Technology, Atlanta, GA); Tajima, Yu (University of California, Los Angeles, CA); Campen, Chistopher (University of California, Berkeley, CA); Sketchley, Tomas (University of California, Los Angeles, CA); Moir, R (Lawrence Livermore National Laboratories); Bardet, Philippe M. (University of California, Berkeley, CA); Durbin, Samuel; Morrow, Charles W.; Vigil, Virginia L (University of Wisconsin, Madison, WI); Modesto-Beato, Marcos A.; Franklin, James Kenneth (University of California, Berkeley, CA); Smith, James Dean; Ying, Alice (University of California, Los Angeles, CA); Cook, Jason T.; Schmitz, Lothar (University of California, Los Angeles, CA); Abdel-Khalik, S. (Georgia Institute of Technology, Atlanta, GA); Farnum, Cathy Ottinger; Abdou, Mohamed A. (University of California, Los Angeles, CA); Bonazza, Riccardo (University of Wisconsin, Madison, WI); Rodriguez, Salvador B.; Sridharan, Kumar (University of Wisconsin, Madison, WI); Rochau, Gary Eugene; Gudmundson, Jesse (University of Wisconsin, Madison, WI); Peterson, Per F. (University of California, Berkeley, CA); Marriott, Ed (University of Wisconsin, Madison, WI); Oakley, Jason (University of Wisconsin, Madison, WI)

2006-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Impact of pulsed irradiation upon neutron activation calculations for inertial and magnetic fusion energy power plants  

SciTech Connect (OSTI)

Sisolak et al. defined two methods for the approximation of pulsed irradiation: the steady-state (SS) and the equivalent steady-state (ESS) methods. Both methods have been shown to greatly simplify the process of calculating radionuclide inventories. However, they are not accurate when applied to magnetic fusion energy (MFF) and inertial fusion energy (IFE) experimental facilities. In the work reported here, an attempt has been made to evaluate the accuracy of the SS and ESS methods as they might be applied to typical MFE and IFE power plants. 18 refs., 6 figs.

Latkowski, J.F. [Lawrence Livermore National Lab., CA (United States); Sanz, J. [Universidad Politecnica de Madrid (Spain); Vujic, J.L. [Univ. of California, Berkeley, CA (United States)

1996-12-31T23:59:59.000Z

22

Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

E-Print Network [OSTI]

of Con- trolled Nuclear Fusion, CONF-760975-P3, pages 1061more effective solution, nuclear fusion. Fission Energy Thethe development of nuclear fusion weapons, humankind has

Kramer, Kevin James

2010-01-01T23:59:59.000Z

23

The role of the NIF in the development of inertial fusion energy  

SciTech Connect (OSTI)

Recent decisions by DOE to proceed with the National Ignition Facility (NIF) and the first half of the Induction Systems Linac Experiments (ILSE) can provide the scientific basis for inertial fusion ignition and high-repetition heavy-ion driver physics, respectively. Both are critical to Inertial Fusion Energy (IFE). A conceptual design has been completed for a 1.8-MJ, 500-TW, 0.35-{micro}m-solid-state laser system, the NIF. The NIF will demonstrate inertial fusion ignition and gain for national security applications, and for IFE development. It will support science applications using high-power lasers. The demonstration of inertial fusion ignition and gain, along with the parallel demonstration of the feasibility of an efficient, high-repetition-rate driver, would provide the basis for a follow-on Engineering Test Facility (ETF) identified in the National Energy Policy Act of 1992. The ETF would provide an integrated testbed for the development and demonstration of the technologies needed for IFE power plants. In addition to target physics of ignition, the NIF will contribute important data on IFE target chamber issues, including neutron damage, activation, target debris clearing, operational experience in many areas prototypical to future IFE power plants, and an opportunity to provide tests of candidate low-cost IFE targets and injection systems. An overview of the NIF design and the target area environments relevant to conducting IFE experiments are described in Section 2. In providing this basic data for IFE, the NIF will provide confidence that an ETF can be successful in the integration of drivers, target chambers, and targets for IFE.

Logan, B.G.

1995-03-16T23:59:59.000Z

24

Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

E-Print Network [OSTI]

aspects of a hybrid fusion-fission energy system called theof a Hybrid Fusion-Fission Nuclear Energy System by Kevinof a Hybrid Fusion-Fission Nuclear Energy System by Kevin

Kramer, Kevin James

2010-01-01T23:59:59.000Z

25

TIMELY DELIVERY OF LASER INERTIAL FUSION ENERGY (LIFE)  

SciTech Connect (OSTI)

The National Ignition Facility (NIF), the world's largest and most energetic laser system, is now operational at Lawrence Livermore National Laboratory. A key goal of the NIF is to demonstrate fusion ignition for the first time in the laboratory. Its flexibility allows multiple target designs (both indirect and direct drive) to be fielded, offering substantial scope for optimization of a robust target design. In this paper we discuss an approach to generating gigawatt levels of electrical power from a laser-driven source of fusion neutrons based on these demonstration experiments. This 'LIFE' concept enables rapid time-to-market for a commercial power plant, assuming success with ignition and a technology demonstration program that links directly to a facility design and construction project. The LIFE design makes use of recent advances in diode-pumped, solid-state laser technology. It adopts the paradigm of Line Replaceable Units utilized on the NIF to provide high levels of availability and maintainability and mitigate the need for advanced materials development. A demonstration LIFE plant based on these design principles is described, along with the areas of technology development required prior to plant construction. A goal-oriented, evidence-based approach has been proposed to allow LIFE power plant rollout on a time scale that meets policy imperatives and is consistent with utility planning horizons. The system-level delivery builds from our prior national investment over many decades and makes full use of the distributed capability in laser technology, the ubiquity of semiconductor diodes, high volume manufacturing markets, and U.S. capability in fusion science and nuclear engineering. The LIFE approach is based on the ignition evidence emerging from NIF and adopts a line-replaceable unit approach to ensure high plant availability and to allow evolution from available technologies and materials. Utilization of a proven physics platform for the ignition scheme is an essential component of an acceptably low-risk solution. The degree of coupling seen on NIF between driver and target performance mandates that little deviation be adopted from the NIF geometry and beamline characteristics. Similarly, the strong coupling between subsystems in an operational power plant mandates that a self-consistent solution be established via an integrated facility delivery project. The benefits of separability of the subsystems within an IFE plant (driver, chamber, targets, etc.) emerge in the operational phase of a power plant rather than in its developmental phase. An optimized roadmap for IFE delivery needs to account for this to avoid nugatory effort and inconsistent solutions. For LIFE, a system design has been established that could lead to an operating power plant by the mid-2020s, drawing from an integrated subsystem development program to demonstrate the required technology readiness on a time scale compatible with the construction plan. Much technical development work still remains, as does alignment of key stakeholder groups to this newly emerging development option. If the required timeline is to be met, then preparation of a viable program is required alongside the demonstration of ignition on NIF. This will enable timely analysis of the technical and economic case and establishment of the appropriate delivery partnership.

Dunne, A M

2010-11-30T23:59:59.000Z

26

Pathways to Inertial Fusion Energy Laser Direct Drive  

E-Print Network [OSTI]

(NRL) Smoothing by Spectral Dispersion ­ SSD (LLE) DT ice preheated ablator (lower density) DT ice/sec), and ignited by a converging shock produced by high intensity spike in the laser pulse. * R. Betti et al., Phys. Shock ignited target #12;The target has to release enough energy to power the reactor... AND produce

27

Summary of Assessment of Prospects for Inertial Fusion Energy | Princeton  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassiveSubmittedStatus TomAbout »Lab (NewportSuccess Stories T E C H TPlasma Physics

28

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

SciTech Connect (OSTI)

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.

Latkowski, J.F.

1996-11-01T23:59:59.000Z

29

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

SciTech Connect (OSTI)

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.

Moses, E

2011-03-25T23:59:59.000Z

30

The National Ignition Facility and the Promise of Inertial Fusion Energy  

SciTech Connect (OSTI)

The National Ignition Facility (NIF) at the Lawrence Livermore National Laboratory (LLNL) in Livermore, CA, is now operational. The NIF is the world's most energetic laser system capable of producing 1.8 MJ and 500 TW of ultraviolet light. 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 planetary interiors and stellar environments. On September 29, 2010, the first integrated ignition experiment was conducted, demonstrating the successful coordination of the laser, cryogenic target system, array of diagnostics and infrastructure required for ignition demonstration. In light of this strong progress, the U.S. and international communities are examining the implication of NIF ignition for inertial fusion energy (IFE). A laser-based IFE power plant will require a repetition rate of 10-20 Hz and a laser with 10% electrical-optical efficiency, as well as further development and advances in large-scale target fabrication, target injection, and other supporting technologies. These capabilities could lead to a prototype IFE demonstration plant in the 10- to 15-year time frame. LLNL, in partnership with other institutions, is developing a Laser Inertial Fusion Engine (LIFE) concept and examining in detail various technology choices, as well as the advantages of both pure fusion and fusion-fission schemes. This paper will describe the unprecedented experimental capabilities of the NIF and the results achieved so far on the path toward ignition. The paper will conclude with a discussion about the need to build on the progress on NIF to develop an implementable and effective plan to achieve the promise of LIFE as a source of carbon-free energy.

Moses, E I

2010-12-13T23:59:59.000Z

31

Recyclable transmission line concept for z-pinch driven inertial fusion energy.  

SciTech Connect (OSTI)

Recyclable transmission lines (RTL)s are being studied as a means to repetitively drive z pinches to generate fusion energy. We have shown previously that the RTL mass can be quite modest. Minimizing the RTL mass reduces recycling costs and the impulse delivered to the first wall of a fusion chamber. Despite this reduction in mass, a few seconds will be needed to reload an RTL after each subsequent shot. This is in comparison to other inertial fusion approaches that expect to fire up to ten capsules per second. Thus a larger fusion yield is needed to compensate for the slower repetition rate in a z-pinch driven fusion reactor. We present preliminary designs of z-pinch driven fusion capsules that provide an adequate yield of 1-4 GJ. We also present numerical simulations of the effect of these fairly large fusion yields on the RTL and the first wall of the reactor chamber. These simulations were performed with and without a neutron absorbing blanket surrounding the fusion explosion. We find that the RTL will be fully vaporized out to a radius of about 3 meters assuming normal incidence. However, at large enough radius the RTL will remain in either the liquid or solid state and this portion of the RTL could fragment and become shrapnel. We show that a dynamic fragmentation theory can be used to estimate the size of these fragmented particles. We discuss how proper design of the RTL can allow this shrapnel to be directed away from the sensitive mechanical parts of the reactor chamber.

De Groot, J. S. (University of California, Davis, CA); Olson, Craig Lee; Cochrane, Kyle Robert (Ktech Corporation, Albuquerque, NM); Slutz, Stephen A.; Vesey, Roger Alan; Peterson, Per F. (University of California, Berkeley, CA)

2003-12-01T23:59:59.000Z

32

Achieving competitive excellence in nuclear energy: The threat of proliferation; the challenge of inertial confinement fusion  

SciTech Connect (OSTI)

Nuclear energy will have an expanding role in meeting the twenty-first-century challenges of population and economic growth, energy demand, and global warming. These great challenges are non-linearly coupled and incompletely understood. In the complex global system, achieving competitive excellence for nuclear energy is a multi-dimensional challenge. The growth of nuclear energy will be driven by its margin of economic advantage, as well as by threats to energy security and by growing evidence of global warming. At the same time, the deployment of nuclear energy will be inhibited by concerns about nuclear weapons proliferation, nuclear waste and nuclear reactor safety. These drivers and inhibitors are coupled: for example, in the foreseeable future, proliferation in the Middle East may undermine energy security and increase demand for nuclear energy. The Department of Energy`s nuclear weapons laboratories are addressing many of these challenges, including nuclear weapons builddown and nonproliferation, nuclear waste storage and burnup, reactor safety and fuel enrichment, global warming, and the long-range development of fusion energy. Today I will focus on two major program areas at the Lawrence Livermore National Laboratory (LLNL): the proliferation of nuclear weapons and the development of inertial confinement fusion (ICF) energy.

Nuckolls, J.H.

1994-06-01T23:59:59.000Z

33

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

SciTech Connect (OSTI)

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.

Thio, Francis Y.C.

2008-01-01T23:59:59.000Z

34

Progress in heavy ion driven inertial fusion energy: From scaledexperiments to the integrated research experiment  

SciTech Connect (OSTI)

The promise of inertial fusion energy driven by heavy ion beams requires the development of accelerators that produce ion currents ({approx}100s Amperesheam) and ion energies ({approx}1-10 GeV) that have not been achieved simultaneously in any existing accelerator. The high currents imply high generalized perveances, large tune depressions. and high space charge potentials of the beam center relative to the beam pipe. Many of the scientific issues associated with ion beams of high perveance and large tune depression have been addressed over the last two decades on scaled experiments at Lawrence Berkeley and Lawrence Livermore National Laboratories, the University of Maryland, and elsewhere. The additional requirement of high space charge potential (or equivalently high line charge density) gives rise to effects (particularly the role of electrons in beam transport) which must be understood before proceeding to a large scale accelerator. The first phase of a new series of experiments in Heavy Ion Fusion Virtual National Laboratory (HIF VNL), the High Current Experiments (HCX), is now being constructed at LBNL. The mission of the HCX will be to transport beams with driver line charge density so as to investigate the physics of this regime, including constraints on the maximum radial filling factor of the beam through the pipe. This factor is important for determining both cost and reliability of a driver scale accelerator. The HCX will provide data for design of the next steps in the sequence of experiments leading to an inertial Fusion energy power plant. The focus of the program after the HCX will be on integration of all of the manipulations required for a driver. In the near term following HCX, an Integrated Beam Experiment (IBX) of the same general scale as the HCX is envisioned.

Barnard, J.J.; Ahle, L.E.; Baca, D.; Bangerter, R.O.; Bieniosek,F.M.; Celata, C.M.; Chacon-Golcher, E.; Davidson, R.C.; Faltens, A.; Friedman, A.; Franks, R.M.; Grote, D.P.; Haber, I.; Henestroza, E.; deHoon, M.J.L.; Kaganovich, I.; Karpenko, V.P.; Kishek, R.A.; Kwan, J.W.; Lee, E.P.; Logan, B.G.; Lund, S.M.; Meier, W.R.; Molvik, A.W.; Olson, C.; Prost, L.R.; Qin, H.; Rose, D.; Sabbi, G-L.; Sangster, T.C.; Seidl, P.A.; Sharp, W.M.; Shuman, D.; Vay, J.L.; Waldron, W.L.; Welch, D.; Yu, S.S.

2001-06-22T23:59:59.000Z

35

Fusion Power Associates Fusion Energy Sciences Program  

E-Print Network [OSTI]

experiments ­ Further work on inertial fusion energy technology ­ Take advantage of opportunities in HEDP on several smaller experiments ­ Further work on inertial fusion energy technology · Focus IFE first wall

36

Annular Vortex Generation for Inertial Fusion Energy Beam-Line Protection  

SciTech Connect (OSTI)

The use of swirling annular vortex flow inside beam entrance tubes can protect beam-line structural materials in chambers for heavy-ion inertial fusion energy (IFE) applications. An annular wall jet, or vortex tube, is generated by injecting liquid tangent to the inner surface of a tube wall with both axially and azimuthally directed velocity components. A layer of liquid then lines the beam tube wall, which may improve the effectiveness of neutron shielding, and condenses and removes vaporized coolant that may enter the beam tubes. Vortex tubes have been constructed and tested with a thickness of three-tenths the pipe radius. Analysis of the flow is given, along with experimental examples of vortex tube fluid mechanics and an estimate of the layer thickness, based on simple mass conservation considerations.

Pemberton, Steven J.; Abbott, Ryan P.; Peterson, Per F. [University of California (United States)

2003-05-15T23:59:59.000Z

37

Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

E-Print Network [OSTI]

Example of NIF fusion target hohlraum with multiple beamsimilar to those used on NIF. . . . . Overview of LFFHNES Nuclear Energy System NIF National Ignition Facility ODS

Kramer, Kevin James

2010-01-01T23:59:59.000Z

38

Survey of Laser Markets Relevant to Inertial Fusion Energy Drivers, information for National Research Council  

SciTech Connect (OSTI)

Development of a new technology for commercial application can be significantly accelerated by leveraging related technologies used in other markets. Synergies across multiple application domains attract research and development (R and D) talent - widening the innovation pipeline - and increases the market demand in common components and subsystems to provide performance improvements and cost reductions. For these reasons, driver development plans for inertial fusion energy (IFE) should consider the non-fusion technology base that can be lveraged for application to IFE. At this time, two laser driver technologies are being proposed for IFE: solid-state lasers (SSLs) and KrF gas (excimer) lasers. This document provides a brief survey of organizations actively engaged in these technologies. This is intended to facilitate comparison of the opportunities for leveraging the larger technical community for IFE laser driver development. They have included tables that summarize the commercial organizations selling solid-state and KrF lasers, and a brief summary of organizations actively engaged in R and D on these technologies.

Bayramian, A J; Deri, R J; Erlandson, A C

2011-02-24T23:59:59.000Z

39

Diode-pumped solid-state laser driver experiments for inertial fusion energy applications  

SciTech Connect (OSTI)

Although solid-state lasers have been the primary means by which the physics of inertial confinement fusion (ICF) have been investigated, it was previously thought that solid-state laser technology could not offer adequate efficiencies for an inertial fusion energy (IFE) power plant. Orth and co-workers have recently designed a conceptual IFE power plant, however, with a high efficiency diode-pumped solid-state laser (DPSSL) driver that utilized several recent innovations in laser technology. It was concluded that DPSSLs could offer adequate performance for IFE with reasonable assumptions. This system was based on a novel diode pumped Yb-doped Sr{sub 5}(PO{sub 4}){sub 3}F (Yb:S-FAP) amplifier. Because this is a relatively new gain medium, a project was established to experimentally validate the diode-pumping and extraction dynamics of this system at the smallest reasonable scale. This paper reports on the initial experimental results of this study. We found the pumping dynamics and extraction cross-sections of Yb:S-FAP crystals to be similar to those previously inferred by purely spectroscopic techniques. The saturation fluence for pumping was measured to be 2.2 J/cm{sup 2} using three different methods based on either the spatial, temporal, or energy transmission properties of a Yb:S-FAP rod. The small signal gain implies an emission cross section of 6.0{times}10{sup {minus}20} cm{sup 2}. Up to 1.7 J/cm{sup 3} of stored energy density was achieved in a 6{times}6{times}44 mm{sup 3} Yb:S-FAP amplifier rod. In a free running configuration diode-pumped slope efficiencies up to 43% were observed with output energies up to {approximately}0.5 J per 1 ms pulse from a 3{times}3{times}30 mm{sup 3} rod. When the rod was mounted in a copper block for cooling, 13 W of average power was produced with power supply limited operation at 70 Hz with 500 {mu}s pulses.

Marshall, C.D.; Payne, S.A.; Emanuel, M.E.; Smith, L.K.; Powell, H.T.; Krupke, W.F.

1995-07-11T23:59:59.000Z

40

Hydrodynamic stability theory of double ablation front structures in inertial confinement fusion.  

E-Print Network [OSTI]

??The aim of inertial confinement fusion is the production of energy by the fusion of thermonuclear fuel (deuterium-tritium) enclosed in a spherical target due to (more)

Yez Vico, Carlos

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Ion Fast Ignition-Establishing a Scientific Basis for Inertial Fusion Energy --- Final Report  

SciTech Connect (OSTI)

The Fast Ignition (FI) Concept for Inertial Confinement Fusion (ICF) has the potential to provide a significant advance in the technical attractiveness of Inertial Fusion Energy reactors. FI differs from conventional ?central hot spot? (CHS) target ignition by decoupling compression from heating: using a laser (or heavy ion beam or Z pinch) drive pulse (10?s of nanoseconds) to create a dense fuel and a second, much shorter (~10 picoseconds) high intensity pulse to ignite a small volume within the dense fuel. The compressed fuel is opaque to laser light. The ignition laser energy must be converted to a jet of energetic charged particles to deposit energy in the dense fuel. The original concept called for a spray of laser-generated hot electrons to deliver the energy; lack of ability to focus the electrons put great weight on minimizing the electron path. An alternative concept, proton-ignited FI, used those electrons as intermediaries to create a jet of protons that could be focused to the ignition spot from a more convenient distance. Our program focused on the generation and directing of the proton jet, and its transport toward the fuel, none of which were well understood at the onset of our program. We have developed new experimental platforms, diagnostic packages, computer modeling analyses, and taken advantage of the increasing energy available at laser facilities to create a self-consistent understanding of the fundamental physics underlying these issues. Our strategy was to examine the new physics emerging as we added the complexity necessary to use proton beams in an inertial fusion energy (IFE) application. From the starting point of a proton beam accelerated from a flat, isolated foil, we 1) curved it to focus the beam, 2) attached the foil to a superstructure, 3) added a side sheath to protect it from the surrounding plasma, and finally 4) studied the proton beam behavior as it passed through a protective end cap into plasma. We built up, as we proceeded, a self-consistent picture of the quasi-neutral plasma jet that is the proton beam that, for the first time, included the role of the hot electrons in shaping the jet. Controlling them?through design of the accelerating surface and its connection to the surrounding superstructure?is critical; their uniform spread across the proton accelerating area is vital, but their presence in the jet opposes focus; their electron flow away from the acceleration area reduces conversion efficiency but can also increase focusing ability. The understanding emerging from our work and the improved simulation tools we have developed allow designing structures that optimize proton beams for focused heating. Our findings include: ? The achievable focus of proton beams is limited by the thermal pressure gradient in the laser-generated hot electrons that drive the process. This bending can be suppressed using a controlled flow of hot electrons along the surrounding cone wall, which induces a local transverse focusing sheath electric field. The resultant (vacuum-focused) spot can meet IFE requirements. ? Confinement of laser-generated electrons to the proton accelerating area can be achieved by supporting targets on thin struts. That increases laser-to-proton conversion energy by ~50%. As noted above, confinement should not be total; necessary hot-electron leakage into the surrounding superstructure for proton focusing can be controlled by with the strut width/number. ? Proton jets are further modified as they enter the fuel through the superstructure?s end cap. They can generate currents during that transit that further focus the proton beams. We developed a new ion stopping module for LSP code that properly accounted for changes in stopping power with ionization (e.g. temperature), and will be using it in future studies. The improved understanding, new experimental platforms, and the self-consistent modeling capability allow researchers a new ability to investigate the interaction of large ion currents with warm dense matter. That is of direct importance to the creation and investiga

Stephens, Richard Burnite [General Atomics; Foord, Mark N. [Lawrence Livermore National Laboratory; Wei, Mingsheng [General Atomics; Beg, Farhat N. [University of California, San Diego; Schumacher, Douglass W. [The Ohio State University

2013-10-31T23:59:59.000Z

42

PLASMA-PHYSICS-21 Heavy ion driven reactor-size double shell inertial fusion targets*  

E-Print Network [OSTI]

Inertial Confinement Fusion (ICF) is considered as an alternative to Magnetic Confinement Fusion to achieve controlled thermonuclear fusion. The main goal is to exploit the energy released from thermonuclear fusion reactions

M. C. Serna Moreno; N. A. Tahir; J. J. Lpez Cela; A. R. Piriz; D. H. H. Hoffmann

43

Stability of shocks relating to the shock ignition inertial fusion energy scheme  

SciTech Connect (OSTI)

Motivated by the shock ignition approach to improve the performance of inertial fusion targets, we make a series of studies of the stability of shock waves in planar and converging geometries. We examine stability of shocks moving through distorted material and driving shocks with non-uniform pressure profiles. We then apply a fully 3D perturbation, following this spherically converging shock through collapse to a distorted plane, bounce and reflection into an outgoing perturbed, broadly spherical shock wave. We find broad shock stability even under quite extreme perturbation.

Davie, C. J., E-mail: c.davie10@imperial.ac.uk; Bush, I. A.; Evans, R. G. [Imperial College London, London SW7 2AZ (United Kingdom)

2014-08-15T23:59:59.000Z

44

Molten Salt Fuel Version of Laser Inertial Fusion Fission Energy (LIFE)  

SciTech Connect (OSTI)

Molten salt with dissolved uranium is being considered for the Laser Inertial Confinement Fusion Fission Energy (LIFE) fission blanket as a backup in case a solid-fuel version cannot meet the performance objectives, for example because of radiation damage of the solid materials. Molten salt is not damaged by radiation and therefore could likely achieve the desired high burnup (>99%) of heavy atoms of {sup 238}U. A perceived disadvantage is the possibility that the circulating molten salt could lend itself to misuse (proliferation) by making separation of fissile material easier than for the solid-fuel case. The molten salt composition being considered is the eutectic mixture of 73 mol% LiF and 27 mol% UF{sub 4}, whose melting point is 490 C. The use of {sup 232}Th as a fuel is also being studied. ({sup 232}Th does not produce Pu under neutron irradiation.) The temperature of the molten salt would be {approx}550 C at the inlet (60 C above the solidus temperature) and {approx}650 C at the outlet. Mixtures of U and Th are being considered. To minimize corrosion of structural materials, the molten salt would also contain a small amount ({approx}1 mol%) of UF{sub 3}. The same beryllium neutron multiplier could be used as in the solid fuel case; alternatively, a liquid lithium or liquid lead multiplier could be used. Insuring that the solubility of Pu{sup 3+} in the melt is not exceeded is a design criterion. To mitigate corrosion of the steel, a refractory coating such as tungsten similar to the first wall facing the fusion source is suggested in the high-neutron-flux regions; and in low-neutron-flux regions, including the piping and heat exchangers, a nickel alloy, Hastelloy, would be used. These material choices parallel those made for the Molten Salt Reactor Experiment (MSRE) at ORNL. The nuclear performance is better than the solid fuel case. At the beginning of life, the tritium breeding ratio is unity and the plutonium plus {sup 233}U production rate is {approx}0.6 atoms per 14.1 MeV neutron.

Moir, R W; Shaw, H F; Caro, A; Kaufman, L; Latkowski, J F; Powers, J; Turchi, P A

2008-10-24T23:59:59.000Z

45

Analysis of the energy transport and deposition within the reaction chamber of the prometheus inertial fusion energy reactor  

SciTech Connect (OSTI)

One of the parameters affecting the feasibility of Inertial Fusion Energy (IFE) devices is the number of shots per unit time, i.e. the repetition rate. The repetition rate limits the achievable power that can be obtained from the reactor. To obtain an estimate of the allowable time between shots, a code named RECON was developed to model the response of the reaction chamber to the pellet explosion. This paper discusses how the code treats the thermodynamic response of the cavity gas and models the condensation/evaporation of this vapor to and from the first wall. A large amount of energy from the pellet microexplosion is carried by the pellet debris and the x-rays generated in the fusion reaction. Models of x-ray attenuation and ion slowing down are used to estimate the fraction of the pellet energy that is absorbed in the vapor. A large amount of energy is absorbed into the cavity gas, which causes it to become partially ionized. The ionization complicates the calculation of the temperature, pressure, and the radiative heat transfer from the gas to the first wall. To treat this problem, methods developed by Zel`dovich and Raizer are used in modeling the internal energy and the radiative heat flux. RECON was developed to run with a relatively short computational time, yet accurate enough for conceptual reactor design calculations.

Eggleston, J.E.; Abdou, M.A.; Tillack, M.S. [Univ. of California, Los Angeles, CA (United States)

1994-12-31T23:59:59.000Z

46

Ignition on the National Ignition Facility: A Path Towards Inertial Fusion Energy  

E-Print Network [OSTI]

to Arial 18 pt bold Name here Title or division here Date 00, 2008 LLNL-PRES-407907 #12;NIF-1208-15666.ppt Moses_Fusion Power Associates, 12/03/08 2 Two major possibilities for fusion energy #12;NIF-1208-15666.ppt Moses_Fusion Power Associates, 12/03/08 3 The NIF is nearing completion and will be conducting

47

INERTIAL FUSION DRIVEN BY INTENSE HEAVY-ION BEAMS  

E-Print Network [OSTI]

Thermonuclear Experimental Reactor), now being constructed in Caderache, France [5]. In contrast, inertial fusion

Sharp, W. M.

2011-01-01T23:59:59.000Z

48

Economic Evaluation of Electrical Power Generation Using Laser Inertial Fusion Energy (LIFE)  

E-Print Network [OSTI]

With the completion of the National Ignition Facility (NIF) and upcoming ignition experiments, there is renewed interest in laser fusion-fission hybrids and pure fusion systems for base load power generation. An advantage of a laser fusion based system is that it would produce copious neutrons ( ~ 1.8x10 20 /s for a 500 MW fusion source). This opens the door to hybrid systems with once through, high burn-up, closed fuel cycles. With abundant fusion neutrons, only modest fission gain (5 to 10) is needed for power production. Depleted uranium can be used as the fission fuel, effectively eliminating the need for uranium mining and enrichment. With high burn up, a hybrid would generate only 5 % to 10% the volume of high-level nuclear waste per kilowatt hour that a once through light water reactor (LWR) does. Reprocessing is no longer needed to close the fuel cycle as the spent fuel can, after interim cooling, go directly to geologic disposal. While the depleted uranium fuel cycle offers advantages of simplicity and proliferation avoidance, it has the most challenging fuel lifetime requirements. Fissile fuel such as plutonium, or plutonium and minor actinides separated from spent nuclear fuel, would have roughly twice the fission gain and incur only about 25 % of the radiation damage to reach the same burn up level as depleted uranium. These missions are interesting in their own right and also provide an opportunity for early market entry of laser fusion based energy sources. A third fuel cycle option is to burn spent fuel directly, without prior separation of the plutonium and minor actinides. The neutronic and economic performance of this fuel cycle is very similar to the depleted uranium system. The primary difference is the need to fabricate new LIFE fuel from spent LWR fuel. The advantage of this fuel cycle is that it would burn the residual actinides in spent nuclear fuel, greatly reducing long term radio-toxicity and heat load, while avoiding the need to chemically separate spent LWR fuel.

Tm Anklam; Wayne Meier; Al Erl; Robin Miles; Aaron Simon

2009-01-01T23:59:59.000Z

49

Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

E-Print Network [OSTI]

and Hydroelectric 1.1.3 Nuclear Energy . . . . . . . . .Gain GNEP Global Nuclear Energy Partnership HEU HighlyIn Progress in Nuclear Energy, 17. Pergamon Press, 1986.

Kramer, Kevin James

2010-01-01T23:59:59.000Z

50

Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

E-Print Network [OSTI]

and Hydroelectric 1.1.3 Nuclear Energy . . . . . . . . .microparticles. Annals of Nuclear Energy, [96] F.B. Brown,In Progress in Nuclear Energy, 17. Pergamon Press, 1986.

Kramer, Kevin James

2010-01-01T23:59:59.000Z

51

Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

E-Print Network [OSTI]

2.1.1 Energy Production . . . . . . . . . 2.1.2 Spentof Figures Current World Energy Production Broken Down byCurrent US Energy Production Broken Down by

Kramer, Kevin James

2010-01-01T23:59:59.000Z

52

Status and Prospects of the Fast Ignition Inertial Fusion Concept  

SciTech Connect (OSTI)

Fast ignition is an alternate concept in inertial confinement fusion, which has the potential for easier ignition and greater energy multiplication. If realized it could improve the prospects for inertial fusion energy. It poses stimulating challenges in science and technology and the research is approaching a key stage in which the feasibility of fast ignition will be determined. This review covers the concepts, the state of the science and technology, the near term prospects and the challenges and risks involved in demonstrating high gain fast ignition.

Key, M H

2006-11-15T23:59:59.000Z

53

The impact of pulsed irradiation upon neutron activation calculations for inertial and magnetic fusion energy power plants  

SciTech Connect (OSTI)

Inertial fusion energy (IFE) and magnetic fusion energy (MFE) power plants will probably operate in a pulsed mode. The two different schemes, however, will have quite different time periods. Typical repetition rates for IFE power plants will be 1-5 Hz. MFE power plants will ramp up in current for about 1 hour, shut down for several minutes, and repeat the process. Traditionally, activation calculations for IFE and MFE power plants have assumed continuous operation and used either the ``steady state`` (SS) or ``equivalent steady state`` (ESS) approximations. It has been suggested recently that the SS and ESS methods may not yield accurate results for all radionuclides of interest. The present work expands that of Sisolak, et al. by applying their formulae to conditions which might be experienced in typical IFE and MFE power plants. In addition, complicated, multi-step reaction/decay chains are analyzed using an upgraded version of the ACAB radionuclide generation/depletion code. Our results indicate that the SS method is suitable for application to MFE power plant conditions. We also find that the ESS method generates acceptable results for radionuclides with half-lives more than a factor of three greater than the time between pulses. For components that are subject to 0.05 Hz (or more frequent) irradiation (such as coolant), use of the ESS method is recommended. For components or materials that are subject to less frequent irradiation (such as high-Z target materials), pulsed irradiation calculations should be used.

Latkowski, J.F. [Lawrence Livermore National Lab., CA (United States); Sanz, J. [Universidad Politecnica de Madrid (Spain); Vujic, J.L. [California Univ., Berkeley, CA (United States)

1996-06-26T23:59:59.000Z

54

Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

E-Print Network [OSTI]

of Figures Current World Energy Production Broken Down byUnited States and world energy production could be suppliedFigure 1.1: Current World Energy Production Broken Down by

Kramer, Kevin James

2010-01-01T23:59:59.000Z

55

Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

E-Print Network [OSTI]

including nuclear waste incineration and energy production.occurs, a ramp-down and incineration period begins. At thisduring the ramp up and incineration phases of a thermal

Kramer, Kevin James

2010-01-01T23:59:59.000Z

56

Nuclear diagnostics for inertial confinement fusion implosions  

SciTech Connect (OSTI)

This abstract contains viewgraphs on nuclear diagnostic techniques for inertial confinement fusion implosions. The viewgraphs contain information on: reactions of interest in ICF; advantages and disadvantages of these methods; the properties nuclear techniques can measure; and some specifics on the detectors used.

Murphy, T.J.

1997-11-01T23:59:59.000Z

57

Inertial Fusion Energy reactor design studies: Prometheus-L, Prometheus-H. Volume 2, Final report  

SciTech Connect (OSTI)

This report contains a review of design studies for Inertial Confinement reactor. This second of three volumes discussions is some detail the following: Objectives, requirements, and assumptions; rationale for design option selection; key technical issues and R&D requirements; and conceptual design selection and description.

Waganer, L.M.; Driemeyer, D.E.; Lee, V.D.

1992-03-01T23:59:59.000Z

58

Progress in Direct-Drive Inertial Confinement Fusion  

SciTech Connect (OSTI)

Recent progress in direct-drive inertial confinement fusion research at LLE using the 60-beam, 30-kJUV OMEGA laser system and cryogenic target capability to perform ignition-scaled implosions will be reported. In addition, a new high-energy (2.6-kJ) petawatt capability is currently under construction.

Meyerhofer,D.D.

2004-12-17T23:59:59.000Z

59

FEASIBILITY OF HYDROGEN PRODUCTION USING LASER INERTIAL FUSION AS THE PRIMARY ENERGY SOURCE  

SciTech Connect (OSTI)

The High Average Power Laser (HAPL) program is developing technology for Laser IFE with the goal of producing electricity from the heat generated by the implosion of deuterium-tritium (DT) targets. Alternatively, the Laser IFE device could be coupled to a hydrogen generation system where the heat would be used as input to a water-splitting process to produce hydrogen and oxygen. The production of hydrogen in addition to electricity would allow fusion energy plants to address a much wider segment of energy needs, including transportation. Water-splitting processes involving direct and hybrid thermochemical cycles and high temperature electrolysis are currently being developed as means to produce hydrogen from high temperature nuclear fission reactors and solar central receivers. This paper explores the feasibility of this concept for integration with a Laser IFE plant, and it looks at potential modifications to make this approach more attractive. Of particular interest are: (1) the determination of the advantages of Laser IFE hydrogen production compared to other hydrogen production concepts, and (2) whether a facility of the size of FTF would be suitable for hydrogen production.

Gorensek, M

2006-11-03T23:59:59.000Z

60

Inertial Confinement Fusion and the National Ignition Facility (NIF)  

SciTech Connect (OSTI)

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.

Ross, P.

2012-08-29T23:59:59.000Z

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Three dimensional simulations of space charge dominated heavy ion beams with applications to inertial fusion energy  

SciTech Connect (OSTI)

Heavy ion fusion requires injection, transport and acceleration of high current beams. Detailed simulation of such beams requires fully self-consistent space charge fields and three dimensions. WARP3D, developed for this purpose, is a particle-in-cell plasma simulation code optimized to work within the framework of an accelerator`s lattice of accelerating, focusing, and bending elements. The code has been used to study several test problems and for simulations and design of experiments. Two applications are drift compression experiments on the MBE-4 facility at LBL and design of the electrostatic quadrupole injector for the proposed ILSE facility. With aggressive drift compression on MBE-4, anomalous emittance growth was observed. Simulations carried out to examine possible causes showed that essentially all the emittance growth is result of external forces on the beam and not of internal beam space-charge fields. Dominant external forces are the dodecapole component of focusing fields, the image forces on the surrounding pipe and conductors, and the octopole fields that result from the structure of the quadrupole focusing elements. Goal of the design of the electrostatic quadrupole injector is to produce a beam of as low emittance as possible. The simulations show that the dominant effects that increase the emittance are the nonlinear octopole fields and the energy effect (fields in the axial direction that are off-axis). Injectors were designed that minimized the beam envelope in order to reduce the effect of the nonlinear fields. Alterations to the quadrupole structure that reduce the nonlinear fields further were examined. Comparisons were done with a scaled experiment resulted in very good agreement.

Grote, D.P.

1994-11-01T23:59:59.000Z

62

The Complete Burning of Weapons Grade Plutonium and Highly Enriched Uranium with (Laser Inertial Fusion-Fission Energy) LIFE Engine  

SciTech Connect (OSTI)

The National Ignition Facility (NIF) project, a laser-based Inertial Confinement Fusion (ICF) experiment designed to achieve thermonuclear fusion ignition and burn in the laboratory, is under construction at the Lawrence Livermore National Laboratory (LLNL) and will be completed in April of 2009. Experiments designed to accomplish the NIF's goal will commence in late FY2010 utilizing laser energies of 1 to 1.3 MJ. Fusion yields of the order of 10 to 20 MJ are expected soon thereafter. Laser initiated fusion-fission (LIFE) engines have now been designed to produce nuclear power from natural or depleted uranium without isotopic enrichment, and from spent nuclear fuel from light water reactors without chemical separation into weapons-attractive actinide streams. A point-source of high-energy neutrons produced by laser-generated, thermonuclear fusion within a target is used to achieve ultra-deep burn-up of the fertile or fissile fuel in a sub-critical fission blanket. Fertile fuels including depleted uranium (DU), natural uranium (NatU), spent nuclear fuel (SNF), and thorium (Th) can be used. Fissile fuels such as low-enrichment uranium (LEU), excess weapons plutonium (WG-Pu), and excess highly-enriched uranium (HEU) may be used as well. Based upon preliminary analyses, it is believed that LIFE could help meet worldwide electricity needs in a safe and sustainable manner, while drastically shrinking the nation's and world's stockpile of spent nuclear fuel and excess weapons materials. LIFE takes advantage of the significant advances in laser-based inertial confinement fusion that are taking place at the NIF at LLNL where it is expected that thermonuclear ignition will be achieved in the 2010-2011 timeframe. Starting from as little as 300 to 500 MW of fusion power, a single LIFE engine will be able to generate 2000 to 3000 MWt in steady state for periods of years to decades, depending on the nuclear fuel and engine configuration. Because the fission blanket in a fusion-fission hybrid system is subcritical, a LIFE engine can burn any fertile or fissile nuclear material, including unenriched natural or depleted U and SNF, and can extract a very high percentage of the energy content of its fuel resulting in greatly enhanced energy generation per metric ton of nuclear fuel, as well as nuclear waste forms with vastly reduced concentrations of long-lived actinides. LIFE engines could thus provide the ability to generate vast amounts of electricity while greatly reducing the actinide content of any existing or future nuclear waste and extending the availability of low cost nuclear fuels for several thousand years. LIFE also provides an attractive pathway for burning excess weapons Pu to over 99% FIMA (fission of initial metal atoms) without the need for fabricating or reprocessing mixed oxide fuels (MOX). Because of all of these advantages, LIFE engines offer a pathway toward sustainable and safe nuclear power that significantly mitigates nuclear proliferation concerns and minimizes nuclear waste. An important aspect of a LIFE engine is the fact that there is no need to extract the fission fuel from the fission blanket before it is burned to the desired final level. Except for fuel inspection and maintenance process times, the nuclear fuel is always within the core of the reactor and no weapons-attractive materials are available outside at any point in time. However, an important consideration when discussing proliferation concerns associated with any nuclear fuel cycle is the ease with which reactor fuel can be converted to weapons usable materials, not just when it is extracted as waste, but at any point in the fuel cycle. Although the nuclear fuel remains in the core of the engine until ultra deep actinide burn up is achieved, soon after start up of the engine, once the system breeds up to full power, several tons of fissile material is present in the fission blanket. However, this fissile material is widely dispersed in millions of fuel pebbles, which can be tagged as individual accountable items, and thus made difficult to diver

Farmer, J C; Diaz de la Rubia, T; Moses, E

2008-12-23T23:59:59.000Z

63

FPEOS: A First-Principles Equation of State Table of Deuterium for Inertial Confinement Fusion Applications  

E-Print Network [OSTI]

FPEOS: A First-Principles Equation of State Table of Deuterium for Inertial Confinement Fusion) Understanding and designing inertial confinement fusion (ICF) implosions through radiation- hydrodynamics. To minimize the drive energy for ignition, the imploding shell of DT- fuel needs to be kept as cold

Militzer, Burkhard

64

Damage production and accumulation in SiC structures in inertial and magnetic fusion systems  

E-Print Network [OSTI]

Damage production and accumulation in SiC structures in inertial and magnetic fusion systems M wall in an IFE system is $10% lower than in an MFE system, while gas production and burnup rates magnetic (MFE) and inertial (IFE) confinement fusion systems. Variations in the geometry, neutron energy

Ghoniem, Nasr M.

65

Lasers and Inertial Confinement Fusion in the United States  

E-Print Network [OSTI]

thermonuclear device began the Inertial Confinement Fusion Era I1860 · StanislawUlamandEdward Teller developedLasers and Inertial Confinement Fusion in the United States R. L. McCrory Director and Vice Provost confinement fusion (ICF) has grown as successively larger lasers have been built I1859 · The

66

Journal of Fusion Energy, Vol. 13, Nos. 2/3, 1994 Fusion Energy Advisory Committee (FEAC): Panel 7 Report  

E-Print Network [OSTI]

.2. A Brief History of Heavy Ion Fusion The heavy ion fusion approach to inertial fusion energy (IFEJournal of Fusion Energy, Vol. 13, Nos. 2/3, 1994 Fusion Energy Advisory Committee (FEAC): Panel 7 Report on Inertial Fusion Energy 1 Ronald Davidson,2 Barrett Ripin, Mohamed Abdou, David E. Baldwin

Abdou, Mohamed

67

Inertial Confinement Fusion R&D and Nuclear Proliferation  

SciTech Connect (OSTI)

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.

Robert J. Goldston

2011-04-28T23:59:59.000Z

68

Inertial Confinement Fusion Ignition and High Yield Campaign The Inertial Confinement Fusion Ignition and High Yield (ICF) Campaign supports the U.S. Department of Energy's (DOE)  

E-Print Network [OSTI]

, and effective nuclear weapons stockpile without underground testing. It supports stockpile assessment in simulations is essential to having confidence in them. More than 99 percent of the energy from a nuclear criticality is attained. The ICF program operates and conducts experiments in facilities that can create

69

National Academies Committee on the Prospects for Inertial Confinement Fusion Energy Systems  

E-Print Network [OSTI]

· Methane Hydrates Energy Storage · Nanoscale Electrode Materials for Batteries Energy Conversion potential to meet the IFE requirements Electra KrF Laser (NRL) = 248 nm (fundamental) Gas Laser Mercury target performance #12;What is a Krypton Fluoride (KrF) Laser? · Gas Laser--Excimer (Excited Dimer

70

Tutorial on the Physics of Inertial Confinement Fusion for energy applications  

E-Print Network [OSTI]

thermal input nuclear output Physics E E QQ == The Physics or Thermonuclear Q The Physics Q determines plasma common definition of "burning plasmas" The Physics or Thermonuclear Q #12;The Target Gain "G) Dense shell Useful kinetic energy #12;Ignition takes place in the "hot spot." The thermonuclear

71

Magneto-Inertial Fusion (Magnetized Target Fusion)( g g )  

E-Print Network [OSTI]

National Security, LLC for the DOE/NNSA Slide 1 LA-UR-11-01898 #12;Some Observations An economic for the DOE/NNSA 2 #12;Magneto-inertial fusion: Part of a plan B · May allow more efficient drivers, lower Operated by the Los Alamos National Security, LLC for the DOE/NNSA Slide 3 #12;A Wide Range of Driver

72

An Assessment of Inertial Confinement Fusion Target Physics A Panel on Fusion Target Physics ("the Panel") will serve as a technical resource to the  

E-Print Network [OSTI]

An Assessment of Inertial Confinement Fusion Target Physics A Panel on Fusion Target Physics ("the Panel") will serve as a technical resource to the Committee on Inertial Confinement Energy Systems ("the Physics will prepare a report that will assess the current performance of fusion targets associated

73

HYLIFE-2 inertial confinement fusion reactor design  

SciTech Connect (OSTI)

The HYLIFE-II inertial fusion power plant design study uses a liquid fall, in the form of jets to protect the first structural wall from neutron damage, x-rays, and blast to provide a 30-y lifetime. HYLIFE-I used liquid lithium. HYLIFE-II avoids the fire hazard of lithium by using a molten salt composed of fluorine, lithium, and beryllium (Li{sub 2}BeF{sub 4}) called Flibe. Access for heavy-ion beams is provided. Calculations for assumed heavy-ion beam performance show a nominal gain of 70 at 5 MJ producing 350 MJ, about 5.2 times less yield than the 1.8 GJ from a driver energy of 4.5 MJ with gain of 400 for HYLIFE-I. The nominal 1 GWe of power can be maintained by increasing the repetition rate by a factor of about 5.2, from 1.5 to 8 Hz. A higher repetition rate requires faster re-establishment of the jets after a shot, which can be accomplished in part by decreasing the jet fall height and increasing the jet flow velocity. Multiple chambers may be required. In addition, although not considered for HYLIFE-I, there is undoubtedly liquid splash that must be forcibly cleared because gravity is too slow, especially at high repetition rates. Splash removal can be accomplished by either pulsed or oscillating jet flows. The cost of electricity is estimated to be 0.09$/kW{center dot}h in constant 1988 dollars, about twice that of future coal and light water reactor nuclear power. The driver beam cost is about one-half the total cost. 12 refs., 9 figs., 5 tabs.

Moir, R.W.

1990-10-04T23:59:59.000Z

74

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

SciTech Connect (OSTI)

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.

Donovan, D. C. [Sandia National Laboratories, 7011 East Avenue, Livermore, California 94550 (United States); Boris, D. R. [Naval Research Laboratory, 4555 Overlook Avenue, South West, Washington, DC 20375 (United States); Kulcinski, G. L.; Santarius, J. F. [Fusion Technology Institute, University of Wisconsin-Madison, 1500 Engineering Drive, Madison, Wisconsin 53706 (United States); Piefer, G. R. [Phoenix Nuclear Labs, 2555 Industrial Drive, Madison, Wisconsin 53713 (United States)

2013-03-15T23:59:59.000Z

75

Ignition and Inertial Confinement Fusion at The National Ignition Facility  

SciTech Connect (OSTI)

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.

Moses, E

2009-10-01T23:59:59.000Z

76

Next-generation laser for Inertial Confinement Fusion  

SciTech Connect (OSTI)

We report on the progress in developing and building the Mercury laser system as the first in a series of a new generation of diode- pumped solid-state Inertial Confinement Fusion (ICF) lasers at Lawrence Livermore National Laboratory (LLNL). Mercury will be the first integrated demonstration of a scalable laser architecture compatible with advanced high energy density (HED) physics applications. Primary performance goals include 10% efficiencies at 10 Hz and a 1-10 ns pulse with 1 omega energies of 100 J and with 2 omega/3 omega frequency conversion.

Marshall, C.D.; Deach, R.J.; Bibeau, C. [and others

1997-09-29T23:59:59.000Z

77

Inertial Fusion Driven by Intense Heavy-Ion Beams  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun withconfinementEtching.348ASSEMBLY [ICO]Industry Group LearnsINERTIAL FUSION

78

ARIES Inertial Fusion Chamber Assessment M. S. Tillack*, F. Najmabadi, L. A. El-Guebaly, D. Goodin, W. R. Meier,  

E-Print Network [OSTI]

-coupled indirect drive and fast ignition. Arguably, inertial fusion looks significantly more credible and more components (i.e., final optics, final focus magnets), chamber physics (particle and radiation transport, gas al., "Inertial Fusion Energy Reactor Design Studies: Prometheus Final Report," MDC 92E0008 (DOE

California at San Diego, University of

79

Inertial confinement fusion | Princeton Plasma Physics Lab  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickrinformation for planningtoA Journey Inside the IntroductionInertial

80

Progress in the pulsed power Inertial Confinement Fusion program  

SciTech Connect (OSTI)

Pulsed power accelerators are being used in Inertial Confinement Fusion (ICF) research. In order to achieve our goal of a fusion yield in the range of 200 - 1000 MJ from radiation-driven fusion capsules, it is generally believed that {approx}10 MJ of driver energy must be deposited within the ICF target in order to deposit {approx}1 MJ of radiation energy in the fusion capsule. Pulsed power represents an efficient technology for producing both these energies and these radiation environments in the required short pulses (few tens of ns). Two possible approaches are being developed to utilize pulsed power accelerators in this effort: intense beams of light ions and z- pinches. This paper describes recent progress in both approaches. Over the past several years, experiments have successfully answered many questions critical to ion target design. Increasing the ion beam power and intensity are our next objectives. Last year, the Particle Beam Fusion Accelerator H (PBFA II) was modified to generate ion beams in a geometry that will be required for high yield applications. This 2048 modification has resulted in the production of the highest power ion beam to be accelerated from an extraction ion diode. We are also evaluating fast magnetically-driven implosions (z-pinches) as platforms for ICF ablator physics and EOS experiments. Z-pinch implosions driven by the 20 TW Saturn accelerator have efficiently produced high x- ray power (> 75 TW) and energy (> 400 kJ). Containing these x-ray sources within a hohlraum produces a unique large volume (> 6000 mm{sup 3}), long lived (>20 ns) radiation environment. In addition to studying fundamental ICF capsule physics, there are several concepts for driving ICF capsules with these x-ray sources. Progress in increasing the x-ray power on the Saturn accelerator and promise of further increases on the higher power PBFA II accelerator will be described.

Quintenz, J.P.; Matzen, M.K.; Mehlhorn, T.A. [and others

1996-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Inertial Fusion Program. Progress report, July 1-December 31, 1979  

SciTech Connect (OSTI)

Progress in the development of high-energy short-pulse CO/sub 2/ laser systems for fusion research is reported. Improvements in the Los Alamos National Laboratory eight-beam Helios system are described. These improvements increased the reliability of the laser and permitted the firing of 290 shots, most of which delivered energies of approximately 8 kJ to the target. Modifications to Gemini are outlined, including the installation of a new target-insertion mechanism. The redirection of the Antares program is discussed in detail, which will achieve a total energy of approximatey 40 kJ with two beams. This redirection will bring Antares on-line almost two years earlier than was possible with the full six-beam system, although at a lower energy. Experiments with isentropically imploded Sirius-B targets are discussed, and x-ray radiation-loss data from gold microballoons are presented, which show that these results are essentially identical with those obtained at glass-laser wavelengths. Significant progress in characterizing laser fusion targets is reported. New processes for fabricating glass miroballoon x-ray diagnostic targets, the application of high-quality metallic coatings, and the deposition of thick plastic coatings are described. Results in the development of x-ray diagnostics are reported, and research in the Los Alamos heavy-ion fusion program is summarized. Results of investigations of phase-conjugation research of gaseous saturable absorbers and of the use of alkali-halide crystals in a new class of saturable absorbers are summarized. New containment-vessel concepts for Inertial Confinement Fusion reactors are discussed, and results of a scoping study of four fusion-fission hybrid concepts are presented.

Skoberne, F. (comp.) [comp.

1981-10-01T23:59:59.000Z

82

Laser Fusion Energy The High Average Power  

E-Print Network [OSTI]

Laser Fusion Energy and The High Average Power Program John Sethian Naval Research Laboratory Dec for Inertial Fusion Energy with lasers, direct drive targets and solid wall chambers Lasers DPPSL (LLNL) Kr posters Snead Payne #12;Laser(s) Goals 1. Develop technologies that can meet the fusion energy

83

The role of nuclear reactions and -particle transport in the dynamics of inertial confinement fusion capsules  

E-Print Network [OSTI]

The role of nuclear reactions and -particle transport in the dynamics of inertial confinement fusion capsules Josselin Garnier1,a and Catherine Cherfils-Clérouin2 1 Laboratoire de Probabilités et the energy released by nuclear reactions, a nonlocal model for the -particle energy deposition process

Garnier, Josselin

84

Status of the US National Inertial Fusion ProgramSNL Z Facility UR/LLE OMEGA  

E-Print Network [OSTI]

for inertial fusion and high energy density physics · NIF 81% complete, first ignition experiments planned Ignition Facility is 85 % complete NIF concentrates 1.8 Mega Joules of energy into a mm3 size target -- it needs to be flush left -- keep horizontal within Title/Logo limits at the top #12;7 NIF has executed

85

Fusion energy  

ScienceCinema (OSTI)

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

Baylor, Larry

2014-05-23T23:59:59.000Z

86

Fusion energy  

SciTech Connect (OSTI)

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

Baylor, Larry

2014-05-02T23:59:59.000Z

87

Inertial confinement fusion based on the ion-bubble trigger  

SciTech Connect (OSTI)

Triggering the ion-bubble in an inertial confinement fusion, we have developed a novel scheme for the fast ignition. This scheme relies on the plasma cavitation by the wake of an intense laser pulse to generate an ion-bubble. The bubble acts both as an intense electron accelerator and as an electron wiggler. Consequently, the accelerated electrons trapped in the bubble can emit an intense tunable laser light. This light can be absorbed by an ablation layer on the outside surface of the ignition capsule, which subsequently drills it and thereby produces a guide channel in the pellet. Finally, the relativistic electron beam created in the bubble is guided through the channel to the high density core igniting the fusion fuel. The normalized beam intensity and beam energy required for triggering the ignition have been calculated when core is heated by the e-beam. In addition, through solving the momentum transfer, continuity and wave equations, a dispersion relation for the electromagnetic and space-charge waves has been analytically derived. The variations of growth rate with the ion-bubble density and electron beam energy have been illustrated. It is found that the growth rates of instability are significantly controlled by the ions concentration and the e-beam energy in the bubble.

Jafari, S., E-mail: SJafari@guilan.ac.ir; Nilkar, M.; Ghasemizad, A. [Department of Physics, University of Guilan, Rasht 41335-1914 (Iran, Islamic Republic of); Mehdian, H. [Department of Physics and Institute for Plasma Research, Tarbiat Moallem University, Tehran 15614 (Iran, Islamic Republic of)

2014-10-15T23:59:59.000Z

88

Atomic scale mixing for inertial confinement fusion associated hydro instabilities  

E-Print Network [OSTI]

Atomic scale mixing for inertial confinement fusion associated hydro instabilities J. Melvina, , P Alamos, NM 87545, USA Abstract Hydro instabilities have been identified as a potential cause- able. We find numerical convergence for this important quantity, in a purely hydro study, with only

New York at Stoney Brook, State University of

89

Future directions in inertial confinement fusion  

SciTech Connect (OSTI)

The author discusses future directions for the ICF program. At this time there is still uncertainty on a number of key issues necessary to decide on what type of a National Ignition Facility should be constructed. Mechanisms are in place to answer these questions. The author offers his opinions of where the program is likely to proceed. Technology wise indications are that direct drive heating has the best chance of reaching ignition and high gain. This has the advantage of making all three major user programs happy, namely weapons physics, weapons effects, and electrical energy. The demand for and price of energy in the country will have a major impact on the way the program is developed. From the laser fusion side the most promising drivers at present seem to be KrF lasers, and a major concern for these systems is whether the peak to valley nonuniformities can be reduced to the 1 to 2% level when delivered to the target in order to avoid driving instabilities.

Bodner, S.E. (Naval Research Laboratory, Washington, DC (United States))

1992-06-01T23:59:59.000Z

90

Basics of Inertial Confinement Fusion NIF and Photon Science Directorate Chief Scientist  

E-Print Network [OSTI]

Lawrence Livermore National Laboratory Work performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344 AAAS Annual Meeting 14-18 FebruaryBasics of Inertial Confinement Fusion John Lindl NIF and Photon Science Directorate Chief Scientist

91

Investigation of plasma instabilities relevant toInvestigation of plasma instabilities relevant to inertial confinement fusioninertial confinement fusion  

E-Print Network [OSTI]

. At sufficiently high temperatures a propagating fusion burn wave is ignited, releasing ~70 times the energy it is hoped that their effects can be minimized allowing fusion power to be harnessed to help combat the world's energy crisis. Plasmas InstabilitiesInertial Confinement Instabilities Small instabilities in a plasma

Strathclyde, University of

92

Recyclable transmission line (RTL) and linear transformer driver (LTD) development for Z-pinch inertial fusion energy (Z-IFE) and high yield.  

SciTech Connect (OSTI)

Z-Pinch Inertial Fusion Energy (Z-IFE) complements and extends the single-shot z-pinch fusion program on Z to a repetitive, high-yield, power plant scenario that can be used for the production of electricity, transmutation of nuclear waste, and hydrogen production, all with no CO{sub 2} production and no long-lived radioactive nuclear waste. The Z-IFE concept uses a Linear Transformer Driver (LTD) accelerator, and a Recyclable Transmission Line (RTL) to connect the LTD driver to a high-yield fusion target inside a thick-liquid-wall power plant chamber. Results of RTL and LTD research are reported here, that include: (1) The key physics issues for RTLs involve the power flow at the high linear current densities that occur near the target (up to 5 MA/cm). These issues include surface heating, melting, ablation, plasma formation, electron flow, magnetic insulation, conductivity changes, magnetic field diffusion changes, possible ion flow, and RTL mass motion. These issues are studied theoretically, computationally (with the ALEGRA and LSP codes), and will work at 5 MA/cm or higher, with anode-cathode gaps as small as 2 mm. (2) An RTL misalignment sensitivity study has been performed using a 3D circuit model. Results show very small load current variations for significant RTL misalignments. (3) The key structural issues for RTLs involve optimizing the RTL strength (varying shape, ribs, etc.) while minimizing the RTL mass. Optimization studies show RTL mass reductions by factors of three or more. (4) Fabrication and pressure testing of Z-PoP (Proof-of-Principle) size RTLs are successfully reported here. (5) Modeling of the effect of initial RTL imperfections on the buckling pressure has been performed. Results show that the curved RTL offers a much greater buckling pressure as well as less sensitivity to imperfections than three other RTL designs. (6) Repetitive operation of a 0.5 MA, 100 kV, 100 ns, LTD cavity with gas purging between shots and automated operation is demonstrated at the SNL Z-IFE LTD laboratory with rep-rates up to 10.3 seconds between shots (this is essentially at the goal of 10 seconds for Z-IFE). (7) A single LTD switch at Tomsk was fired repetitively every 12 seconds for 36,000 shots with no failures. (8) Five 1.0 MA, 100 kV, 100 ns, LTD cavities have been combined into a voltage adder configuration with a test load to successfully study the system operation. (9) The combination of multiple LTD coaxial lines into a tri-plate transmission line is examined. The 3D Quicksilver code is used to study the electron flow losses produced near the magnetic nulls that occur where coax LTD lines are added together. (10) Circuit model codes are used to model the complete power flow circuit with an inductive isolator cavity. (11) LTD architectures are presented for drivers for Z-IFE and high yield. A 60 MA LTD driver and a 90 MA LTD driver are proposed. Present results from all of these power flow studies validate the whole LTD/RTL concept for single-shot ICF high yield, and for repetitive-shot IFE.

Sharpe, Robin Arthur; Kingsep, Alexander S. (Kurchatov Institute, Moscow, Russia); Smith, David Lewis; Olson, Craig Lee; Ottinger, Paul F. (Naval Research Laboratory, Washington, DC); Schumer, Joseph Wade (Naval Research Laboratory, Washington, DC); Welch, Dale Robert (Voss Scientific, Albuquerque, NM); Kim, Alexander (High Currents Institute, Tomsk, Russia); Kulcinski, Gerald L. (University of Wisconsin, Madison, WI); Kammer, Daniel C. (University of Wisconsin, Madison, WI); Rose, David Vincent (Voss Scientific, Albuquerque, NM); Nedoseev, Sergei L. (Kurchatov Institute, Moscow, Russia); Pointon, Timothy David; Smirnov, Valentin P. (Kurchatov Institute, Moscow, Russia); Turgeon, Matthew C.; Kalinin, Yuri G. (Kurchatov Institute, Moscow, Russia); Bruner, Nichelle "Nicki" (Voss Scientific, Albuquerque, NM); Barkey, Mark E. (University of Alabama, Tuscaloosa, AL); Guthrie, Michael (University of Wisconsin, Madison, WI); Thoma, Carsten (Voss Scientific, Albuquerque, NM); Genoni, Tom C. (Voss Scientific, Albuquerque, NM); Langston, William L.; Fowler, William E.; Mazarakis, Michael Gerrassimos

2007-01-01T23:59:59.000Z

93

Ion Deflection for Final Optics In Laser Inertial Fusion Power Plants  

SciTech Connect (OSTI)

Left unprotected, both transmissive and reflective final optics in a laser inertial fusion power plant would quickly fail from melting, pulsed thermal stresses, or degradation of optical properties as a result of ion implantation. One potential option for mitigating this threat is to magnetically deflect the ions such that they are directed into a robust energy dump. In this paper we detail integrated studies that have been carried out to asses the viability of this approach for protecting final optics.

Abbott, R P; Latkowski, J F

2006-11-17T23:59:59.000Z

94

Weapons Activities/ Inertial Confinement Fusion Ignition  

E-Print Network [OSTI]

a safe, secure, and reliable nuclear weapons stockpile without underground testing. Science-based weapons and certify the stockpile without nuclear testing. The National Ignition Facility (NIF) extends HEDP under extreme conditions that approach the high energy density (HED) environments found in a nuclear

95

Weapons Activities/ Inertial Confinement Fusion Ignition  

E-Print Network [OSTI]

, and reliability of the Nation's nuclear weapons without nuclear testing. The program provides this capability models that are used to assess and certify the stockpile without nuclear testing. The National Ignition that approach the high-energy density (HED) environments found in a nuclear explosion. Virtually all

96

Inertial Confinement Fusion | National Nuclear Security Administration  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickrinformation for planningtoA Journey Inside the Introduction

97

OSIRIS and SOMBRERO Inertial Fusion Power Plant Designs, Volume 2: Designs, Assessments, and Comparisons  

SciTech Connect (OSTI)

This is a comprehensive design study of two Inertial Fusion Energy (IFE) electric power plants. Conceptual designs are presented for a fusion reactor (called Osiris) using an induction-linac heavy-ion beam driver, and another (called SOMBRERO) using a KrF laser driver. The designs covered all aspects of IFE power plants, including the chambers, heat transport and power conversion systems, balance-of-plant facilities, target fabrication, target injection and tracking, as well as the heavy-ion and KrF drivers. The point designs were assessed and compared in terms of their environmental & safety aspects, reliability and availability, economics, and technology development needs.

Meier, W. R.; Bieri, R. L.; Monsler, M. J.; Hendricks, C. D.; Laybourne, P.; Shillito, K. R.

1992-03-01T23:59:59.000Z

98

OSIRIS and SOMBRERO Inertial Fusion Power Plant Designs, Volume 1: Executive Summary & Overview  

SciTech Connect (OSTI)

This is a comprehensive design study of two Inertial Fusion Energy (IFE) electric power plants. Conceptual designs are presented for a fusion reactor (called Osiris) using an induction-linac heavy-ion beam driver, and another (called SOMBRERO) using a KrF laser driver. The designs covered all aspects of IFE power plants, including the chambers, heat transport and power conversion systems, balance-of-plant facilities, target fabrication, target injection and tracking, as well as the heavy-ion and KrF drivers. The point designs were assessed and compared in terms of their environmental & safety aspects, reliability and availability economics, and technology development needs.

Meier, W. R.; Bieri, R. L.; Monsler, M. J.; Hendricks, C.D.; Laybourne, P.; Shillito, K. R.

1992-03-01T23:59:59.000Z

99

Princeton Plasma Physics Lab - Inertial confinement fusion  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - SeptemberMicroneedles for4-16 FOR Primary Author Last Nameenergyiter ITER is

100

Development of backlighting sources for a Compton Radiography diagnostic of Inertial Confinement Fusion targets  

SciTech Connect (OSTI)

An important diagnostic tool for inertial confinement fusion is time-resolved imaging of the dense cold fuel surrounding the hot spot. Here we report on the source and diagnostic development of hard x-ray radiography and on the first radiographs of direct drive implosions obtained at photon energies up to about 100keV, where the Compton effect is the dominant contributor to the shell opacity. The radiographs of direct drive, plastic shell implosions obtained at the OMEGA laser facility have a spatial resolution of {approx}10um and a temporal resolution of {approx}10ps. This novel Compton Radiography is an invaluable diagnostic tool for Inertial Confinement Fusion targets, and will be integrated at the National Ignition Facility (NIF).

Tommasini, R

2010-04-23T23:59:59.000Z

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

HYLIFE-II inertial confinement fusion reactor design  

SciTech Connect (OSTI)

The HYLIFE-2 inertial fusion power plant design study uses a liquid fall, in the form of jets to protect the first structural wall from neutron damage, x rays, and blast to provide a 30-y lifetime. HYLIFE-1 used liquid lithium. HYLIFE 2 avoids the fire hazard of lithium by using a molten salt composed of fluorine, lithium, and beryllium (Li{sub 2}BeF{sub 4}) called Flibe. Access for heavy-ion beams is provided. Calculations for assumed heavy-ion beam performance show a nominal gain of 70 at 5 MJ producing 350 MJ, about 5.2 times less yield than the 1.8 GJ from a driver energy of 4.5 MJ with gain of 400 for HYLIFE-1. The nominal 1 GWe of power can be maintained by increasing the repetition rate by a factor of about 5.2, from 1.5 to 8 Hz. A higher repetition rate requires faster re-establishment of the jets after a shot, which can be accomplished in part by decreasing the jet fall height and increasing the jet flow velocity. Multiple chambers may be required. In addition, although not considered for HYLIFE-1, there is undoubtedly liquid splash that must be forcibly cleared because gravity is too slow, especially at high repetition rates. Splash removal can be accomplished by either pulsed or oscillating jet flows. The cost of electricity is estimated to be 0.09 $/kW{center dot}h in constant 1988 dollars, about twice that of future coal and light water reactor nuclear power. The driver beam cost is about one-half the total cost. 15 refs., 9 figs., 3 tabs.

Moir, R.W.

1990-12-14T23:59:59.000Z

102

A semi-analytic model of magnetized liner inertial fusion  

E-Print Network [OSTI]

Presented is a semi-analytic model of magnetized liner inertial fusion (MagLIF). This model accounts for several key aspects of MagLIF, including: (1) preheat of the fuel (optionally via laser absorption); (2) pulsed-power-driven liner implosion; (3) liner compressibility with an analytic equation of state, artificial viscosity, internal magnetic pressure, and ohmic heating; (4) adiabatic compression and heating of the fuel; (5) radiative losses and fuel opacity; (6) magnetic flux compression with Nernst thermoelectric losses; (7) magnetized electron and ion thermal conduction losses; (8) end losses; (9) enhanced losses due to prescribed dopant concentrations and contaminant mix; (10) deuterium-deuterium and deuterium-tritium primary fusion reactions for arbitrary deuterium to tritium fuel ratios; and (11) magnetized alpha-particle fuel heating. We show that this simplified model, with its transparent and accessible physics, can be used to reproduce the general 1D behavior presented throughout the original Ma...

McBride, Ryan D

2015-01-01T23:59:59.000Z

103

Inertial Fusion Program. Progress report, January-December 1980  

SciTech Connect (OSTI)

This report summarizes research and development effort in support of the Inertial Confinement Fusion program, including absorption measurements with an integrating sphere, generation of high CO/sub 2/-laser harmonics in the backscattered light from laser plasmas, and the effects of hydrogen target contamination on the hot-electron temperature and transport. The development of new diagnostics is outlined and measurements taken with a proximity-focused x-ray streak camera are presented. High gain in phase conjugation using germanium was demonstrated, data were obtained on retropulse isolation by plasmas generated from metal shutters, damage thresholds for copper mirrors at high fluences were characterized, and phase conjugation in the ultraviolet was demonstrated. Significant progress in the characterization of targets, new techniques in target coating, and important advances in the development of low-density, small-cell-size plastic foam that permit highly accurate machining to any desired shape are presented. The results of various fusion reactor system studies are summarized.

Not Available

1982-05-01T23:59:59.000Z

104

Role of hydrodynamic instability growth in hot-spot mass gain and fusion performance of inertial confinement fusion implosions  

SciTech Connect (OSTI)

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.

Srinivasan, Bhuvana, E-mail: srinbhu@vt.edu [Theoretical Division, Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Department of Aerospace and Ocean Engineering, Virginia Tech, Blacksburg, Virginia 24061 (United States); Tang, Xian-Zhu, E-mail: xtang@lanl.gov [Theoretical Division, Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States)

2014-10-15T23:59:59.000Z

105

THE CONCEPT OF ISOCHORIC CENTRAL SPARK IGNITION AND ITS FUEL GAIN IN INERTIAL FUSION  

E-Print Network [OSTI]

1 THE CONCEPT OF ISOCHORIC CENTRAL SPARK IGNITION AND ITS FUEL GAIN IN INERTIAL FUSION of the best methods in inertial confinement fusion (ICF) is the concept of central spark ignition, consisting of two distinct regions named as hot and cold regions and formed by hydro-dynamical implosion of fuel

Boyer, Edmond

106

Inertial confinement fusion. 1995 ICF annual report, October 1994--September 1995  

SciTech Connect (OSTI)

Lawrence Livermore National Laboratory`s (LLNL`s) Inertial Confinement Fusion (ICF) Program is a Department of Energy (DOE) Defense Program research and advanced technology development program focused on the goal of demonstrating thermonuclear fusion ignition and energy gain in the laboratory. During FY 1995, the ICF Program continued to conduct ignition target physics optimization studies and weapons physics experiments in support of the Defense Program`s stockpile stewardship goals. It also continued to develop technologies in support of the performance, cost, and schedule goals of the National Ignition Facility (NIF) Project. The NIF is a key element of the DOE`s Stockpile Stewardship and Management Program. In addition to its primary Defense Program goals, the ICF Program provides research and development opportunities in fundamental high-energy-density physics and supports the necessary research base for the possible long-term application to inertial fusion energy (IFE). Also, ICF technologies have had spin-off applications for industrial and governmental use. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

NONE

1996-06-01T23:59:59.000Z

107

Inertial confinement fusion research and development studies. Final report, October 1979-August 1980  

SciTech Connect (OSTI)

These Inertial Confinement Fusion (ICF) research and development studies were selected for structural, thermal, and vacuum pumping analyses in support of the High Yield Lithium Injection Fusion Energy (HYLIFE) concept development. An additional task provided an outlined program plan for an ICF Engineering Test Facility, using the HYLIFE concept as a model, although the plan is generally applicable to other ICF concepts. The HYLIFE is one promising type of ICF concept which features a falling array of liquid lithium jets. These jets surround the fusion reaction to protect the first structural wall (FSW) of the vacuum chamber by absorbing the fusion energy, and to act as the tritium breeder. The fusion energy source is a deuterium-tritium pellet injected into the chamber every second and driven by laser or heavy ion beams. The studies performed by Grumman have considered the capabilities of specific HYLIFE features to meet life requirements and the requirement to recover to preshot conditions prior to each subsequent shot. The components under investigation were the FSW which restrains the outward motion of the liquid lithium, the nozzle plate which forms the falling jet array, the graphite shield which is in direct top view of the fusion pellet, and the vacuum pumping system. The FSW studies included structural analysis, and definition of an experimental program to validate computer codes describing lithium motion and the resulting impact on the wall.

Bullis, R.; Finkelman, M.; Leng, J.; Luzzi, T.; Ojalvo, I.; Powell, E.; Sedgley, D.

1980-08-01T23:59:59.000Z

108

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

SciTech Connect (OSTI)

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.

Moses, E

2009-10-15T23:59:59.000Z

109

Multiple-beam laserplasma interactions in inertial confinement fusion  

SciTech Connect (OSTI)

The experimental evidence for multiple-beam laser-plasma instabilities of relevance to laser driven inertial confinement fusion at the ignition scale is reviewed, in both the indirect and direct-drive approaches. The instabilities described are cross-beam energy transfer (in both indirectly driven targets on the NIF and in direct-drive targets), multiple-beam stimulated Raman scattering (for indirect-drive), and multiple-beam two-plasmon decay instability (in direct drive). Advances in theoretical understanding and in the numerical modeling of these multiple beam instabilities are presented.

Myatt, J. F., E-mail: jmya@lle.rochester.edu; Zhang, J.; Maximov, A. V. [Laboratory for Laser Energetics, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States); Department of Mechanical Engineering, University of Rochester, Rochester, New York 14627 (United States); Short, R. W.; Seka, W.; Edgell, D. H.; Michel, D. T.; Igumenshchev, I. V. [Laboratory for Laser Energetics, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States); Froula, D. H. [Laboratory for Laser Energetics, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States); Department of Physics and Astronomy, University of Rochester, Rochester, New York 14627-0171 (United States); Hinkel, D. E.; Michel, P.; Moody, J. D. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551-0808 (United States)

2014-05-15T23:59:59.000Z

110

Determination of the deuterium-tritium branching ratio based on inertial confinement fusion implosions  

E-Print Network [OSTI]

The deuterium-tritium (D-T) ?-to-neutron branching ratio [[superscript 3]H(d,?)[superscript 5]He/[superscript 3]H(d,n)[superscript 4]He] was determined under inertial confinement fusion (ICF) conditions, where the ...

Rosenberg, Michael Jonathan

111

Proton emission imaging of the nuclear burn in inertial confinement fusion experiments  

E-Print Network [OSTI]

A proton core imaging system has been developed and extensively used for measuring the nuclear burn regions of inertial confinement fusion implosions. These imaging cameras, mounted to the 60-beam OMEGA laser facility, use ...

DeCiantis, Joseph Loreto

2005-01-01T23:59:59.000Z

112

E-Print Network 3.0 - advanced fuel fusion Sample Search Results  

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

advanced energy sources, inertial fusion requires... principles of controlled inertial fusion: thermonuclear ignition and burn of deuterium-tritium (DT) fuel... by the...

113

Inertial fusion program. Progress report, July 1-December 31, 1978  

SciTech Connect (OSTI)

Progress at Los Alamos Scientific Laboratory (LASL) in the development of high-energy short-pulse CO/sub 2/ laser systems for fusion research is reported. Improvements to LASL's two-beam system, Gemini, are outlined and experimental results are discussed. Our eight-beam system, Helios, was fired successfully on target for the first time, and became the world's most powerful gas laser for laser fusion studies. Work on Antares, our 100- to 200-TW target irradiation system, is summarized, indicating that design work and building construction are 70 and 48% complete, respectively. A baseline design for automatic centering of laser beams onto the various relay mirrors and the optical design of the Antares front end are discussed. The results of various fusion reactor studies are summarized, as well as investigations of synthetic-fuel production through application of fusion energy to hydrogen production by thermochemical water splitting. Studies on increased efficiency of energy extraction in CO/sub 2/ lasers and on lifetimes of cryogenic pellets in a reactor environment are summarized, as well as the results of studies on pellet injection, tracking, and beam synchronization.

Perkins, R.B.

1980-11-01T23:59:59.000Z

114

Inertial fusion program, January 1-June 30, 1979  

SciTech Connect (OSTI)

Progress in the development of high-energy short-pulse carbon dioxide laser systems for fusion research is reported. Improvements are outlined for the Los Alamos National Laboratory's Gemini System, which permitted over 500 shots in support of 10 different target experiments; the transformation of our eight-beam system, Helios, from a developmental to an operational facility that is capable of irradiating targets on a routine basis is described; and progress made toward completion of Antares, our 100- to 200-TW target irradiation system, is detailed. Investigations of phenomena such as phase conjugation by degenerate four-wave mixing and its applicability to laser fusion systems, and frequency multiplexing as a means toward multipulse energy extraction are summarized. Also discussed are experiments with targets designed for adiabatic compression. Progress is reported in the development of accurate diagnostics, especially for the detection of expanding ions, of neutron yield, and of x-ray emission. Significant advances in our theoretical efforts are summarized, such as the adaptation of our target design codes for use with the CRAY-1 computer, and new results leading to a better understanding of implosion phenomena are reported. The results of various fusion reactor studies are summarized, including the development of an ICF reactor blanket that offers a promising alternative to the usual lithium blanket, and the formulation of a capital-cost data base for laser fusion reactors to permit meaningful comparisons with other technologies.

Skoberne, F. (comp.)

1981-06-01T23:59:59.000Z

115

Production and measurement of engineered surfaces for inertial confinement fusion research  

SciTech Connect (OSTI)

Inertial Confinement Fusion uses the optical energy from a very high power laser to implode spherical capsules that contain a fuel mixture of deuterium and tritium. The capsules are made of either Beryllium, plastic, or glass and range from 0.1 mm to 2 mm in diameter. As a capsule implodes, thereby compressing the fuel to reach nuclear fusion conditions, it achieves temperatures of millions of degrees Centigrade and very high pressures. In this state, the capsule materials act like fluids and often a low density fluidic material will push on a higher density material which can be a very unstable condition depending upon the smoothness of the interface between the two materials. This unstable condition is called a hydrodynamic instabillity which results in the mixing of the two materials. If the mixing occurs between the fuel and a non-fuel material, it can stop the fusion reaction just like adding significant amounts of water to gasoline can stop the operation of an automobile. Another region in the capsule where surface roughness can cause capsule performance degradation is at a joint. For instance, many capsules are made of hemispheres that are joined together. If the joint surfaces are too rough, then there will an effective reduction in density at the joint. This density reduction can cause a non-uniform implosion which will reduce the fusion energy coming out of the capsule.

Day, Robert D [Los Alamos National Laboratory; Hatch, Douglas J [Los Alamos National Laboratory; Rivera, Gerald [Los Alamos National Laboratory

2011-01-19T23:59:59.000Z

116

NNSA Defense Programs Inertial Confinement Fusion Ignition and High Yield Campaign  

E-Print Network [OSTI]

Fusion and National Ignition Facility Project Dr. Christopher J. Keane NA-16 Office of Inertial Scott L. Samuelson NA-162 NA-10 * = stationed in Albuquerque #12;5 Militarily Effective Yield Fission concepts (pulsed power fusion, "fast ignition", petawatt lasers) 4. Maintain robust national program

117

Comment on 'Species separation in inertial confinement fusion fuels'[Phys. Plasmas 20, 012701 (2013)  

SciTech Connect (OSTI)

A recent paper presents numerical simulations of shock waves in a two-ion-component plasma, investigating how species separation occurring in the latter can affect the nuclear fusion yield of inertial confinement fusion targets. Here, it is shown that an important physical mechanism has obviously been omitted in those calculations, which thus lead to significantly overestimated results.

Larroche, O. [CEA DIF, Bruyeres le Chatel, 91297 Arpajon Cedex (France)

2013-04-15T23:59:59.000Z

118

Inertial Confinement Fusion quarterly report, April--June 1995. Volume 5, No. 3  

SciTech Connect (OSTI)

The ICF Quarterly Reports is published four times each fiscal year by the Inertial Confinement Fusion Program at the Lawrence Livermore National Laboratory. The journal reports selected current research within the ICF Program. Major areas of investigation presented here include fusion target theory and design, target fabrication, target experiments, and laser and optical science and technology.

NONE

1995-12-31T23:59:59.000Z

119

Role of Fusion Energy in a Sustainable Global Energy Strategy  

SciTech Connect (OSTI)

Fusion can play an important role in sustainable global energy because it has an available and unlimited fuel supply and location not restricted by climate or geography. Further, it emits no greenhouse gases. It has no potential for large energy releases in an accident, and no need for more than about 100 years retention for radioactive waste disposal. Substantial progress in the realization of fusion energy has been made during the past 20 years of research. It is now possible to produce significant amounts of energy from controlled deuterium and tritium (DT) reactions in the laboratory. This has led to a growing confidence in our ability to produce burning plasmas with significant energy gain in the next generation of fusion experiments. As success in fusion facilities has underpinned the scientific feasibility of fusion, the high cost of next-step fusion facilities has led to a shift in the focus of international fusion research towards a lower cost development path and an attractive end product. The increasing data base from fusion research allows conceptual fusion power plant studies, of both magnetic and inertial confinement approaches to fusion, to translate commercial requirements into the design features that must be met if fusion is to play a role in the world's energy mix; and identify key R and D items; and benchmark progress in fusion energy development. This paper addresses the question, ''Is mankind closer or farther away from controlled fusion than a few decades ago?'' We review the tremendous scientific progress during the last 10 years. We use the detailed engineering design activities of burning plasma experiments as well as conceptual fusion power plant studies to describe our visions of attractive fusion power plants. We use these studies to compare technical requirements of an attractive fusion system with present achievements and to identify remaining technical challenges for fusion. We discuss scenarios for fusion energy deployment in the energy market.

Sheffield, J.

2001-03-07T23:59:59.000Z

120

INSTITUTE OF PHYSICS PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 43 (2003) 16931709 PII: S0029-5515(03)67272-8  

E-Print Network [OSTI]

INSTITUTE OF PHYSICS PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 43 (2003) 1693­1709 PII: S0029-5515(03)67272-8 Fusion energy with lasers, direct drive targets.iop.org/NF/43/1693 Abstract A coordinated, focused effort is underway to develop Laser Inertial Fusion Energy

Ghoniem, Nasr M.

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Osiris and SOMBRERO inertial confinement fusion power plant designs. Volume 1, Executive summary and overview, Final report  

SciTech Connect (OSTI)

Conceptual designs and assessments have been completed for two inertial fusion energy (IFE) electric power plants. The detailed designs and results of the assessment studies are presented in this report. Osiris is a heavy-ion-beam (HIB) driven power plant and SOMBRERO is a Krypton-Fluoride (KrF) laser-driven power plant. Both plants are sized for a net electric power of 1000 MWe.

Meier, W.R.; Bieri, R.L.; Monsler, M.J.

1992-03-01T23:59:59.000Z

122

Fusion Energy Sciences  

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

Large Scale Production Computing and Storage Requirements for Fusion Energy Sciences: Target 2017 The NERSC Program Requirements Review "Large Scale Production Computing and...

123

TRISO Fuel Performance: Modeling, Integration into Mainstream Design Studies, and Application to a Thorium-fueled Fusion-Fission Hybrid Blanket  

E-Print Network [OSTI]

of a Hybrid Fusion-Fission Nuclear Energy System. Thesis.hybrid fusion-fission Laser Inertial Fusion-based Energy (LIFE) systems.Hybrid LIFE Engines Laser Inertial Fusion-based Energy (LIFE) systems

Powers, Jeffrey

2011-01-01T23:59:59.000Z

124

How Fusion Energy Works  

Broader source: Energy.gov [DOE]

Fusion energy is the energy source of the sun and all of the stars. As part of How Energy Works, we'll cover everything from fuel sources to plasma physics and beyond.

125

Fusion reactor control study. Volume 4: inertial confinement reactors. Final report  

SciTech Connect (OSTI)

This study of inertial confinement fusion (ICF) reactor control investigated concepts of the type intended to be driven by laser, electron, or light-ion pulsed energy beams. The study delineates the major reactor control functions, the methods and techniques advanced so far to perform those functions, and the problems, uncertainties, and issues associated with their possible implementation. The perceived shortcomings of some proposed methods of beam/target interaction initiated a search for potentially better solutions to the guidance/pointing/tracking control problem. A preliminary study of a new scheme to accomplish this most important control function is described. The simulated performance of the concept, which involves the active control of the intensity of a laser tube through which the fuel pellet travels to the target point, is encouraging. However, it is concluded that a more detailed study including experimental verification is required to establish the practicality of the concept.

Chang, F.R.; Fisher, J.L.; Madden, P.A.

1982-03-01T23:59:59.000Z

126

Inertial fusion program. Progress report, January 1-June 30, 1978  

SciTech Connect (OSTI)

Studies and experiments aimed at investigating the possibility of restoring wavefront quality in optical systems through phase conjugation are summarized, and work that could lead to the development of highly damage-resistant isolators is discussed. The effects of various parameters on pulse-energy uniformity and of multipass extraction on laser efficiency are reported. Results of equation-of-state, shock propagation, multiburst simulation, and opacity measurements are discussed. Target designs are described that should provide a smooth transition from the exploding-pusher regime of experiments to that of isentropic compression. Progress in target fabrication techniques toward creating a 20-times-liquid-density target are outlined, and efforts that led to the extension of our neutron detection capability to levels of less than 10/sup 3/ n are summarized. The results of various studies of laser fusion application, e.g., for producing ultrahigh-temperature process heat or hydrogen from water decomposition are presented, as well as investigations of fusion-fission hybrids for the production of /sup 233/U from /sup 232/Th.

Skoberne, F. (comp.)

1980-05-01T23:59:59.000Z

127

Fusion Energy Sciences Program Mission  

E-Print Network [OSTI]

Fusion Energy Sciences Program Mission The Fusion Energy Sciences (FES) program leads the national for an economically and environmentally attractive fusion energy source. The National Energy Policy states that fusion power has the long-range potential to serve as an abundant and clean source of energy and recommends

128

Engineering design of the Nova Laser Facility for inertial-confinement fusion  

SciTech Connect (OSTI)

The design of the Nova Laser Facility for inertial confinement fusion experiments at Lawrence Livermore National Laboratory is presented from an engineering perspective. Emphasis is placed upon design-to-performance requirements as they impact the various subsystems that comprise this complex experimental facility.

Simmons, W W; Godwin, R O; Hurley, C A; Wallerstein, E. P.; Whitham, K.; Murray, J. E.; Bliss, E. S.; Ozarski, R. G.; Summers, M. A.; Rienecker, F.; Gritton, D. G.; Holloway, F. W.; Suski, G. J.; Severyn, J. R.

1982-01-25T23:59:59.000Z

129

The physics issues that determine inertial confinement fusion target gain and driver requirements: A tutorial*  

E-Print Network [OSTI]

The physics issues that determine inertial confinement fusion target gain and driver requirements ``bookkeeping'' of input parametrized by ICF drivers' coupling efficiencies to the target, and subsequent requirements will be discussed for both the direct drive driver impinging directly on the target and indirect

130

A Fusion Test Facility for Inertial Fusion Presented by Stephen Obenschain  

E-Print Network [OSTI]

target designs consistent with the energy application. · Development of economical mass production with direct laser drive NRL Laser Fusion DT ice (fuel) ablator D Pellet shell imploded by laser ablation to v 300 km/sec for >MJ designs Hot fuel Cold fuel · Reduce pellet mass while increasing implosion velocity

131

Fusion Energy Program Presentation to  

E-Print Network [OSTI]

International Thermonuclear Experimental Reactor Plasma Technologies Fusion Technologies Advanced MaterialsFusion Energy Program Presentation to Field Work Proposals Washington, D.C. N. Anne Davies Associate Director for Fusion energy Office of Energy Research March23, 1994 #12;FUSION ENERGY PROGRAM FYI

132

Pulsed Power Driven Fusion Energy  

SciTech Connect (OSTI)

Pulsed power is a robust and inexpensive technology for obtaining high powers. Considerable progress has been made on developing light ion beams as a means of transporting this power to inertial fusion capsules. However, further progress is hampered by the lack of an adequate ion source. Alternatively, z-pinches can efficiently convert pulsed power into thermal radiation, which can be used to drive an inertial fusion capsule. However, a z-pinch driven fusion explosion will destroy a portion of the transmission line that delivers the electrical power to the z-pinch. They investigate several options for providing standoff for z-pinch driven fusion. Recyclable Transmission Lines (RTLs) appear to be the most promising approach.

SLUTZ,STEPHEN A.

1999-11-22T23:59:59.000Z

133

Starpower: The U.S. and the International Quest for Fusion Energy  

E-Print Network [OSTI]

of this report) #12;. Foreword Fusion research, offering the hope of an energy technology with an essentially un with the requirements for develop- ment of a usefuI energy technology. The report does not analyze inertial confinement

134

Pressure and impulse scaling methods for wall impact in ICF (inertial confinement fusion)  

SciTech Connect (OSTI)

The design of the first structural wall (FSW) in an inertial confinement fusion (ICF) reactor requires some knowledge of the expected wall loading produced by x-ray and neutron deposition; specifically in the High Yield Lithium Injection Fusion Energy (HYLIFE) reactor, wall loading results from two sources -- gas shock and liquid impact. Gas shock is derived from x-ray deposition in the thin layers of exposed blanket material, producing ionized vapor, which will generate gas shock on the FSW. Liquid impact, on the other hand, results from the acceleration of liquid blanket material by two possible forces -- the drag from vapor expansion through the blanket material and the neutron-induced isochoric disassembly process. Both impacts, however, are coupled by the interaction of hot gas expanding through the liquid blanket. This paper discusses scaling methods for estimating pressure and impulse on the HYLIFE FSW from these impacts. In particular, this paper reviews simple analytical and numerical techniques, and the use of experimental results in the estimation of wall impacts for the HYLIFE blanket geometry. Considered important in the analyses are supersonic flow through jet arrays and isochoric disassembly. Given the same initial parameters as those used in previous HYLIFE studies, the techniques described here yield results comparable to the previous studies utilizing heavy numerical simulation.

Liu, J.C.; Chen, X.M.; Schrock, V.E. (California Univ., Berkeley, CA (USA). Dept. of Nuclear Engineering); Orth, C.D. (Lawrence Livermore National Lab., CA (USA))

1990-01-01T23:59:59.000Z

135

To: ! Members of the National Academy of Sciences Committee on the Prospects for Inertial Confinement Fusion Energy Systems, and the Panel  

E-Print Network [OSTI]

: either a shift primarily to non-ignition nuclear weapons research ("high energy density physics different indirect-drive target designs that could be quickly developed and tested. For others, Plan B would for a proper direct-drive test. Also, the chamber portholes that would be needed for direct-drive were covered

136

ITER Fusion Energy  

ScienceCinema (OSTI)

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.

Dr. Norbert Holtkamp

2010-01-08T23:59:59.000Z

137

Improving particle confinement in inertial electrostatic fusion for spacecraft power and propulsion  

E-Print Network [OSTI]

Fusion energy is attractive for use in future spacecraft because of improved fuel energy density and reduced radioactivity compared with fission power. Unfortunately, the most promising means of generating fusion power on ...

Dietrich, Carl, 1977-

2007-01-01T23:59:59.000Z

138

Progress in inertial fusion research at the Los Alamos Scientific Laboratory. Paper No. IAEA-CN-38/B-2  

SciTech Connect (OSTI)

The Los Alamos Scientific Laboratory Inertial Confinement Fusion Program is reviewed. Experiments using the Helios CO/sub 2/ laser system delivering up to 6 kJ on target are described. Because breakeven energy estimates for laser drivers of 1 ..mu..m and above have risen and there is a need for CO/sub 2/ experiments in the tens-of-kilojoule regime as soon as practical, a first phase of Antares construction is now directed toward completion of two of the six original modules in 1983. These modules are designed to deliver 40 kJ of CO/sub 2/ laser light on target.

Perkins, R.B.

1980-01-01T23:59:59.000Z

139

Metrics for long wavelength asymmetries in inertial confinement fusion implosions on the National Ignition Facility  

SciTech Connect (OSTI)

We investigate yield degradation due to applied low mode P2 and P4 asymmetries in layered inertial confinement fusion implosions. This study has been performed with a large database of >600 2D simulations. We show that low mode radiation induced drive asymmetries can result in significant deviation between the core hot spot shape and the fuel ?R shape at peak compression. In addition, we show that significant residual kinetic energy at peak compression can be induced by these low mode asymmetries. We have developed a metric, which is a function of the hot spot shape, fuel ?R shape, and residual kinetic energy at peak compression, that is well correlated to yield degradation due to low mode shape perturbations. It is shown that the ?R shape and residual kinetic energy cannot, in general, be recovered by inducing counter asymmetries to make the hot core emission symmetric. In addition, we show that the yield degradation due to low mode asymmetries is well correlated to measurements of time dependent shape throughout the entire implosion, including early time shock symmetry and inflight fuel symmetry.

Kritcher, A. L.; Town, R.; Bradley, D.; Clark, D.; Spears, B.; Jones, O.; Haan, S.; Springer, P. T.; Lindl, J.; Callahan, D.; Edwards, M. J.; Landen, O. L. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551-0808 (United States)] [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551-0808 (United States); Scott, R. H. H. [Rutherford Appleton Laboratory, Chilton, Didcot, Oxfordshire (United Kingdom)] [Rutherford Appleton Laboratory, Chilton, Didcot, Oxfordshire (United Kingdom)

2014-04-15T23:59:59.000Z

140

Plasma Jet Driven Magneto-Inertial Fusion (PJMIF)  

E-Print Network [OSTI]

National Security, LLC for NNSA LA-UR-11-07030 #12;Plasma jet experiments can provide cm National Security, LLC for NNSA Imploding plasma liner formed by 30 merging plasma jets with 1.5 MJ, LLC for NNSA MIF ICF Basko et al., Nucl. Fusion, 2000 Magnetic field reduces thermal transport

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141

Optimized beryllium target design for indirectly driven inertial confinement fusion experiments on the National Ignition Facility  

SciTech Connect (OSTI)

For indirect drive inertial confinement fusion, Beryllium (Be) ablators offer a number of important advantages as compared with other ablator materials, e.g., plastic and high density carbon. In particular, the low opacity and relatively high density of Be lead to higher rocket efficiencies giving a higher fuel implosion velocity for a given X-ray drive; and to higher ablation velocities providing more ablative stabilization and reducing the effect of hydrodynamic instabilities on the implosion performance. Be ablator advantages provide a larger target design optimization space and can significantly improve the National Ignition Facility (NIF) [J. D. Lindl et al., Phys. Plasmas 11, 339 (2004)] ignition margin. Herein, we summarize the Be advantages, briefly review NIF Be target history, and present a modern, optimized, low adiabat, Revision 6 NIF Be target design. This design takes advantage of knowledge gained from recent NIF experiments, including more realistic levels of laser-plasma energy backscatter, degraded hohlraum-capsule coupling, and the presence of cross-beam energy transfer.

Simakov, Andrei N., E-mail: simakov@lanl.gov; Wilson, Douglas C.; Yi, Sunghwan A.; Kline, John L.; Batha, Steven H. [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, New Mexico 87545 (United States)] [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, New Mexico 87545 (United States); Clark, Daniel S.; Milovich, Jose L.; Salmonson, Jay D. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551 (United States)] [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551 (United States)

2014-02-15T23:59:59.000Z

142

Mode 1 drive asymmetry in inertial confinement fusion implosions on the National Ignition Facility  

SciTech Connect (OSTI)

Mode 1 radiation drive asymmetry (pole-to-pole imbalance) at significant levels can have a large impact on inertial confinement fusion implosions at the National Ignition Facility (NIF). This asymmetry distorts the cold confining shell and drives a high-speed jet through the hot spot. The perturbed hot spot shows increased residual kinetic energy and reduced internal energy, and it achieves reduced pressure and neutron yield. The altered implosion physics manifests itself in observable diagnostic signatures, especially the neutron spectrum which can be used to measure the neutron-weighted flow velocity, apparent ion temperature, and neutron downscattering. Numerical simulations of implosions with mode 1 asymmetry show that the resultant simulated diagnostic signatures are moved toward the values observed in many NIF experiments. The diagnostic output can also be used to build a set of integrated implosion performance metrics. The metrics indicate that P{sub 1} has a significant impact on implosion performance and must be carefully controlled in NIF implosions.

Spears, Brian K., E-mail: spears9@llnl.gov; Edwards, M. J.; Hatchett, S.; Kritcher, A.; Lindl, J.; Munro, D.; Patel, P.; Robey, H. F.; Town, R. P. J. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551-0808 (United States)] [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551-0808 (United States); Kilkenny, J. [General Atomics, P.O. Box 85608, San Diego, California 92186-5608 (United States)] [General Atomics, P.O. Box 85608, San Diego, California 92186-5608 (United States); Knauer, J. [Laboratory for Laser Energetics, 250 E. River Road Rochester, New York 14623-1212 (United States)] [Laboratory for Laser Energetics, 250 E. River Road Rochester, New York 14623-1212 (United States)

2014-04-15T23:59:59.000Z

143

Development of backlighting sources for a Compton radiography diagnostic of Inertial Confinement Fusion targets  

SciTech Connect (OSTI)

We present scaled demonstrations of backlighter sources, emitting Bremsstrahlung x-rays with photon energies above 75 keV, that we will use to record x-ray Compton radiographic snapshots of cold dense DT fuel in inertial confinement fusion implosions at the National Ignition Facility (NIF). In experiments performed at the Titan laser facility at Lawrence Livermore National Laboratory, we measured the source size and the Bremsstrahlung spectrum as a function of laser intensity and pulse length, from solid targets irradiated at 2e17-5e18 W/cm{sup 2} using 2-40 ps pulses. Using Au planar foils we achieved source sizes down to 5.5 {micro}m, and conversion efficiencies of about 1e-3 J/J into x-ray photons with energies in the 75-100 keV spectral range. We can now use these results to design NIF backlighter targets and shielding, and to predict Compton radiography performance as a function of the NIF implosion yield and associated background.

Tommasini, R; MacPhee, A; Hey, D; Ma, T; Chen, C; Izumi, N; Unites, W; MacKinnon, A; Hatchett, S P; Remington, B A; Park, H S; Springer, P; Koch, J A; Landen, O L; Seely, J; Holland, G; Hudson, L

2008-05-07T23:59:59.000Z

144

Inertial Confinement Fusion quarterly report, October--December 1994. Volume 5, No. 1  

SciTech Connect (OSTI)

The ICF quarterly report is published by the Inertial Confinement Fusion Program at the Lawrence Livermore National Laboratory. Topics included in this issue include: system description and initial performance results for beamlet, design and performance of the beamlet amplifiers and optical switch, beamlet pulse-generation and wavefront-control system, large-aperture, high- damage-threshold optics for beamlet, beamlet pulsed power system, beamlet laser diagnostics, and beam propagation and frequency conversion modeling for the beamlet laser.

NONE

1995-09-01T23:59:59.000Z

145

Suggested Path to Develop Inertial Fusion Energy  

E-Print Network [OSTI]

and tested on small scale · We believe this particular Phase I effort could be completed in about 3 years upgrades. "18 kJ" FTF Amplifier · Similar current pulse · Diode voltage 8oo kV · Aperture width 100 cm

146

Inertial fusion energy studies in the UK  

E-Print Network [OSTI]

interactions ·Neutron damage to first wall and optics ·Channel formation #12;The types of research ­ the wider acceleration High harmonic generation Secondary radiation sources Nuclear physics Fundamental laser plasma

147

Novel free-form hohlraum shape design and optimization for laser-driven inertial confinement fusion  

SciTech Connect (OSTI)

The hohlraum shape attracts considerable attention because there is no successful ignition method for laser-driven inertial confinement fusion at the National Ignition Facility. The available hohlraums are typically designed with simple conic curves, including ellipses, parabolas, arcs, or Lame curves, which allow only a few design parameters for the shape optimization, making it difficult to improve the performance, e.g., the energy coupling efficiency or radiation drive symmetry. A novel free-form hohlraum design and optimization approach based on the non-uniform rational basis spline (NURBS) model is proposed. In the present study, (1) all kinds of hohlraum shapes can be uniformly represented using NURBS, which is greatly beneficial for obtaining the optimal available hohlraum shapes, and (2) such free-form uniform representation enables us to obtain an optimal shape over a large design domain for the hohlraum with a more uniform radiation and higher drive temperature of the fuel capsule. Finally, a hohlraum is optimized and evaluated with respect to the drive temperature and symmetry at the Shenguang III laser facility in China. The drive temperature and symmetry results indicate that such a free-form representation is advantageous over available hohlraum shapes because it can substantially expand the shape design domain so as to obtain an optimal hohlraum with high performance.

Jiang, Shaoen; Jing, Longfei, E-mail: scmyking-2008@163.com; Ding, Yongkun [Laser Fusion Research Center, China Academy Engineering Physics, Mianyang 621900 (China); Huang, Yunbao, E-mail: huangyblhy@gmail.com [Mechatronics School of Guangdong University of Technology, Guangzhou 510006 (China)

2014-10-15T23:59:59.000Z

148

Real viscosity effects in inertial confinement fusion target deuteriumtritium micro-implosions  

SciTech Connect (OSTI)

We report on numerical studies of real viscous effects on the implosion characteristics of imploded DT micro-targets. We use the implicit ePLAS code to perform 2D simulations of spherical and slightly ellipsoidal DT shells on DT gas filled ?40??m diameter voids. Before their final implosions the shells have been nearly adiabatically compressed up to 10{sup 2} or 10{sup 3}?g/cm{sup 3} densities. While the use of conventional artificial viscosity can lead to high central densities for initially spherical shells, we find that a real physical viscosity from ion-ion collisions can give a high (>20?keV) central temperature but severely reduced central density (<200?g/cm{sup 3}), while the elliptical shells evidence p?=?2 distortion of the heated central fuel region. These results suggest that the general use of artificial viscosities in Inertial Confinement Fusion (ICF) modeling may have lead to overly optimistic yields for current NIF targets and that polar direct drive with more energy for the imploding capsule may be needed for ultimate ICF success.

Mason, R. J., E-mail: rodmason01@msn.com; Kirkpatrick, R. C.; Faehl, R. J. [Research Applications Corporation, Los Alamos, New Mexico 87544 (United States)] [Research Applications Corporation, Los Alamos, New Mexico 87544 (United States)

2014-02-15T23:59:59.000Z

149

Optical Comb Generation for Streak Camera Calibration for Inertial Confinement Fusion Experiments  

SciTech Connect (OSTI)

The National Ignition Facility (NIF) at Lawrence Livermore National Laboratory (LLNL) is coming on-line to support physics experimentation for the U.S. Department of Energy (DOE) programs in Inertial Confinement Fusion (ICF) and Stockpile Stewardship (SS). Optical streak cameras are an integral part of the experimental diagnostics instrumentation at NIF. To accurately reduce streak camera data a highly accurate temporal calibration is required. This article describes a technique for simultaneously generating a precise +/- 2 ps optical marker pulse (fiducial reference) and trains of precisely timed, short-duration optical pulses (so-called comb pulse trains) that are suitable for the timing calibrations. These optical pulse generators are used with the LLNL optical streak cameras. They are small, portable light sources that, in the comb mode, produce a series of temporally short, uniformly spaced optical pulses, using a laser diode source. Comb generators have been produced with pulse-train repetition rates up to 10 GHz at 780 nm, and somewhat lower frequencies at 664 nm. Individual pulses can be as short as 25-ps FWHM. Signal output is via a fiber-optic connector on the front panel of the generator box. The optical signal is transported from comb generator to streak camera through multi-mode, graded-index optical fiber.

Ronald Justin, Terence Davies, Frans Janson, Bruce Marshall, Perry Bell, Daniel Kalantar, Joseph Kimbrough, Stephen Vernon, Oliver Sweningsen

2008-09-18T23:59:59.000Z

150

The mitigating effect of magnetic fields on Rayleigh-Taylor unstable inertial confinement fusion plasmas  

SciTech Connect (OSTI)

Rayleigh-Taylor (RT) instabilities at interfaces of disparate mass densities have long been known to generate magnetic fields during inertial confinement fusion implosions. An externally applied magnetic field can also be efficiently amplified by RT instabilities. The focus here is on magnetic field generation and amplification at the gas-ice interface which is RT unstable during the deceleration phase of the implosion. RT instabilities lead to undesirable mix of hot and cold plasmas which enhances thermal energy loss and tends to produce a more massive warm-spot instead of a hot-spot. Two mechanisms are shown here to mitigate the thermal energy loss from the hot-spot. The first mechanism is the reduction of electron thermal conductivity with interface-aligned magnetic fields. This can occur through self-generated magnetic fields via the Biermann battery effect as well as through externally applied magnetic fields that undergo an exponential growth via the stretch-and-fold magnetohydrodynamic dynamo. Self-generated magnetic fields during RT evolution can result in a factor of 2?10 decrease in the electron thermal conductivity at the gas-ice interface, while externally applied magnetic fields that are compressed to 61000 T at the onset of deceleration (corresponding to pre-implosion external fields of 0.0610 T) could result in a factor of 2500 reduction in electron thermal conductivity at the gas-ice interface. The second mechanism to mitigate thermal energy loss from the hot-spot is to decrease the interface mixing area between the hot and cold plasmas. This is achieved through large external magnetic fields of 1000 T at the onset of deceleration which damp short-wavelength RT modes and long-wavelength Kelvin-Helmholtz modes thus significantly slowing the RT growth and reducing mix.

Srinivasan, Bhuvana; Tang, Xian-Zhu [Theoretical Division, Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States)] [Theoretical Division, Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States)

2013-05-15T23:59:59.000Z

151

Fast Neutral Generation by Charge Exchange Reaction and Its Effect on Neutron Production Rate in Inertial Electrostatic Confinement Fusion Systems  

SciTech Connect (OSTI)

Fast neutral generation by charge exchange reaction in inertial electrostatic confinement plasmas is studied by solving the Poisson equation and the Boltzmann equation for fast neutrals. Fusion reactions carried by the charge exchange fast neutrals become appreciable compared with ion-background fusion reaction. It is shown that the fusion reaction between fast neutral and background gas is sensitively affected by experimental parameters (grid voltage, background gas pressure) and ion distribution function.

Yoshinaga, S.; Matsuura, H.; Nakao, Y.; Kudo, K. [Kyushu University (Japan)

2005-05-15T23:59:59.000Z

152

Apparatus for an Inertial Fusion Reactor Inventor Abraham Massry |  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth (AOD)ProductssondeadjustsondeadjustAbout theOFFICEAmes LaboratoryAntonya Sanders-Promoting.Energy

153

Peter A. Norreys Professor of Inertial Fusion Science,  

E-Print Network [OSTI]

Credit: Lawrence Livermore National Laboratory #12;EEE n output nuclear Nuclear energy output from Campaign · "Science of Ignition on the NIF" Workshop · Central Laser Facility / ORION #12;Universities: LLNL NIF Point Design #12;Cryogenic target & shield #12;Target Gain G is NOT a physics parameter

154

Liquid Vortex Shielding for Fusion Energy Applications  

SciTech Connect (OSTI)

Swirling liquid vortices can be used in fusion chambers to protect their first walls and critical elements from the harmful conditions resulting from fusion reactions. The beam tube structures in heavy ion fusion (HIF) must be shielded from high energy particles, such as neutrons, x-rays and vaporized coolant, that will cause damage. Here an annular wall jet, or vortex tube, is proposed for shielding and is generated by injecting liquid tangent to the inner surface of the tube both azimuthally and axially. Its effectiveness is closely related to the vortex tube flow properties. 3-D particle image velocimetry (PIV) is being conducted to precisely characterize its turbulent structure. The concept of annular vortex flow can be extended to a larger scale to serve as a liquid blanket for other inertial fusion and even magnetic fusion systems. For this purpose a periodic arrangement of injection and suction holes around the chamber circumference are used, generating the layer. Because it is important to match the index of refraction of the fluid with the tube material for optical measurement like PIV, a low viscosity mineral oil was identified and used that can also be employed to do scaled experiments of molten salts at high temperature.

Bardet, Philippe M. [University of California, Berkeley (United States); Supiot, Boris F. [University of California, Berkeley (United States); Peterson, Per F. [University of California, Berkeley (United States); Savas, Oemer [University of California, Berkeley (United States)

2005-05-15T23:59:59.000Z

155

Ion beam requirements for fast ignition of inertial fusion targets  

E-Print Network [OSTI]

Ion beam requirements for fast ignition are investigated by numerical simulation taking into account new effects such as ion beam divergence not included before. We assume that ions are generated by the TNSA scheme in a curved foil placed inside a re-entrant cone and focused on the cone apex or beyond. From the focusing point to the compressed core ions propagate with a given divergence angle. Ignition energies are obtained for two compressed fuel configurations heated by proton and carbon ion beams. The dependence of the ignition energies on the beam divergence angle and on the position of the ion beam focusing point have been analysed. Comparison between TNSA and quasi-monoenergetic ions is also shown.

Honrubia, J J

2015-01-01T23:59:59.000Z

156

A Concept Exploration Program in Fast Ignition Inertial Fusion Final Report  

SciTech Connect (OSTI)

The Fast Ignition (FI) approach to Inertial Confinement Fusion (ICF) holds particular promise for fusion energy because the independently generated compression and ignition pulses allow ignition with less compression, resulting in (potentially) higher gain. Exploiting this concept effectively requires an understanding of the transport of electrons in prototypical geometries and at relevant densities and temperatures. Our consortium, which included General Atomics (GA), The Ohio State University (OSU), the University of California, San Diego (UCSD), University of California, Davis (UC-Davis), and Princeton University under this grant (~$850K/yr) and Lawrence Livermore National Laboratory (LLNL) under a companion grant, won awards in 2000, renewed in 2005, to investigate the physics of electron injection and transport relevant to the FI concept, which is crucial to understand electron transport in integral FI targets. In the last two years we have also been preparing diagnostics and starting to extend the work to electron transport into hot targets. A complementary effort, the Advanced Concept Exploration (ACE) program for Fast Ignition, was funded starting in 2006 to integrate this understanding into ignition schemes specifically suitable for the initial fast ignition attempts on OMEGA and National Ignition Facility (NIF), and during that time these two programs have been managed as a coordinated effort. This result of our 7+ years of effort has been substantial. Utilizing collaborations to access the most capable laser facilities around the world, we have developed an understanding that was summarized in a Fusion Science & Technology 2006, Special Issue on Fast Ignition. The author lists in the 20 articles in that issue are dominated by our group (we are first authors in four of them). Our group has published, or submitted 67 articles, including 1 in Nature, 2 Nature Physics, 10 Physical Review Letters, 8 Review of Scientific Instruments, and has been invited to give numerous talks at national and international conferences (including APS-DPP, IAEA, FIW). The advent of PW capabilities at Rutherford Appleton Lab (UK) and then at Titan (LLNL) (2005 and 2006, respectively), was a major step toward experiments in ultra-high intensity high-energy FI relevant regime. The next step comes with the activation of OMEGA EP at LLE, followed shortly by NIF-ARC at LLNL. These capabilities allow production of hot dense material for electron transport studies. In this transitional period, considerable effort has been spent in developing the necessary tools and experiments for electron transport in hot and dense plasmas. In addition, substantial new data on electron generation and transport in metallic targets has been produced and analyzed. Progress in FI detailed in 2 is related to the Concept Exploration Program (CEP) objectives; this section is a summary of the publications and presentations listed in 5. This work has benefited from the synergy with work on related Department of Energy (DOE) grants, the Fusion Science Center and the Fast Ignition Advanced Concept Exploration grant, and from our interactions with overseas colleagues, primarily at Rutherford Appleton Laboratory in the UK, and the Institute for Laser Engineering in Japan.

Stephens, Richarad Burnite [General Atomics] [General Atomics; Freeman, Richard R. [The Ohio State University] [The Ohio State University; Van Woekom, L. D. [The Ohio State University] [The Ohio State University; Key, M. [Lawrence Livermore National Laboratory] [Lawrence Livermore National Laboratory; MacKinnon, Andrew J. [Lawrence Livermore National Laboratory] [Lawrence Livermore National Laboratory; Wei, Mingsheng [General Atomics] [General Atomics

2014-02-27T23:59:59.000Z

157

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

SciTech Connect (OSTI)

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.

Lynn, Alan G., E-mail: lynn@ece.unm.edu; Gilmore, Mark [Department of Electrical and Computer Engineering, University of New Mexico, Albuquerque, New Mexico 87131 (United States)

2014-11-15T23:59:59.000Z

158

Magnetic Probe to Study Plasma Jets for Magneto-Inertial Fusion  

SciTech Connect (OSTI)

A probe has been constructed to measure the magnetic field of a plasma jet generated by a pulsed plasma rail-gun. The probe consists of two sets of three orthogonally-oriented commercial chip inductors to measure the three-dimensional magnetic field vector at two separate positions in order to give information about the magnetic field evolution within the jet. The strength and evolution of the magnetic field is one of many factors important in evaluating the use of supersonic plasma jets for forming imploding spherical plasma liners as a standoff driver for magneto-inertial fusion.

Martens, Daniel [Los Alamos National Laboratory; Hsu, Scott C. [Los Alamos National Laboratory

2012-08-16T23:59:59.000Z

159

Inertial Confinement Fusion: How to Make a Star  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary)morphinanInformation Desert Southwest Region service area.Portaldefault Sign In AboutIn theIndustry @

160

Magnetic-compression/magnetized-target fusion (MAGO/MTF): A marriage of inertial and magnetic confinement  

SciTech Connect (OSTI)

Intermediate between magnetic confinement (MFE) and inertial confinement (ICF) in time and density scales is an area of research now known in the US as magnetized target fusion (MTF) and in Russian as MAGO (MAGnitnoye Obzhatiye--magnetic compression). MAGO/MTF uses a magnetic field and preheated, wall-confined plasma fusion fuel within an implodable fusion target. The magnetic field suppresses thermal conduction losses in the fuel during the target implosion and hydrodynamic compression heating process. In contrast to direct, hydrodynamic compression of initially ambient-temperature fuel (i.e., ICF), MAGO/MTF involves two steps: (a) formation of a warm (e.g., 100 eV or higher), magnetized (e.g., 100 kG) plasma within a fusion target prior to implosion; (b) subsequent quasi-adiabatic compression by an imploding pusher, of which a magnetically driven imploding liner is one example. In this paper, the authors present ongoing activities and potential future activities in this relatively unexplored area of controlled thermonuclear fusion.

Lindemuth, I.R.; Ekdahl, C.A.; Kirkpatrick, R.C. [and others

1996-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

{gamma}-ray 'bang-time' measurements with a gas-Cherenkov detector for inertial-confinement fusion experiments  

SciTech Connect (OSTI)

In a laser driven inertial-confinement fusion experiment, bang time is defined as the time between the laser light impinging the target and the peak of the fusion reactions. Bang time is often used to compare computed predictions to experiment. Large laser facilities, such as NIF and LMJ, which are currently under construction, will produce yields far in excess of any previous inertial-confinement fusion experiment. One of the implications of such high yields is that fusion {gamma} rays, which have branching ratios four orders of magnitude less than that of fusion neutrons, may be used to diagnose bang time. This article describes the first of such {gamma}-ray bang-time measurement made using the OMEGA laser facility at the Laboratory for Laser Energetics, University of Rochester. The diagnostic used for this was a gas Cherenkov detector. The experimental setup, data and error analyses, and suggested improvements are presented.

Horsfield, C. J.; Caldwell, S. E.; Christensen, C. R.; Evans, S. C.; Mack, J. M.; Sedillo, T.; Young, C. S.; Glebov, V. Yu. [Atomic Weapons Establishment, Aldermaston, Reading, Berkshire RG7 4PR (United Kingdom); Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Laboratory for Laser Energetics, University of Rochester, Rochester, New York 14623-1299 (United States)

2006-10-15T23:59:59.000Z

162

50 Years of Fusion Research Fusion Innovation Research and Energy  

E-Print Network [OSTI]

, .... · Controlled Thermonuclear Fusion had great potential ­ Uncontrolled Thermonuclear fusion demonstrated in 19521 50 Years of Fusion Research Dale Meade Fusion Innovation Research and Energy® Princeton, NJ SOFE 2009 June 1, 2009 San Diego, CA 92101 #12;2 #12;2 #12;3 Fusion Prior to Geneva 1958 · A period of rapid

163

Manufactured solutions for the three-dimensional Euler equations with relevance to Inertial Confinement Fusion  

SciTech Connect (OSTI)

We present a set of manufactured solutions for the three-dimensional (3D) Euler equations. The purpose of these solutions is to allow for code verification against true 3D flows with physical relevance, as opposed to 3D simulations of lower-dimensional problems or manufactured solutions that lack physical relevance. Of particular interest are solutions with relevance to Inertial Confinement Fusion (ICF) capsules. While ICF capsules are designed for spherical symmetry, they are hypothesized to become highly 3D at late time due to phenomena such as RayleighTaylor instability, drive asymmetry, and vortex decay. ICF capsules also involve highly nonlinear coupling between the fluid dynamics and other physics, such as radiation transport and thermonuclear fusion. The manufactured solutions we present are specifically designed to test the terms and couplings in the Euler equations that are relevant to these phenomena. Example numerical results generated with a 3D Finite Element hydrodynamics code are presented, including mesh convergence studies.

Waltz, J., E-mail: jwaltz@lanl.gov [Computational Physics Division, Los Alamos National Laboratory, Los Alamos, NM (United States); Canfield, T.R. [Theoretical Division, Los Alamos National Laboratory, Los Alamos, NM (United States); Morgan, N.R. [Computational Physics Division, Los Alamos National Laboratory, Los Alamos, NM (United States); Risinger, L.D.; Wohlbier, J.G. [Computational and Computer Sciences Division, Los Alamos National Laboratory, Los Alamos, NM (United States)

2014-06-15T23:59:59.000Z

164

Fusion Energy Sciences  

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

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165

Fusion Energy Sciences  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickr Flickr Editor's note:Computing |FuelsFunding availableFusion Large

166

Towards Human Energy Expenditure Estimation Using Smart Phone Inertial Sensors  

E-Print Network [OSTI]

to reliably estimate energy expenditure (EE). Direct calorimetry [5] measures the heat produced by human bodyTowards Human Energy Expenditure Estimation Using Smart Phone Inertial Sensors Bozidara Cvetkovi´c1 human energy expenditure during sport and normal daily ac- tivities. The paper presents technical

Lu?trek, Mitja

167

Snowmass 2002: The Fusion Energy Sciences Summer Study  

SciTech Connect (OSTI)

The Fusion Summer Study 2002 will be a forum for the critical technical assessment of major next-steps in the fusion energy sciences program, and will provide crucial community input to the long-range planning activities undertaken by the DOE [Department of Energy] and the FESAC [Fusion Energy Sciences Advisory Committee]. It will be an ideal place for a broad community of scientists to examine goals and proposed initiatives in burning plasma science in magnetic fusion energy and integrated research experiments in inertial fusion energy. This meeting is open to every member of the fusion energy science community and significant international participation is encouraged. The objectives of the Fusion Summer Study are three: (1) Review scientific issues in burning plasmas to establish the basis for the following two objectives and to address the relations of burning plasma in tokamaks to innovative magnetic fusion energy (MFE) confinement concepts and of ignition in inertial fusion energy (IFE) to integrated research facilities. (2) Provide a forum for critical discussion and review of proposed MFE burning plasma experiments (e.g., IGNITOR, FIRE, and ITER) and assess the scientific and technological research opportunities and prospective benefits of these approaches to the study of burning plasmas. (3) Provide a forum for the IFE community to present plans for prospective integrated research facilities, assess present status of the technical base for each, and establish a timetable and technical progress necessary to proceed for each. Based on significant preparatory work by the fusion community prior to the July Snowmass meeting, the Snowmass working groups will prepare a draft report that documents the scientific and technological benefits of studies of burning plasmas. The report will also include criteria by which the benefits of each approach to fusion science, fusion engineering/technology, and the fusion development path can be assessed. Finally, the report will present a uniform technical assessment of the benefits of the three approaches. The draft report will be presented and extensively discussed during the July meeting, leading to a final report. This report will provide critical fusion community input to the decision process of FESAC and DOE in 2002-2003, and to the review of burning plasma science by the National Academy of Sciences called for by FESAC and Energy Legislation which was passed by the House of Representatives [H.R. 4]. Members of the fusion community are encouraged to participate in the Snowmass working groups.

N. Sauthoff; G. Navratil; R. Bangerter

2002-01-31T23:59:59.000Z

168

Direct-Drive Inertial Fusion Research at the University of Rochester's Laboratory for Laser Energetics: A Review  

SciTech Connect (OSTI)

This paper reviews the status of direct-drive inertial confinement fusion (ICF) research at the University of Rochester's Laboratory for Laser Energetics (LLE). LLE's goal is to demonstrate direct-drive ignition on the National Ignition Facility (NIF) by 2014. Baseline "all-DT" NIF direct-drive ignition target designs have been developed that have a predicted gain of 45 (1-D) at a NIF drive energy of ~1.6 MJ. Significantly higher gains are calculated for targets that include a DT-wicked foam ablator. This paper also reviews the results of both warm fuel and initial cryogenic-fuel spherical target implosion experiments carried out on the OMEGA UV laser. The results of these experiments and design calculations increase confidence that the NIF direct-drive ICF ignition goal will be achieved.

McCrory, R.L.; Meyerhofer, D.D.; Loucks, S.J.; Skupsky, S.; Bahr, R.E.; Betti, R.; Boehly, T.R.; Craxton, R.S.; Collins, T.J.B.; Delettrez, J.A.; Donaldson, W.R.; Epstein, R.; Fletcher, K.A.; Freeman, C.; Frenje, J.A.; Glebov, V.Yu.; Goncharov, V.N.; Harding, D.R.; Jaanimagi, P.A.; Keck, R.L.; Kelly, J.H.; Kessler, T.J.; Kilkenny, J.D.; Knauer, J.P.; Li, C.K.; Lund, L.D.; Marozas, J.A.; McKenty, P.W.; Marshall, F.J.; Morse, S.F.B.; Padalino, S.; Petrasso, R.D.; Radha, P.B.; Regan, S.P.; Roberts, S.; Sangster, T.C.; Seguin, F.H.; Seka, W.; Smalyuk, V.A.; Soures, J.M.; Stoeckl, C.; Thorp, K.A.; Yaakobi, B.; Zuegel, J.D.

2010-04-16T23:59:59.000Z

169

Magnetized Target Fusion (MTF) (a.k.a. Magneto-Inertial Fusion)  

E-Print Network [OSTI]

.g., Atlas $50M). The low cost and size of experimental facilities should significantly reduce fusion TEMPERATURE (eV) IONDENSITY(/cm)3 1016 1014 1018 1020 1022 1024 1026 103 104 105 Facility Cost($) = 1 TEMPERATURE (eV) 104 105 Facility Cost($) B=5 MG Operation at an intermediate density leads to reduced

170

"50" Years of Fusion Research Fusion Innovation Research and Energy  

E-Print Network [OSTI]

Classified US Program on Controlled Thermonuclear Fusion (Project Sherwood) carried out until 1958 when"50" Years of Fusion Research Dale Meade Fusion Innovation Research and Energy® Princeton, NJ Fi P th SFusion Fire Powers the Sun "W d t if k f i k ""We need to see if we can make fusion work

171

Path toward fusion energy  

SciTech Connect (OSTI)

A brief history of the fusion research program is given. Some of the problems that plagued the developmental progress are described. (MOW)

Furth, H.P.

1985-08-01T23:59:59.000Z

172

Development of a Bayesian method for the analysis of inertial confinement fusion experiments on the NIF  

E-Print Network [OSTI]

The complex nature of inertial confinement fusion (ICF) experiments results in a very large number of experimental parameters that are only known with limited reliability. These parameters, combined with the myriad physical models that govern target evolution, make the reliable extraction of physics from experimental campaigns very difficult. We develop an inference method that allows all important experimental parameters, and previous knowledge, to be taken into account when investigating underlying microphysics models. The result is framed as a modified $\\chi^{2}$ analysis which is easy to implement in existing analyses, and quite portable. We present a first application to a recent convergent ablator experiment performed at the NIF, and investigate the effect of variations in all physical dimensions of the target (very difficult to do using other methods). We show that for well characterised targets in which dimensions vary at the 0.5% level there is little effect, but 3% variations change the results of i...

Gaffney, Jim A; Sonnad, Vijay; Libby, Stephen B

2013-01-01T23:59:59.000Z

173

Interactive tools designed to study mix in inertial confinement fusion implosions  

SciTech Connect (OSTI)

Graphical user interface tools have been built in IDL to study mix in inertial confinement fusion (ICF) implosion cores. FLAME (Fall-Line Analysis Mix Evaluator), a code which investigates yield degradation due to mix , was designed to post-process 1D hydrodynamic simulation output by implementing a variety of mix models. Three of these mix models are based on the physics of the fall-line. In addition, mixing data from other sources can be incorporated into the yield degradation analysis. Two independent tools called HAME (Haan Analysis Mix Evaluator) and YAME (Youngs Analysis Mix Evaluator) were developed to calculate the spatial extent of the mix region according to the Haan saturation model and Youngs' phenomenological model, respectively. FLAME facilitates a direct comparison to experimental data. The FLAME, HAME, and YAME interfaces are user-friendly, flexible, and platform-independent.

Welser-sherrill, Leslie [Los Alamos National Laboratory; Cooley, James H [Los Alamos National Laboratory; Wilson, Doug C [Los Alamos National Laboratory

2008-01-01T23:59:59.000Z

174

Realization of Fusion Energy: An alternative fusion roadmap  

E-Print Network [OSTI]

Realization of Fusion Energy: An alternative fusion roadmap Farrokh Najmabadi Professor of Electrical & Computer Engineering Director, Center for Energy Research UC San Diego International Fusion Road of emerging nations, energy use is expected to grow ~ 4 fold in this century (average 1.6% annual growth rate

175

Dynamic response of materials on subnanosecond time scales, and beryllium properties for inertial confinement fusion  

SciTech Connect (OSTI)

During the past few years, substantial progress has been made in developing experimental techniques capable of investigating the response of materials to dynamic loading on nanosecond time scales and shorter, with multiple diagnostics probing different aspects of the behavior. These relatively short time scales are scientifically interesting because plastic flow and phase changes in common materials with simple crystal structures--such as iron--may be suppressed, allowing unusual states to be induced and the dynamics of plasticity and polymorphism to be explored. Loading by laser-induced ablation can be particularly convenient: this technique has been used to impart shocks and isentropic compression waves from {approx}1 to 200 GPa in a range of elements and alloys, with diagnostics including line imaging surface velocimetry, surface displacement (framed area imaging), x-ray diffraction (single crystal and polycrystal), ellipsometry, and Raman spectroscopy. A major motivation has been the study of the properties of beryllium under conditions relevant to the fuel capsule in inertial confinement fusion: magnetically driven shock and isentropic compression shots at Z were used to investigate the equation of state and shock melting characteristics, complemented by laser ablation experiments to investigate plasticity and heterogeneous response from the polycrystalline microstructure. These results will help to constrain acceptable tolerances on manufacturing, and possible loading paths, for inertial fusion ignition experiments at the National Ignition Facility. Laser-based techniques are being developed further for future material dynamics experiments, where it should be possible to obtain high quality data on strength and phase changes up to at least 1 TPa.

Swift, Damian C.; Tierney, Thomas E.; Luo Shengnian; Paisley, Dennis L.; Kyrala, George A.; Hauer, Allan; Greenfield, Scott R.; Koskelo, Aaron C.; McClellan, Kenneth J.; Lorenzana, Hector E.; Kalantar, Daniel; Remington, Bruce A.; Peralta, Pedro; Loomis, Eric [Los Alamos National Laboratory, MS E526, Los Alamos, New Mexico 87545 (United States); Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore, California 94550 (United States); Arizona State University, Tempe, Arizona 85287 (United States)

2005-05-15T23:59:59.000Z

176

Osiris and SOMBRERO inertial confinement fusion power plant designs. Volume 2, Designs, assessments, and comparisons, Final report  

SciTech Connect (OSTI)

The primary objective of the of the IFE Reactor Design Studies was to provide the Office of Fusion Energy with an evaluation of the potential of inertial fusion for electric power production. The term reactor studies is somewhat of a misnomer since these studies included the conceptual design and analysis of all aspects of the IFE power plants: the chambers, heat transport and power conversion systems, other balance of plant facilities, target systems (including the target production, injection, and tracking systems), and the two drivers. The scope of the IFE Reactor Design Studies was quite ambitious. The majority of our effort was spent on the conceptual design of two IFE electric power plants, one using an induction linac heavy ion beam (HIB) driver and the other using a Krypton Fluoride (KrF) laser driver. After the two point designs were developed, they were assessed in terms of their (1) environmental and safety aspects; (2) reliability, availability, and maintainability; (3) technical issues and technology development requirements; and (4) economics. Finally, we compared the design features and the results of the assessments for the two designs.

Meier, W.R.; Bieri, R.L.; Monsler, M.J.

1992-03-01T23:59:59.000Z

177

Dark Energy and Dark Matter as Inertial Effects  

E-Print Network [OSTI]

A globally rotating model of the universe is postulated. It is shown that dark energy and dark matter are cosmic inertial effects resulting from such a cosmic rotation, corresponding to centrifugal and a combination of centrifugal and the Coriolis forces, respectively. The physics and the cosmological and galactic parameters obtained from the model closely match those attributed to dark energy and dark matter in the standard {\\Lambda}-CDM model.

Serkan Zorba

2012-10-20T23:59:59.000Z

178

An improved method for measuring the absolute DD neutron yield and calibrating neutron time-of-flight detectors in inertial confinement fusion experiments  

E-Print Network [OSTI]

Since the establishment of nuclear physics in the early 1900's and the development of the hydrogen bomb in the 1950's, inertial confinement fusion (ICF) has been an important field in physics. Funded largely though the ...

Waugh, C. (Caleb Joseph)

2014-01-01T23:59:59.000Z

179

Studies of ion kinetic effects in shock-driven inertial confinement fusion implosions at OMEGA and the NIF and magnetic reconnection using laser-produced plasmas at OMEGA  

E-Print Network [OSTI]

Studies of ion kinetic effects during the shock-convergence phase of inertial confinement fusion (ICF) implosions and magnetic reconnection in strongly-driven, laser-produced plasmas have been facilitated by the use of ...

Rosenberg, Michael Jonathan

2014-01-01T23:59:59.000Z

180

Theory of hydro-equivalent ignition for inertial fusion and its applications to OMEGA and the National Ignition Facility  

SciTech Connect (OSTI)

The theory of ignition for inertial confinement fusion capsules [R. Betti et al., Phys. Plasmas 17, 058102 (2010)] is used to assess the performance requirements for cryogenic implosion experiments on the Omega Laser Facility. The theory of hydrodynamic similarity is developed in both one and two dimensions and tested using multimode hydrodynamic simulations with the hydrocode DRACO [P. B. Radha et al., Phys. Plasmas 12, 032702 (2005)] of hydro-equivalent implosions (implosions with the same implosion velocity, adiabat, and laser intensity). The theory is used to scale the performance of direct-drive OMEGA implosions to the National Ignition Facility (NIF) energy scales and determine the requirements for demonstrating hydro-equivalent ignition on OMEGA. Hydro-equivalent ignition on OMEGA is represented by a cryogenic implosion that would scale to ignition on the NIF at 1.8?MJ of laser energy symmetrically illuminating the target. It is found that a reasonable combination of neutron yield and areal density for OMEGA hydro-equivalent ignition is 3 to 6??10{sup 13} and ?0.3?g/cm{sup 2}, respectively, depending on the level of laser imprinting. This performance has not yet been achieved on OMEGA.

Nora, R.; Betti, R.; Bose, A.; Woo, K. M.; Christopherson, A. R.; Meyerhofer, D. D. [Laboratory for Laser Energetics, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States); Fusion Science Center, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States); Department of Physics and/or Mechanical Engineering, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States); Anderson, K. S.; Shvydky, A.; Marozas, J. A.; Collins, T. J. B.; Radha, P. B.; Hu, S. X.; Epstein, R.; Marshall, F. J.; Sangster, T. C. [Laboratory for Laser Energetics, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States); McCrory, R. L. [Laboratory for Laser Energetics, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States); Department of Physics and/or Mechanical Engineering, University of Rochester, 250 East River Road, Rochester, New York 14623-1299 (United States)

2014-05-15T23:59:59.000Z

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Dynamic symmetry of indirectly driven inertial confinement fusion capsules on the National Ignition Facility  

SciTech Connect (OSTI)

In order to achieve ignition using inertial confinement fusion it is important to control the growth of low-mode asymmetries as the capsule is compressed. Understanding the time-dependent evolution of the shape of the hot spot and surrounding fuel layer is crucial to optimizing implosion performance. A design and experimental campaign to examine sources of asymmetry and to quantify symmetry throughout the implosion has been developed and executed on the National Ignition Facility (NIF) [E. I. Moses et al., Phys. Plasmas 16, 041006 (2009)]. We have constructed a large simulation database of asymmetries applied during different time intervals. Analysis of the database has shown the need to measure and control the hot-spot shape, areal density distribution, and symmetry swings during the implosion. The shape of the hot spot during final stagnation is measured using time-resolved imaging of the self-emission, and information on the shape of the fuel at stagnation can be obtained from Compton radiography [R. Tommasini et al., Phys. Plasmas 18, 056309 (2011)]. For the first time on NIF, two-dimensional inflight radiographs of gas-filled and cryogenic fuel layered capsules have been measured to infer the symmetry of the radiation drive on the capsule. These results have been used to modify the hohlraum geometry and the wavelength tuning to improve the inflight implosion symmetry. We have also expanded our shock timing capabilities by the addition of extra mirrors inside the re-entrant cone to allow the simultaneous measurement of shock symmetry in three locations on a single shot, providing asymmetry information up to Legendre mode 4. By diagnosing the shape at nearly every step of the implosion, we estimate that shape has typically reduced fusion yield by about 50% in ignition experiments.

Town, R. P. J., E-mail: town2@llnl.gov; Bradley, D. K.; Kritcher, A.; Jones, O. S.; Rygg, J. R.; Tommasini, R.; Barrios, M.; Benedetti, L. R.; Berzak Hopkins, L. F.; Celliers, P. M.; Dppner, T.; Dewald, E. L.; Eder, D. C.; Field, J. E.; Glenn, S. M.; Izumi, N.; Haan, S. W.; Khan, S. F.; Ma, T.; Milovich, J. L. [Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, California 94551-0808 (United States); and others

2014-05-15T23:59:59.000Z

182

(Fusion energy research)  

SciTech Connect (OSTI)

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.

Phillips, C.A. (ed.)

1988-01-01T23:59:59.000Z

183

Pulse*Star Inertial Confinement Fusion Reactor: heat transfer loop and balance of plant considerations  

SciTech Connect (OSTI)

A conceptual heat transfer loop and balance of plant design for the Pulse*Star Inertial Confinement Fusion Reactor has been investigated and results are presented. The Pulse*Star reaction vessel, a perforated steel bell jar approximately 11 m in diameter, is immersed in Li/sub 17/Pb/sub 83/ coolant which flows through the perforations and forms a 1.5 m thick plenum of droplets around an 8 m diameter inner chamber. The reactor and associated pumps, piping, and steam generators are contained within a 17 m diameter pool of Li/sub 17/Pb/sub 83/ coolant to minimize structural requirements and occupied space, resulting in reduced cost. Four parallel heat transfer loops with flow rates of 5.5 m/sup 3//s each are necessary to transfer 3300 MWt of power. The steam generator design was optimized by finding the most cost-effective combination of heat exchanger area and pumping power. Power balance calculations based on an improved electrical conversion efficiency revealed a net electrical output of 1260 MWe to the bus bar and a resulting net efficiency of 39%. Suggested balance-of-plant layouts are also presented.

McDowell, M.W.; Murray, K.A.

1984-05-09T23:59:59.000Z

184

ADVANCED FUSION TECHNOLOGY RESEARCH AND DEVELOPMENT ANNUAL REPORT TO THE US DEPARTMENT OF ENERGY  

SciTech Connect (OSTI)

OAK A271 ADVANCED FUSION TECHNOLOGY RESEARCH AND DEVELOPMENT ANNUAL REPORT TO THE US DEPARTMENT OF ENERGY. The General Atomics (GA) Advanced Fusion Technology Program seeks to advance the knowledge base needed for next-generation fusion experiments, and ultimately for an economical and environmentally attractive fusion energy source. To achieve this objective, they carry out fusion systems design studies to evaluate the technologies needed for next-step experiments and power plants, and they conduct research to develop basic and applied knowledge about these technologies. GA's Advanced Fusion Technology program derives from, and draws on, the physics and engineering expertise built up by many years of experience in designing, building, and operating plasma physics experiments. The technology development activities take full advantage of the GA DIII-D program, the DIII-D facility and the Inertial Confinement Fusion (ICF) program and the ICF Target Fabrication facility.

PROJECT STAFF

2001-09-01T23:59:59.000Z

185

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

SciTech Connect (OSTI)

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 â??proof of principleâ? 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.

Slough, John

2011-12-10T23:59:59.000Z

186

Fusion Electricity A roadmap to the realisation of fusion energy  

E-Print Network [OSTI]

Fusion Electricity A roadmap to the realisation of fusion energy #12;28 European countries signed association EURaToM University of latvia LATVIA lithuanian Energy Institute LITHUANIA Ministry of Education and Research ROMANIA Ministry of Education, science, culture and sport SLOVENIA centro de Investigaciones

187

Present and future status of thermochemical cycles applied to fusion energy sources  

SciTech Connect (OSTI)

This paper reviews the status of current research on thermochemical hydrogen production cycles and identifies the needs for advanced cycles and materials research. The Los Alamos Scientific Laboratory (LASL) bismuth sulfate thermochemical cycle is characterized, and fusion reactor blanket concepts for both inertial and magnetic confinement schemes are presented as thermal energy sources for process heat applications.

Booth, L.A.; Cox, K.E.; Krakowski, R.A.; Pendergrass, J.H.

1980-01-01T23:59:59.000Z

188

Science/Fusion Energy Sciences FY 2007 Congressional Budget Fusion Energy Sciences  

E-Print Network [OSTI]

Science/Fusion Energy Sciences FY 2007 Congressional Budget Fusion Energy Sciences Funding Profile Adjustments FY 2006 Current Appropriation FY 2007 Request Fusion Energy Sciences Science,182 Total, Fusion Energy Sciences........... 266,947b 290,550 -2,906 287,644 318,950 Public Law

189

Science/Fusion Energy Sciences FY 2011 Congressional Budget Fusion Energy Sciences  

E-Print Network [OSTI]

Science/Fusion Energy Sciences FY 2011 Congressional Budget Fusion Energy Sciences Funding Profile FY 2010 Current Appropriation FY 2011 Request Fusion Energy Sciences Science 163,479 +57,399 182, Fusion Energy Sciences 394,518b +91,023 426,000 380,000 Public Law Authorizations: Public Law 95

190

JJ, IAP Cambridge January 20101 Fusion Energy & ITER:Fusion Energy & ITER  

E-Print Network [OSTI]

JJ, IAP Cambridge January 20101 Fusion Energy & ITER:Fusion Energy & ITER: Challenges Billions ITERITER startsstarts DEMODEMO decisiondecision:: Fusion impact? Energy without greenEnergy Fusion fuel: deuterium et tritium Deuterium: plenty in the ocean Tritium: made in situ from Lithium

191

Introduction to Fusion Energy Jerry Hughes  

E-Print Network [OSTI]

;Terrestrial energy sources have their origin in the nuclear fusion reactions of stars Supernova produces Earth #12;Terrestrial energy sources have their origin in the nuclear fusion reactions of stars energy sources have their origin in the nuclear fusion reactions of stars Geothermal Nuclear fission

192

A compact proton spectrometer for measurement of the absolute DD proton spectrum from which yield and ?R are determined in thin-shell inertial-confinement-fusion implosions  

SciTech Connect (OSTI)

A compact, step range filter proton spectrometer has been developed for the measurement of the absolute DD proton spectrum, from which yield and areal density (?R) are inferred for deuterium-filled thin-shell inertial confinement fusion implosions. This spectrometer, which is based on tantalum step-range filters, is sensitive to protons in the energy range 1-9 MeV and can be used to measure proton spectra at mean energies of ?1-3 MeV. It has been developed and implemented using a linear accelerator and applied to experiments at the OMEGA laser facility and the National Ignition Facility (NIF). Modeling of the proton slowing in the filters is necessary to construct the spectrum, and the yield and energy uncertainties are <10% in yield and 120?keV, respectively. This spectrometer can be used for in situ calibration of DD-neutron yield diagnostics at the NIF.

Rosenberg, M. J., E-mail: mrosenbe@mit.edu; Zylstra, A. B.; Frenje, J. A.; Rinderknecht, H. G.; Gatu Johnson, M.; Waugh, C. J.; Sguin, F. H.; Sio, H.; Sinenian, N.; Li, C. K.; Petrasso, R. D. [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States); Glebov, V. Yu.; Hohenberger, M.; Stoeckl, C.; Sangster, T. C. [Laboratory for Laser Energetics, University of Rochester, Rochester, New York 14623 (United States); Yeamans, C. B.; LePape, S.; Mackinnon, A. J.; Bionta, R. M.; Talison, B. [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States); and others

2014-10-15T23:59:59.000Z

193

Gas Transport and Control in Thick-Liquid Inertial Fusion Power Plants  

E-Print Network [OSTI]

advanced protection concept for NIF. Fusion Technology, 30(near-target experiments in NIF. Fusion Technology, 34(3):vered ?rst-wall systems for NIF. Fusion Technology, 34(3):

Debonnel, Christophe Sylvain

2006-01-01T23:59:59.000Z

194

The National Ignition Facility and the Path to Fusion Energy  

SciTech Connect (OSTI)

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.

Moses, E

2011-07-26T23:59:59.000Z

195

How does Casimir energy fall? III. Inertial forces on vacuum energy.  

E-Print Network [OSTI]

How does Casimir energy fall? III. Inertial forces on vacuum energy. K V Shajesh, Kimball A Milton, Prachi Parashar and Jeffrey A Wagner Oklahoma Center for High Energy Physics and Homer L. Dodge@nhn.ou.edu Date: 7 November 2007 Abstract. We have recently demonstrated that Casimir energy due to parallel

Milton, Kim

196

Z-Pinch Fusion for Energy Applications  

SciTech Connect (OSTI)

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.

SPIELMAN,RICK B.

2000-01-01T23:59:59.000Z

197

Fusion Energy Sciences Jobs  

Office of Science (SC) Website

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched5 Industrial CarbonArticles News(SC)Opportunities AdvancedOpportunitiesOffice

198

The Path to Magnetic Fusion Energy  

SciTech Connect (OSTI)

When the possibility of fusion as an energy source for electricity generation was realized in the 1950s, understanding of the plasma state was primitive. The fusion goal has been paced by, and has stimulated, the development of plasma physics. Our understanding of complex, nonlinear processes in plasmas is now mature. We can routinely produce and manipulate 100 million degree plasmas with remarkable finesse, and we can identify a path to commercial fusion power. The international experiment, ITER, will create a burning (self-sustained) plasma and produce 500 MW of thermal fusion power. This talk will summarize the progress in fusion research to date, and the remaining steps to fusion power.

Prager, Stewart (PPPL) [PPPL

2011-05-04T23:59:59.000Z

199

Distribution Category: Magnetic Fusion Energy  

E-Print Network [OSTI]

. Abdou Fusion Power Program October 1982 Invited paper presented at the International Conference by Mohamed A. Abdou ABSTRACT Key technological problems that influence tritium breeding in fusion blankets

Abdou, Mohamed

200

Plasma Physics and Fusion Energy Miklos Porkolab  

E-Print Network [OSTI]

Plasma Physics and Fusion Energy Miklos Porkolab MIT Plasma Science and Fusion Center Presented at the Fusion Power Associates Annual Meeting Washington, D.C. December 2-3, 2009 Porkolab_FPA_2009 #12;Proposed is sufficient physics to make ITER a success but much more to learn for DEMO grade plasmas See review talk

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Sean Finnegan & Ann Satsangi Fusion Energy Sciences  

E-Print Network [OSTI]

Energy (IFE) science. #12;HEDLP definition "High-energy-density laboratory plasma (HEDLP) physicsSean Finnegan & Ann Satsangi Fusion Energy Sciences Program Management Team for HEDLP Fusion Power Associates15 December 2011 Comments on the DOE-SC Program in High Energy Density Laboratory Plasma Science

202

Science/Fusion Energy Sciences FY 2008 Congressional Budget Fusion Energy Sciences  

E-Print Network [OSTI]

. Benefits Total world energy consumption has increased by more than 50% during the past 25 years, and given,182 31,317 Total, Fusion Energy Sciences 280,683a 318,950 427,850 Public Law Authorizations: Public LawScience/Fusion Energy Sciences FY 2008 Congressional Budget Fusion Energy Sciences Funding Profile

203

A Strategic Program Plan for Fusion Energy Sciences Fusion Energy Sciences  

E-Print Network [OSTI]

, while creating manageable waste and little risk to public safety and health. Making fusion energy a part light atoms such as those of hydrogen, holds great promise for clean and abundant energy produc- tionA Strategic Program Plan for Fusion Energy Sciences 1 Fusion Energy Sciences #12;2 Bringing

204

The National Ignition Facility (NIF) A Path to Fusion Energy  

SciTech Connect (OSTI)

Fusion energy has long been considered a promising clean, nearly inexhaustible source of energy. Power production by fusion micro-explosions of inertial confinement fusion (ICF) targets has been a long term research goal since the invention of the first laser in 1960. The NIF is poised to take the next important step in the journey by beginning experiments researching ICF ignition. Ignition on NIF will be the culmination of over thirty years of ICF research on high-powered laser systems such as the Nova laser at LLNL and the OMEGA laser at the University of Rochester as well as smaller systems around the world. NIF is a 192 beam Nd-glass laser facility at LLNL that is more than 90% complete. The first cluster of 48 beams is operational in the laser bay, the second cluster is now being commissioned, and the beam path to the target chamber is being installed. The Project will be completed in 2009 and ignition experiments will start in 2010. When completed NIF will produce up to 1.8 MJ of 0.35 {micro}m light in highly shaped pulses required for ignition. It will have beam stability and control to higher precision than any other laser fusion facility. Experiments using one of the beams of NIF have demonstrated that NIF can meet its beam performance goals. The National Ignition Campaign (NIC) has been established to manage the ignition effort on NIF. NIC has all of the research and development required to execute the ignition plan and to develop NIF into a fully operational facility. NIF will explore the ignition space, including direct drive, 2{omega} ignition, and fast ignition, to optimize target efficiency for developing fusion as an energy source. In addition to efficient target performance, fusion energy requires significant advances in high repetition rate lasers and fusion reactor technology. The Mercury laser at LLNL is a high repetition rate Nd-glass laser for fusion energy driver development. Mercury uses state-o-the art technology such as ceramic laser slabs and light diode pumping for improved efficiency and thermal management. Progress in NIF, NIC, Mercury, and the path forward for fusion energy will be presented.

Moses, E

2006-11-27T23:59:59.000Z

205

A compact proton spectrometer for measurement of the absolute DD proton spectrum from which yield and R are determined in thin-shell inertial-confinement-fusion  

E-Print Network [OSTI]

Energetics, University of Rochester, Rochester, New York 14623, USA 3 Lawrence Livermore National Laboratory neutron spectrometer for characterizing inertial confinement fusion implosions at OMEGA and the NIF Rev, Livermore, California 94550, USA 4 General Atomics, San Diego, California 92186, USA (Received 5 June 2014

206

Fusion: an energy source for synthetic fuels  

SciTech Connect (OSTI)

The decreasing availability of fossil fuels emphasizes the need to develop systems which will produce synthetic fuel to substitute for and supplement the natural supply. An important first step in the synthesis of liquid and gaseous fuels is the production of hydrogen. Thermonuclear fusion offers an inexhaustible source of energy for the production of hydrogen from water. Depending on design, electric generation efficiencies of approx. 40 to 60% and hydrogen production efficiencies by high temperature electrolysis of approx. 50 to 70% are projected for fusion reactors using high temperature blankets. Fusion/coal symbiotic systems appear economically promising for the first generation of commercial fusion synfuels plants. Coal production requirements and the environmental effects of large-scale coal usage would be greatly reduced by a fusion/coal system. In the long term, there could be a gradual transition to an inexhaustible energy system based solely on fusion.

Fillo, J A; Powell, J; Steinberg, M

1980-01-01T23:59:59.000Z

207

Inertial fusion energy power reactor fuel recovery system  

SciTech Connect (OSTI)

A conceptual design is proposed to support the recovery of un-expended fuel, ash, and associated post-detonation products resident in plasma exhaust from a {approx}2 GWIFE direct drive power reactor. The design includes systems for the safe and efficient collection, processing, and purification of plasma exhaust fuel components. The system has been conceptually designed and sized such that tritium bred within blankets, lining the reactor target chamber, can also be collected, processed, and introduced into the fuel cycle. The system will nominally be sized to process {approx}2 kg of tritium per day and is designed to link directly to the target chamber vacuum pumping system. An effort to model the fuel recovery system (FRS) using the Aspen Plus engineering code has commenced. The system design supports processing effluent gases from the reactor directly from the exhaust of the vacuum pumping system or in batch mode, via a buffer vessel in the Receiving and Analysis System. Emphasis is on nuclear safety, reliability, and redundancy as to maximize availability. The primary goal of the fuel recovery system design is to economically recycle components of direct drive IFE fuel. The FRS design is presented as a facility sub-system in the context of supporting the larger goal of producing safe and economical IFE power. (authors)

Gentile, C. A.; Kozub, T.; Langish, S. W.; Ciebiera, L. P. [Princeton Plasma Physics Laboratory, Princeton, NJ 08543 (United States); Nobile, A.; Wermer, J. [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Sessions, K. [Savannah River National Laboratory, Aiken, SC 29808 (United States)

2008-07-15T23:59:59.000Z

208

Systems Modeling For The Laser Fusion-Fission Energy (LIFE) Power Plant  

SciTech Connect (OSTI)

A systems model has been developed for the Laser Inertial Fusion-Fission Energy (LIFE) power plant. It combines cost-performance scaling models for the major subsystems of the plant including the laser, inertial fusion target factory, engine (i.e., the chamber including the fission and tritium breeding blankets), energy conversion systems and balance of plant. The LIFE plant model is being used to evaluate design trade-offs and to identify high-leverage R&D. At this point, we are focused more on doing self consistent design trades and optimization as opposed to trying to predict a cost of electricity with a high degree of certainty. Key results show the advantage of large scale (>1000 MWe) plants and the importance of minimizing the cost of diodes and balance of plant cost.

Meier, W R; Abbott, R; Beach, R; Blink, J; Caird, J; Erlandson, A; Farmer, J; Halsey, W; Ladran, T; Latkowski, J; MacIntyre, A; Miles, R; Storm, E

2008-10-02T23:59:59.000Z

209

Direct drive heavy-ion-beam inertial fusion at high coupling efficiency  

E-Print Network [OSTI]

M J of fusion yield. This NIF capsule design ab- sorbs 200capsules the size of the NIF capsule with heavy-ion beams (designs emerge, and, if the NIF's ignition campaign is also

Logan, B.G.

2008-01-01T23:59:59.000Z

210

Direct Drive Heavy-Ion-Beam Inertial Fusion at High Coupling Efficiency  

E-Print Network [OSTI]

of fusion yield [16]. This NIF capsule design absorbs 200 kJcapsules the size of the NIF capsule with heavy ion beams (designs emerge, and, i f the NIF's ignition campaign is also

Logan, B. Grant

2008-01-01T23:59:59.000Z

211

Culham Centre for Fusion Energy Fusion -A clean future  

E-Print Network [OSTI]

, scientists and engineers are working to make fusion a real option for our electricity supply.At the forefront consumption is expected to grow dramatically over the next fifty years as the world's population expands; Governments are divided over whether to include nuclear fission in their energy portfolios; and renewable

212

EPRI Fusion Energy Assessment July 19, 2011  

E-Print Network [OSTI]

EPRI Fusion Energy Assessment July 19, 2011 Palo Alto, CA Roadmapping an MFE Strategy R.J. Fonck research program RJF EPRI 2011 #12;ACCELERATE MFE VIA FUSION NUCLEAR S&T PROGRAM IN ITER TIMEFRAME #12;THE development · Similar efforts, and results, pursued by international partners RJF EPRI 2011 #12;THE SEQUENCE

213

RENEWABLE ENERGY GROUPS COVET FUSION'S BUDGET  

E-Print Network [OSTI]

RENEWABLE ENERGY GROUPS COVET FUSION'S BUDGET A group called the Energy Efficiency Education-effective and environmentally sound energy- efficiency and renewable energy programs." Rep. Philip R. Sharp (D-IN) and chair the resolution, H. Con. Res. 188). Sharp said "For too long, cost-effectiveefficiencyand renewable energy

214

Solenoid transport of a heavy ion beam for warm dense matterstudies and inertial confinement fusion  

SciTech Connect (OSTI)

From February to July 2006, I have been doing research as a guest at Lawrence Berkeley National Laboratory (LBNL), in the Heavy Ion Fusion group. This internship, which counts as one semester in my master's program in France, I was very pleased to do it in a field that I consider has the beauty of fundamental physics, and at the same time the special appeal of a quest for a long-term and environmentally-respectful energy source. During my stay at LBNL, I have been involved in three projects, all of them related to Neutralized Drift Compression Experiment (NDCX). The first one, experimental and analytical, has consisted in measuring the effects of the eddy currents induced by the pulsed magnets in the conducting plates of the source and diagnostic chambers of the Solenoid Transport Experiment (STX, which is a subset of NDCX). We have modeled the effect and run finite-element simulations that have reproduced the perturbation to the field. Then, we have modified WARP, the Particle-In-Cell code used to model the whole experiment, in order to import realistic fields including the eddy current effects and some details of each magnet. The second project has been to take part in a campaign of WARP simulations of the same experiment to understand the leakage of electrons that was observed in the experiment as a consequence to some diagnostics and the failure of the electrostatic electron trap. The simulations have shown qualitative agreement with the measured phenomena, but are still in progress. The third project, rather theoretical, has been related to the upcoming target experiment of a thin aluminum foil heated by a beam to the 1-eV range. At the beginning I helped by analyzing simulations of the hydrodynamic expansion and cooling of the heated material. But, progressively, my work turned into making estimates for the nature of the liquid/vapor two-phase flow. In particular, I have been working on criteria and models to predict the formation of droplets, their size, and their partial or total evaporation in the expanding flow.

Armijo, Julien

2006-10-01T23:59:59.000Z

215

Fusion EnergyFusion Energy Powering the XXI centuryPowering the XXI century  

E-Print Network [OSTI]

that the main cause of recent global warming is atmospheric pollution 20th International Atomic Energy AgencyNuclear Fusion (Safe & low level radioactive(Safe & low level radioactive waste, no atmospheric pollution)waste, no atmospheric pollution) 20th International Atomic Energy Agency, Fusion Energy Conference, Vilamoura, Portugal

216

Inertial confinement fusion quarterly report, October--December 1992. Volume 3, No. 1  

SciTech Connect (OSTI)

This report contains papers on the following topics: The Beamlet Front End: Prototype of a new pulse generation system;imaging biological objects with x-ray lasers; coherent XUV generation via high-order harmonic generation in rare gases; theory of high-order harmonic generation; two-dimensional computer simulations of ultra- intense, short-pulse laser-plasma interactions; neutron detectors for measuring the fusion burn history of ICF targets; the recirculator; and lasnex evolves to exploit computer industry advances.

Dixit, S.N. [ed.

1992-12-31T23:59:59.000Z

217

Alternative pathways to fusion energy (focus on Department of Energy  

E-Print Network [OSTI]

Alternative pathways to fusion energy (focus on Department of Energy Innovative Confinement for a restructured fusion energy science program [5] 1996 | FESAC: Opportunities in Alternative Confinement Concepts, suggests program for Innovative Concepts [1] 1995 | OTA TPX and the Alternates [2] 1995 | PCAST (given flat

218

Status of Research on Fusion Energy and Plasma Turbulence  

E-Print Network [OSTI]

Status of Research on Fusion Energy and Plasma Turbulence Candy, Waltz (General Atomics) Greg Project · A DOE, Office of Fusion Energy Sciences, SciDAC (Scientific Discovery Through Advanced Computing_annual.html #12;#12;#12;Progress in Fusion Energy Outpaced Computers J.B. Lister #12;Progress in Fusion

Hammett, Greg

219

MSc in Plasma Physics & Applications Laser Fusion Energy  

E-Print Network [OSTI]

. Thermonuclear fusion provides unlimited energy for all the world which is clean from long lived radioactiveMSc in Plasma Physics & Applications Laser Fusion Energy Why laser fusionDescription of the course fusion for energy production. This unique training scheme involves eight leading European centres

Paxton, Anthony T.

220

On the Loss of Wind-Induced Near-Inertial Energy to Turbulent Mixing in the Upper Ocean  

E-Print Network [OSTI]

On the Loss of Wind-Induced Near-Inertial Energy to Turbulent Mixing in the Upper Ocean XIAOMING-inertial energy available for ocean mixing at depth is, at most, 0.1 TW. This confirms a recent suggestion energy source for the diapycnal mixing in the ocean required to maintain the meridional over- turning

Miami, University of

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Fusion cross sections at deep subbarrier energies  

E-Print Network [OSTI]

A recent publication reports that heavy-ion fusion cross sections at extreme subbarrier energies show a continuous change of their logarithmic slope with decreasing energy, resulting in a much steeper excitation function compared with theoretical predictions. We show that the energy dependence of this slope is partly due to the asymmetric shape of the Coulomb barrier, that is its deviation from a harmonic shape. We also point out that the large low-energy slope is consistent with the surprisingly large surface diffusenesses required to fit recent high-precision fusion data.

K. Hagino; N. Rowley; M. Dasgupta

2003-02-12T23:59:59.000Z

222

Process for manufacture of inertial confinement fusion targets and resulting product  

DOE Patents [OSTI]

An ICF target comprising a spherical pellet of fusion fuel surrounded by a concentric shell; and a process for manufacturing the same which includes the steps of forming hemispheric shells of a silicon or other substrate material, adhering the shell segments to each other with a fuel pellet contained concentrically therein, then separating the individual targets from the parent substrate. Formation of hemispheric cavities by deposition or coating of a mold substrate is also described. Coatings or membranes may also be applied to the interior of the hemispheric segments prior to joining.

Masnari, Nino A. (Ann Arbor, MI); Rensel, Walter B. (Ann Arbor, MI); Robinson, Merrill G. (Ann Arbor, MI); Solomon, David E. (Ann Arbor, MI); Wise, Kensall D. (Ann Arbor, MI); Wuttke, Gilbert H. (Ypsilanti Township, Washtenaw County, MI)

1982-01-01T23:59:59.000Z

223

Nuclear Fusion: A Solution to the GlobalNuclear Fusion: A Solution to the Global Energy CrisisEnergy Crisis  

E-Print Network [OSTI]

Nuclear Fusion: A Solution to the GlobalNuclear Fusion: A Solution to the Global Energy Crisis.maclellan@strath.ac.uk Introduction and Motivation What is Nuclear Fusion? Laser Plasma Interactions The world, and particularly is harnessing the power of nuclear fusion. It is however, extremely difficult to sustain a fusion reaction

Strathclyde, University of

224

ROLE OF FUSION ENERGY IN A SUSTAINABLE GLOBAL ENERGY STRATEGY RLE DE L'NERGIE DE FUSION DANS UNE STRATGIE D'NERGIE  

E-Print Network [OSTI]

1-1 ROLE OF FUSION ENERGY IN A SUSTAINABLE GLOBAL ENERGY STRATEGY RLE DE L'NERGIE DE FUSION DANS. 1. Introduction 1. Introduction 1.1. Fusion energy 1.1. Energie de fusion Fusion energy is one of only a few truly long-term energy options. Since its inception in the 1950s, the vision of the fusion

Najmabadi, Farrokh

225

ROLE OF FUSION ENERGY IN A SUSTAINABLE GLOBAL ENERGY STRATEGY R LE DE L'NERGIE DE FUSION DANS UNE STRATGIE D'NERGIE  

E-Print Network [OSTI]

1-1 ROLE OF FUSION ENERGY IN A SUSTAINABLE GLOBAL ENERGY STRATEGY R LE DE L'NERGIE DE FUSION DANS. 1. Introduction 1. Introduction 1.1. Fusion energy 1.1. Energie de fusion Fusion energy is one of only a few truly long-term energy options. Since its inception in the 1950s, the vision of the fusion

226

Dependence of Shell Mix on Feedthrough in Direct Drive Inertial Confinement Fusion S. P. Regan, J. A. Delettrez, V. N. Goncharov, F. J. Marshall, J. M. Soures, V. A. Smalyuk, P. B. Radha, B. Yaakobi,  

E-Print Network [OSTI]

Dependence of Shell Mix on Feedthrough in Direct Drive Inertial Confinement Fusion S. P. Regan, J 87545, USA J. A. Frenje, C. K. Li, R. D. Petrasso, and F. H. Se´guin Plasma Science and Fusion Center May 2004) The mixing of cold, high-density shell plasma with the low-density, hot spot plasma

227

Laser Intertial Fusion Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

SciTech Connect (OSTI)

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

Kramer, K

2010-04-08T23:59:59.000Z

228

THE DEVELOPMENT OF HEAVY-ION ACCELERATORS AS DRIVERS FOR INERTIALLY CONFINED FUSION  

E-Print Network [OSTI]

1978 ]) e E HO- HIGH THERMONUCLEAR ENERGY GAINS HJT.H A. LQNfive "boilers'*, in which the thermonuclear pellet has been

Herrmannsfeldt, W.b.

2010-01-01T23:59:59.000Z

229

July 4, 2006/ARR An Overview of Fusion Technology and  

E-Print Network [OSTI]

Inertial Fusion Energy; UCSD's contribution involves the reaction chamber, final optics, and target to short-pulse high-energy laser irradiation, laser ablation plume dynamics, laser plasma light

Raffray, A. René

230

Bold Step by the World to Fusion Energy: ITER  

E-Print Network [OSTI]

THE DESIGN OF ITER · ITER PROJECT & ROLE OF THE UNITED STATES · PATH FROM ITER TO PRACTICAL FUSION POWER #12;Elements of a D-T Fusion Energy System ~ D-Li Plasma Heating Drivers or Confinement Balance of PlantD = nT = n TOTAL THERMAL ENERGY IN FUSION FUEL, DEFINE "ENERGY CONFINEMENT TIME", E ENERGY BALANCE dW d

231

Exact Dragging of Inertial Axes by Cosmic Energy-Currents on the Past Light-Cone  

E-Print Network [OSTI]

We prove exact rotational dragging of local inertial axes (= spin axes of gyroscopes) by arbitrary cosmic energy-currents on the past light-cone of the gyroscope for linear perturbations of Friedmann-Robertson-Walker cosmologies. Hence the principle formulated by Mach holds for arbitrary linear cosmological perturbations.

Christoph Schmid

2014-06-18T23:59:59.000Z

232

Fusion Power Associates Annual Meeting and Symposium Fusion Energy: Preparing for the NIF and ITER Era  

E-Print Network [OSTI]

Fusion Power Associates Annual Meeting and Symposium Fusion Energy: Preparing for the NIF and ITER of Directors 8:20 Presentation of Awards ­ S. Dean, President, FPA 8:30 Fusion at the Department of Energy Technology Program­ Stan Milora, ORNL 1:40 Issues and Opportunities from ITER Review ­ R. Hawryluk, PPPL 2

233

http://science.energy.gov/fes Establishing the scien.fic basis for fusion energy  

E-Print Network [OSTI]

http://science.energy.gov/fes Establishing the scien.fic basis for fusion energy and plasma science goals · Office of Science role regarding fusion energy: establish university engagement and leadership. Fusion materials science will be an increasing

234

Design of an electronic charged particle spectrometer to measure S R< on inertial fusion experiments  

E-Print Network [OSTI]

G permanent magnet, this instrument will uniquely determine particle identities and measure particle energies on the Omega Upgrade are actively underway. Using seven 512 512 charge coupled devices CCDs and a 7.5 k

235

Department of Advanced Energy Nuclear Fusion Research Education Program  

E-Print Network [OSTI]

24 Department of Advanced Energy Nuclear Fusion Research Education Program 23 8 23 to Nuclear Fusion Research Education Program 277-8561 5-1-5 1 04-7136-4092 http://www.k.u-tokyo.ac.jp/fusion: nemoto@criepi.denken.or.jp tel: 046-856-2121 12 http://www. k.u-tokyo.ac.jp/fusion-pro/ #12

Yamamoto, Hirosuke

236

Taming turbulence in magnetized plasmas: from fusion energy to  

E-Print Network [OSTI]

occurs (fusion of particle beams will not work...) Thermonuclear fusion in a confined plasma (T~10 keTaming turbulence in magnetized plasmas: from fusion energy to black hole accretion disks Troy?: In fusion plasmas turbulent leakage of heat and particles is a key issue. Sheared flow can suppress

237

Energy Sources Used for Fusion Welding  

E-Print Network [OSTI]

) Energy Sources Used for Fusion Welding Thomas W. Eagar, Massachusetts Institute of Technology WELDING AND JOINING processes are es- sential for the development of virtually every manufactured product this situation. First, welding and joining are multifaceted, both in terms of process variations (such as fas

Eagar, Thomas W.

238

Spectrometry of charged particles from inertial-confinement-fusion F. H. Seguin,a)  

E-Print Network [OSTI]

capsules with D2 , D3 He, DT, or DTH fuel in a shell of plastic, glass, or D2 ice, we now routinely make to neutrons, these reactions produce charged particles whose numbers and energy spectra are di- rectly related

239

A compact neutron spectrometer for characterizing inertial confinement fusion implosions at OMEGA and the NIF  

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

A compact spectrometer for measurements of the primary deuterium-tritium neutron spectrum has been designed and implemented on the OMEGA laser facility [T. Boehly et al. , Opt. Commun.133, 495 (1997)]. This instrument uses the recoil spectrometry technique, where neutrons produced in an implosion elastically scatter protons in a plastic foil, which are subsequently detected by a proton spectrometer. This diagnostic is currently capable of measuring the yield to ?10% accuracy, and mean neutron energy to ?50 keV precision. As these compact spectrometers can be readily placed at several locations around an implosion, effects of residual fuel bulk flows during burn can be measured. Future improvements to reduce the neutron energy uncertainty to 15?20 keV are discussed, which will enable measurements of fuel velocities to an accuracy of ?25?40 km/s.

Zylstra, A. B.; Gatu Johnson, M.; Frenje, J. A.; Seguin, F. H.; Rinderknecht, H. G.; Rosenberg, M. J.; Sio, H. W.; Li, C. K.; Petrasso, R. D.; McCluskey, M.; Mastrosimone, D.; Glebov, V. Yu.; Forrest, C.; Stoeckl, C.; Sangster, T. C.

2014-06-01T23:59:59.000Z

240

A compact neutron spectrometer for characterizing inertial confinement fusion implosions at OMEGA and the NIF  

SciTech Connect (OSTI)

A compact spectrometer for measurements of the primary deuterium-tritium neutron spectrum has been designed and implemented on the OMEGA laser facility [T. Boehly et al., Opt. Commun. 133, 495 (1997)]. This instrument uses the recoil spectrometry technique, where neutrons produced in an implosion elastically scatter protons in a plastic foil, which are subsequently detected by a proton spectrometer. This diagnostic is currently capable of measuring the yield to ?10% accuracy, and mean neutron energy to ?50 keV precision. As these compact spectrometers can be readily placed at several locations around an implosion, effects of residual fuel bulk flows during burn can be measured. Future improvements to reduce the neutron energy uncertainty to 15?20 keV are discussed, which will enable measurements of fuel velocities to an accuracy of ?25?40 km/s.

Zylstra, A. B., E-mail: zylstra@mit.edu; Gatu Johnson, M.; Frenje, J. A.; Sguin, F. H.; Rinderknecht, H. G.; Rosenberg, M. J.; Sio, H. W.; Li, C. K.; Petrasso, R. D. [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States); McCluskey, M.; Mastrosimone, D.; Glebov, V. Yu.; Forrest, C.; Stoeckl, C.; Sangster, T. C. [Laboratory for Laser Energetics, University of Rochester, Rochester, New York 14623 (United States)

2014-06-15T23:59:59.000Z

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Preliminary assessment and analysis of CO{sub 2} cleaning for an inertial fusion device  

SciTech Connect (OSTI)

The mechanisms of cleaning with carbon dioxide ice (CO{sub 2}) for the National Ignition Facility (NIF) application are discussed and analyzed. The compatibility between this cleaning process and the materials proposed for energy-relevant liquid-interaction experiments is examined. The cleaning mechanisms include kinetic shear stress, sublimation followed by thermophoresis, and solvent action. The study shows that the debris size could determine the efficiency of this cleaning technique. Furthermore, if the condensed vapor particulate becomes flattened and embedded inside the abscissa while hitting the surface, a large kinetic shear would be needed for debris removal which might damage the surface. 20 refs., 5 figs.

Ying, A.; Abdou, M. [Univ. of California, Los Angeles, CA (United States)

1996-12-31T23:59:59.000Z

242

The Heavy Ion Fusion Virtual National Laboratory The Heavy Ion Path to Fusion Energy  

E-Print Network [OSTI]

-consistent power plant design for a multi- beam induction linac, final focus and chamber propagationThe Heavy Ion Fusion Virtual National Laboratory The Heavy Ion Path to Fusion Energy Grant Logan Director Heavy-Ion Fusion Virtual National Laboratory Presented to FESAC Workshop on Development Paths

243

DANCING WITH THE STARSDANCING WITH THE STARS QUEST FOR FUSION ENERGYQUEST FOR FUSION ENERGY  

E-Print Network [OSTI]

Selection London (1859) #12;Hermann von Helmholtz Conservation of Energy Conversion of Mechanical Energy of the =Sun 264 10 Watts? Potential energy Solar power out Su pu n's lifetime t 14 6 10 .sec= ?= The Sun wouldDANCING WITH THE STARSDANCING WITH THE STARS QUEST FOR FUSION ENERGYQUEST FOR FUSION ENERGY Abhay

244

Energy Scaling Laws for Distributed Inference in Random Fusion Networks  

E-Print Network [OSTI]

the minimum spanning tree, and above by a suboptimal policy, referred to as Data Fusion for Markov Random, the policy with the minimum average energy consumption is bounded below by the average energy of fusion along models, Eu- clidean random graphs, stochastic geometry and data fusion. I. INTRODUCTION WE consider

Yukich, Joseph E.

245

Applications of Skyrme energy-density functional to fusion reactions spanning the fusion barriers  

E-Print Network [OSTI]

The Skyrme energy density functional has been applied to the study of heavy-ion fusion reactions. The barriers for fusion reactions are calculated by the Skyrme energy density functional with proton and neutron density distributions determined by using restricted density variational (RDV) method within the same energy density functional together with semi-classical approach known as the extended semi-classical Thomas-Fermi method. Based on the fusion barrier obtained, we propose a parametrization of the empirical barrier distribution to take into account the multi-dimensional character of real barrier and then apply it to calculate the fusion excitation functions in terms of barrier penetration concept. A large number of measured fusion excitation functions spanning the fusion barriers can be reproduced well. The competition between suppression and enhancement effects on sub-barrier fusion caused by neutron-shell-closure and excess neutron effects is studied.

Min Liu; Ning Wang; Zhuxia Li; Xizhen Wu; Enguang Zhao

2006-01-25T23:59:59.000Z

246

Vintage DOE: What is Fusion | Department of Energy  

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

Vintage DOE: What is Fusion Vintage DOE: What is Fusion January 10, 2011 - 12:45pm Addthis Ginny Simmons Ginny Simmons Former Managing Editor for Energy.gov, Office of Public...

247

Sub-barrier Fusion Cross Sections with Energy Density Formalism  

E-Print Network [OSTI]

We discuss the applicability of the energy density formalism (EDF) for heavy-ion fusion reactions at sub-barrier energies. For this purpose, we calculate the fusion excitation function and the fusion barrier distribution for the reactions of $^{16}$O with $^{154,}$$^{144}$Sm,$^{186}$W and $^{208}$Pb with the coupled-channels method. We also discuss the effect of saturation property on the fusion cross section for the reaction between two $^{64}$Ni nuclei, in connection to the so called steep fall-off phenomenon of fusion cross sections at deep sub-barrier energies.

F. Muhammad Zamrun; K. Hagino; N. Takigawa

2006-06-07T23:59:59.000Z

248

Sub-barrier Fusion Cross Sections with Energy Density Formalism  

SciTech Connect (OSTI)

We discuss the applicability of the energy density formalism (EDF) for heavy-ion fusion reactions at sub-barrier energies. For this purpose, we calculate the fusion excitation function and the fusion barrier distribution for the reactions of 16O with 154,144Sm, 186W and 208Pb with the coupled-channels method. We also discuss the effect of saturation property on the fusion cross section for the reaction between two 64Ni nuclei, in connection to the so called steep fall-off phenomenon of fusion cross sections at deep sub-barrier energies.

Zamrun, Muhammad; Hagino, F. K.; Takigawa, N. [Department of Physics, Tohoku University, 980-8578 (Japan)

2006-08-14T23:59:59.000Z

249

Design, fabrication and measurement of a novel cooling arm for fusion energy source  

E-Print Network [OSTI]

The issues of energy and environment are the main constraint of sustainable development in worldwide. Nuclear energy source is one important optional choice for long term sustainable development. The nuclear energy consists of fusion energy and fission energy. Compared with fission, inertial confinement fusion (ICF) is a kind of clean fusion energy and can generate large energy and little environmental pollution. ICF mainly consists of peripheral driver unit and target. The cooling arm is an important component of the target, which cools the hohlraum to maintain the required temperature and positions the thermal-mechanical package (TMP) assembly. This paper mainly investigates the cooling arm, including the structural design, the verticality of sidewall and the mechanical properties. The TMP assembly is uniformly clamped in its radial when using (111) crystal orientation silicon to fabricate cooling arm. The finite element method is used to design the structure of cooling arm with 16 clamping arms, and the MEMS technologies are employed to fabricate the micro-size cooling arm structure with high vertical sidewall. Finally, the mechanical test of cooling arm is taken, and the result can meet the requirement of positioning TMP assembly.

Shui-Dong Jiang; Jing-Quan Liu; Jia-Bin Mei; Bin Yang; Chun-Sheng Yang

2012-07-05T23:59:59.000Z

250

Journal of Fusion Energy, Vol. 19, No. 1, March 2000 ( 2001) Review of the Fusion Materials Research Program  

E-Print Network [OSTI]

, Livermore, CA 94551. 6 University of Wisconsin, Madison, WI 53706. 7 Columbia University, New York, NY 10027Journal of Fusion Energy, Vol. 19, No. 1, March 2000 ( 2001) Review of the Fusion Materials.S. Department of Energy (DOE) Fusion Energy Sciences Advisory Committee Panel on the Review of the Fusion

Abdou, Mohamed

251

INSTITUTE OF PHYSICS PUBLISHING PLASMA PHYSICS AND CONTROLLED FUSION Plasma Phys. Control. Fusion 48 (2006) B153B163 doi:10.1088/0741-3335/48/12B/S15  

E-Print Network [OSTI]

-drive). If the thermonuclear fuel is ignited and a burn wave propagates through the dense core, the fusion energy produced canINSTITUTE OF PHYSICS PUBLISHING PLASMA PHYSICS AND CONTROLLED FUSION Plasma Phys. Control. Fusion for direct-drive and fast ignition inertial confinement fusion R Betti1,2,3 , K Anderson1,3 , T R Boehly3

252

Department of Advanced Energy Nuclear Fusion Research Education Program  

E-Print Network [OSTI]

23 Department of Advanced Energy Nuclear Fusion Research Education Program 22 8 24) (1) (2) (3) (4) (5) (6) (7) (8) #12;- 7 - 23 Guide to Nuclear Fusion Research Education@criepi.denken.or.jp tel: 046-856-2121 12 http://www. k.u-tokyo.ac.jp/fusion-pro/ #12;- 3 - (1) TOEFL TOEIC

Yamamoto, Hirosuke

253

Department of Advanced Energy Nuclear Fusion Research Education Program  

E-Print Network [OSTI]

26 Department of Advanced Energy Nuclear Fusion Research Education Program 25 8 20) #12; 26 Guide to Nuclear Fusion Research Education Program 03-5841-6563 E-mail : ae: 050-336-27836 mail: sakai@isas.jaxa.jp tel: 050-3362-5919 , 7 12 http://www. k.u-tokyo.ac.jp/fusion

Yamamoto, Hirosuke

254

China To Build Its Own Fusion Reactor ENERGY TECH  

E-Print Network [OSTI]

Thermonuclear Experimental Reactor project reached agreement in Moscow Tuesday to construct the first fusion devices in thermonuclear reaction," and that "Chinese scientists started to develop a fusion operationChina To Build Its Own Fusion Reactor ENERGY TECH by Edward Lanfranco Beijing (UPI) July 1, 2005

255

A roadmap to the realiza/on of fusion energy  

E-Print Network [OSTI]

A roadmap to the realiza/on of fusion energy Francesco Romanelli, EFDA STAC #12;Why a roadmap · The need for a long-term strategy on energy Strategic Energy Technology plan, Energy Roadmap 2050 · In this context, Fusion must

256

Fast ignition when heating the central part of an inertial confinement fusion target by an ion beam  

SciTech Connect (OSTI)

We investigate the ignition and burning of a precompressed laser fusion target when it is rapidly heated by an ion beam with the formation of a temperature peak in the central part of the target. We present the results of our comprehensive numerical simulations of the problem that include the following components: (1) the target compression under the action of a profiled laser pulse, (2) the heating of the compressed target with spatially nonuniform density and temperature distributions by a beam of high-energy ions, and (3) the burning of the target with the initial spatial density distribution formed at the instant of maximum target compression and the initial spatial temperature distribution formed as a result of the compressed-target heating by an ion beam. The dependences of the threshold energies of the igniting ion beam and the thermonuclear gain on the width of the Gaussian beam ion energy spectrum have been established. The peculiarities of fast ignition by an ion beam related to the spatial distribution of parameters for the target precompressed by a laser pulse are discussed.

Guskov, S. Yu., E-mail: guskov@sci.lebedev.ru [Russian Academy of Sciences, Lebedev Physical Institute (Russian Federation); Zmitrenko, N. V. [Russian Academy of Sciences, Keldysh Institute of Applied Mathematics (Russian Federation); Ilin, D. V.; Sherman, V. E. [St. Petersburg State Technical University (Russian Federation)

2014-11-15T23:59:59.000Z

257

tTOURflAL DE PHYSIQUE Colloque C7, suppliment au n07, Tome 40, J u i l l e t 1979, page C7-775 DIAGNOSTICSPROGRAM FOR A MAGNETICALLY INSULATED ION DIODE FOR INERTIAL CONFINEMENT FUSION  

E-Print Network [OSTI]

, Albuquerque, flew Mexico, 87185. Inertial confinement fusion (ICF) schemes 2 require an ion power density of 1 the focused proton and carbon beam profiles via induced atomic excitation and thermal emission from targets exposure times of less than five nanoseconds. The resulting electron images were transported along a 2 k

Paris-Sud XI, Université de

258

Inertial Fusion Sciences and Applications 2003: State of the Art 2003, Published by the American Nuclear Society  

SciTech Connect (OSTI)

Collection of all papers presented and submitted at the IFSA2003 conference. Topics included target design and performance, fast ignition, plasma instabilities, laser technology, fusion reactor technology

Editors: B. A. Hammel; D. D. Meyerhofer; J. Meyer-ter-Vehn; H. Azechi. Organizing Chair: W. J. Hogan

2004-06-01T23:59:59.000Z

259

Fusion energy | Princeton Plasma Physics Lab  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickr Flickr Editor's note:Computing |FuelsFundingSciencesFusion

260

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 February 21, 2013 Tweet Widget Google Plus One Share on Facebook Scientists participating in...

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Nuclear Fusion (Nuclear Fusion ( )) as Clean Energy Source for Mankindas Clean Energy Source for Mankind  

E-Print Network [OSTI]

from renewables (wind power, solar power, hydropower, geothermal, ocean wave & tidal power, biomass energy resources (coal 43%, natural gas 19%, oil 6%, cogeneration 7%); ~21% by nuclear fission power the Moon. #12;ADVANTAGES OF FUSION · Abundant Supply of Fuel (deuterium and tritium) · No Risk of Nuclear

Chen, Yang-Yuan

262

Fun With Plasma Turbulence, From Fusion Energy to Black Holes  

E-Print Network [OSTI]

) & in astrophysics · Summarize status of fusion energy research · Cross-validation: statistical techniques useful Energy is Essentially Unchanged since 1980 Cumulative Funding 0 5000 10000 15000 20000 25000 30000 35000Fun With Plasma Turbulence, From Fusion Energy to Black Holes Greg Hammett Miller Visiting Research

Hammett, Greg

263

A novel method for modeling the neutron time of flight detector response in current mode to inertial confinement fusion experiments (invited)  

SciTech Connect (OSTI)

A novel method for modeling the neutron time of flight (nTOF) detector response in current mode for inertial confinement fusion experiments has been applied to the on-axis nTOF detectors located in the basement of the Z-Facility. It will be shown that this method can identify sources of neutron scattering, and is useful for predicting detector responses in future experimental configurations, and for identifying potential sources of neutron scattering when experimental set-ups change. This method can also provide insight on how much broadening neutron scattering contributes to the primary signals, which is then subtracted from them. Detector time responses are deconvolved from the signals, allowing a transformation from dN/dt to dN/dE, extracting neutron spectra at each detector location; these spectra are proportional to the absolute yield.

Nelson, A. J.; Cooper, G. W. [Department of Chemical and Nuclear Engineering, University of New Mexico, Albuquerque, New Mexico 87131 (United States); Ruiz, C. L.; Chandler, G. A.; Fehl, D. L.; Hahn, K. D.; Leeper, R. J.; Smelser, R.; Torres, J. A. [Sandia National Laboratories, Albuquerque, New Mexico 87185-1196 (United States)

2012-10-15T23:59:59.000Z

264

Improved Magnetic Fusion Energy Economics via Massive Resistive Electromagnets  

SciTech Connect (OSTI)

Abandoning superconductors for magnetic fusion reactors and instead using resistive magnet designs based on cheap copper or aluminum conductor material operating at "room temperature" (300 K) can reduce the capital cost per unit fusion power and simplify plant operations. By increasing unit size well beyond that of present magnetic fusion energy conceptual designs using superconducting electromagnets, the recirculating power fraction needed to operate resistive electromagnets can be made as close to zero as needed for economy without requiring superconductors. Other advantages of larger fusion plant size, such as very long inductively driven pulses, may also help reduce the cost per unit fusion power.

Woolley, R.D.

1998-08-19T23:59:59.000Z

265

How Fusion Energy Works | Department of Energy  

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

32 likes Every four minutes, another American home or business goes solar, but how do solar panels turn sunlight into energy? We'll answer that question and more Learn More...

266

Development of a polar direct-drive platform for studying inertial confinement fusion implosion mix on the National Ignition Facility  

SciTech Connect (OSTI)

Experiments were performed to develop a platform for the simultaneous measurement of mix and its effects on fusion burn. Two polar direct drive implosions of all-plastic capsules were conducted for the first time on the National Ignition Facility (NIF). To measure implosion trajectory and symmetry, area image backlighting of these capsules was also employed for the first time on NIF, an advance over previous 1-D slit imaging experiments, providing detailed symmetry data of the capsules as they imploded. The implosion trajectory and low-mode asymmetry seen in the resultant radiographs agreed with pre-shot predictions even though the 700 kJ drive energy produced laser beam intensities exceeding laser-plasma instability thresholds. Post-shot simulations indicate that the capsule yield was reduced by a factor of two compared to pre-shot predictions owing to as-shot laser drive asymmetries. The pre-shot predictions of bang time agreed within 200 ps with the experimental results. The second shot incorporated a narrow groove encircling the equator of the capsule. A predicted yield reduction factor of three was not observed.

Schmitt, Mark J.; Bradley, Paul A.; Cobble, James A.; Fincke, James R.; Hakel, Peter; Hsu, Scott C.; Krasheninnikova, Natalia S.; Kyrala, George A.; Magelssen, Glenn R.; Montgomery, David S.; Murphy, Thomas J.; Obrey, Kimberly A.; Shah, Rahul C.; Tregillis, Ian L.; Baumgaertel, Jessica A.; Wysocki, Frederick J.; Batha, Steven H. [Los Alamos National Laboratory, MS F699, Los Alamos, New Mexico 87545 (United States)] [Los Alamos National Laboratory, MS F699, Los Alamos, New Mexico 87545 (United States); Stephen Craxton, R.; McKenty, Patrick W. [Laboratory for Laser Energetics, University of Rochester, 250 E. River Road, Rochester, New York 14623 (United States)] [Laboratory for Laser Energetics, University of Rochester, 250 E. River Road, Rochester, New York 14623 (United States); Fitzsimmons, Paul [General Atomics, 3550 General Atomics Court, San Diego, California 92121 (United States)] [General Atomics, 3550 General Atomics Court, San Diego, California 92121 (United States); and others

2013-05-15T23:59:59.000Z

267

IOP PUBLISHING PLASMA PHYSICS AND CONTROLLED FUSION Plasma Phys. Control. Fusion 51 (2009) 014005 (9pp) doi:10.1088/0741-3335/51/1/014005  

E-Print Network [OSTI]

IOP PUBLISHING PLASMA PHYSICS AND CONTROLLED FUSION Plasma Phys. Control. Fusion 51 (2009) 014005 to inertial fusion [1] concerns the propagation and energy deposition of a fast electron beam in strongly change produced in the target material by the shock wave. While the initially cold solid target

Strathclyde, University of

268

Fusion Energy Sciences Advisory Committee Strategic Planning  

E-Print Network [OSTI]

with excellent safety features and modest environmental impact that is available to all nations. The quest of the fusion fuel from within the reactor. Throughout its history, the quest for fusion has been a global

269

Fusion Energy: Visions of the Future  

E-Print Network [OSTI]

worldwide · X-ray/neutron applications · US teams at KSU, NSTec 2009: LPP Focus Fusion-1 lab begins

270

Magnetized Target Fusion (MTF): Principles, Status, and International Collaboration  

SciTech Connect (OSTI)

Magnetized target fusion (MTF) is an approach to thermonuclear fusion that is intermediate between the two extremes of inertial and magnetic confinement. Target plasma preparation is followed by compression to fusion conditions. The use of a magnetic field to reduce electron thermal conduction and potentially enhance DT alpha energy deposition allows the compression rate to be drastically reduced relative to that for inertial confinement fusion. This leads to compact systems with target driver power and intensity requirements that are orders of magnitude lower than for ICF. A liner on plasma experiment has been proposed to provide a firm proof of principle for MTF.

Kirkpatrick, R.C.

1998-11-16T23:59:59.000Z

271

Commentary on A Conceptual Design of Transport Lines for a Heavy-Ion Inertial-Fusion Power Plant  

SciTech Connect (OSTI)

Some major system features are not stated but can be inferred. For example this is probably an engineering test facility, not a power plant driver, because the standoff from target to final magnet is only 5.0 m. The fusion target takes two-sided illumination with indirect drive using a total of 60 beam pulses: 10 pre-pulses (3.0 GeV) + 20 main pulses (4.0 GeV) from each side. On page 12 it's stated that the charge per beam pulse is 26.8 {micro}C, so we calculate pre-pulse: 20 x 3 GeV x 26.8 {micro}C = 1.608MJ, main pulse: 40 x 4 GeV x 26.8 {micro}C = 4.288MJ, total beam energy 5.896MJ. The beam ion mass ks 200 amu, so the species is Hg{sup +}. Therefore the mid-pulse velocities are: pre-pulse v = .1773c = 5.316 x 10{sup 7} m/s, main pulse v = .2040c = 6.114 x 10{sup 7} m/s, On page 12 it is stated that the pre-compression pulse length is L{sub 0} = 10.0m, and compression is by a 'factor of order 20'. They infer a final pulse length of about .5 m and final durations pre-pulse {tau} {approx} .5/5.316 x 10{sup 7} = 9.4 ns; main pulse {tau} {approx} .5/6.114 x 10{sup 7} = 8.2 ms. The magnetic rigidity of the beam ions is [B{rho}] = {gamma}m v/e = {l_brace} 112.0 T-m - prepulse/129.5 T-m - mainpulse{r_brace}.

Lee, E.P.

2011-04-13T23:59:59.000Z

272

Fusion-fission energy systems evaluation  

SciTech Connect (OSTI)

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.

Teofilo, V.L.; Aase, D.T.; Bickford, W.E.

1980-01-01T23:59:59.000Z

273

Heavy ion fusion science research for high energy density physics and fusion applications  

E-Print Network [OSTI]

cost direct plasma MHD direct conversion [38], as well as toT-lean targets and direct conversion for heavy ion fusion. [conversion loss of beam energy into x-rays. High ablation velocities with heavy ion direct

Logan, B.G.

2007-01-01T23:59:59.000Z

274

Key Points of STFC and EPSRC's Fusion for Energy EPSRC and STFC Councils have agreed a revised strategy for fusion for energy  

E-Print Network [OSTI]

Key Points of STFC and EPSRC's Fusion for Energy Strategy EPSRC and STFC Councils have agreed a revised strategy for fusion for energy research: 1) EPSRC and STFC will support fusion research as a long and demonstrating leadership to realise the goal of fusion energy. 2) EPSRC will develop a long term base funding

275

The National Ignition Facility Status and Plans for Laser Fusion and High-Energy-Density Experimental Studies  

E-Print Network [OSTI]

The National Ignition Facility (NIF) currently under construction at the University of California Lawrence Livermore National Laboratory (LLNL) is a 192-beam, 1.8-megajoule, 500-terawatt, 351-nm laser for inertial confinement fusion (ICF) and high-energy-density experimental studies. NIF is being built by the Department of Energy and the National Nuclear Security Agency (NNSA) to provide an experimental test bed for the U.S. Stockpile Stewardship Program to ensure the country's nuclear deterrent without underground nuclear testing. The experimental program will encompass a wide range of physical phenomena from fusion energy production to materials science. Of the roughly 700 shots available per year, about 10% will be dedicated to basic science research. Laser hardware is modularized into line replaceable units (LRUs) such as deformable mirrors, amplifiers, and multi-function sensor packages that are operated by a distributed computer control system of nearly 60,000 control points. The supervisory control roo...

Moses, E I

2001-01-01T23:59:59.000Z

276

Plasma Barodiffusion in Inertial-Confinement-Fusion Implosions: Application to Observed Yield Anomalies in Thermonuclear Fuel Mixtures  

E-Print Network [OSTI]

Anomalies in Thermonuclear Fuel Mixtures Peter Amendt, O. L. Landen, and H. F. Robey Lawrence Livermore National Laboratory, Livermore, California 94551, USA C. K. Li and R. D. Petrasso Plasma Science and Fusion performance in general, and upcoming igni- tion tuning campaigns on the National Ignition Facility (NIF) [4

277

Department of Advanced Energy Nuclear Fusion Research Education Program  

E-Print Network [OSTI]

25 Department of Advanced Energy Nuclear Fusion Research Education Program 24 8 21.Yasuhiro@jaxa.jp tel: 050-336-27836 mail: sakai@isas.jaxa.jp tel: 050-3362-5919 12 http://www. k.u-tokyo.ac.jp/fusion 15 (1) (2) (1) (2) (3) (4) (5) (6) (7) (8) (9) #12;- 8 - 25 Guide to Nuclear

Yamamoto, Hirosuke

278

Thermonuclear Fusion Energy : Assessment and Next Step Ren Pellat  

E-Print Network [OSTI]

Thermonuclear Fusion Energy : Assessment and Next Step René Pellat High Commissioner at the French 2000, Rome Abstract Fifty years of thermonuclear fusion work with no insurmountable road blocks have is well advanced through the International Thermonuclear Experimental Reactor (ITER) programme, which has

279

Inertial Fusion in NNSA N AT I O N AL N U C L E AR S E C U R I T Y AD M I N I S T R AT I O N OFFICE OF DEFENSE PROGRAMS  

E-Print Network [OSTI]

1 Inertial Fusion in NNSA N AT I O N AL N U C L E AR S E C U R I T Y AD M I N I S T R AT I O N, 2012 #12;2 ICF Program is critically important element of NNSA's Stockpile Stewardship Program (SSP to the Editor from Tom D'Agostino (NNSA Administrator) & Parney Albright (LLNL Director) stated NIF's primary

280

Fusion energy Fusion powers the Sun, and all stars, in which light nuclei fuse together at high temperatures  

E-Print Network [OSTI]

Fusion energy · Fusion powers the Sun, and all stars, in which light nuclei fuse together at high in excess of 100 million degrees, much higher than in the Sun. The hot hydrogen gas (known as a `plasma

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

The Energy-Momentum Tensor in General Relativity and in Alternative Theories of Gravitation, and the Gravitational vs. Inertial Mass  

E-Print Network [OSTI]

We establish a general relation between the canonical energy-momentum tensor of Lagrangian dynamics and the tensor that acts as the source of the gravitational field in Einstein's equations, and we show that there is a discrepancy between these tensors when there are direct nonminimal couplings between matter and the Riemann tensor. Despite this discrepancy, we give a general proof of the exact equality of the gravitational and inertial masses for any arbitrary system of matter and gravitational fields, even in the presence of nonminimal second-derivative couplings and-or linear or nonlinear second-derivative terms of any kind in the Lagrangian. The gravitational mass is defined by the asymptotic Newtonian potential at large distance from the system, and the inertial mass is defined by the volume integral of the energy density determined from the canonical energy-momentum tensor. In the Brans-Dicke scalar field theory, we establish that the nonminimal coupling and long range of the scalar field leads to an inequality between the gravitational and inertial masses, and we derive an exact formula for this inequality and confirm that it is approximately proportional to the gravitational self-energy (the Nordvedt effect), but with a constant of proportionality different from what is claimed in the published literature in calculations based on the PPN scheme. Similar inequalities of gravitational and inertial masses are expected to occur in other scalar and vector theories.

Hans C. Ohanian

2013-02-28T23:59:59.000Z

282

IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014002 (10pp) doi:10.1088/0029-5515/50/1/014002  

E-Print Network [OSTI]

Harnessing the energy of thermonuclear fusion reactions is one of the greatest challenges of our time. FusionIOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014002 (10pp) doi:10.1088/0029-5515/50/1/014002 ITER on the road to fusion energy Kaname Ikeda Director

283

Adiabatic Heavy Ion Fusion Potentials for Fusion at Deep Sub-barrier Energies  

E-Print Network [OSTI]

The fusion cross sections from well above barrier to extreme sub-barrier energies have been analysed using the energy (E) and angular momentum (L) dependent barrier penetration model ({\\small{ELDBPM}}). From this analysis, the adiabatic limits of fusion barriers have been determined for a wide range of heavy ion systems. The empirical prescription of Wilzynska and Wilzynski has been used with modified radius parameter and surface tension coefficient values consistent with the parameterization of the nuclear masses. The adiabatic fusion barriers calculated from this prescription are in good agreement with the adiabatic barriers deduced from {\\small{ELDBPM}} fits to fusion data. The nuclear potential diffuseness is larger at adiabatic limit, resulting in a lower $\\hbar\\omega$ leading to increase of "logarithmic slope" observed at energies well below the barrier. The effective fusion barrier radius and curvature values are anomalously smaller than the predictions of known empirical prescriptions. A detailed comparison of the systematics of fusion barrier with and without L-dependence has been presented.

S. V. S. Sastry; S. Kailas; A. K. Mohanty; A. Saxena

2003-11-12T23:59:59.000Z

284

An in-flight radiography platform to measure hydrodynamic instability growth in inertial confinement fusion capsules at the National Ignition Facility  

SciTech Connect (OSTI)

A new in-flight radiography platform has been established at the National Ignition Facility (NIF) to measure RayleighTaylor and RichtmyerMeshkov instability growth in inertial confinement fusion capsules. The platform has been tested up to a convergence ratio of 4. An experimental campaign is underway to measure the growth of pre-imposed sinusoidal modulations of the capsule surface, as a function of wavelength, for a pair of ignition-relevant laser drives: a low-foot drive representative of what was fielded during the National Ignition Campaign (NIC) [Edwards et al., Phys. Plasmas 20, 070501 (2013)] and the new high-foot [Dittrich et al., Phys. Rev. Lett. 112, 055002 (2014); Park et al., Phys. Rev. Lett. 112, 055001 (2014)] pulse shape, for which the predicted instability growth is much lower. We present measurements of Legendre modes 30, 60, and 90 for the NIC-type, low-foot, drive, and modes 60 and 90 for the high-foot drive. The measured growth is consistent with model predictions, including much less growth for the high-foot drive, demonstrating the instability mitigation aspect of this new pulse shape. We present the design of the platform in detail and discuss the implications of the data it generates for the on-going ignition effort at NIF.

Raman, K. S.; Smalyuk, V. A.; Casey, D. T.; Haan, S. W.; Hurricane, O. A.; Kroll, J. J.; Peterson, J. L.; Remington, B. A.; Robey, H. F.; Clark, D. S.; Hammel, B. A.; Landen, O. L.; Marinak, M. M.; Munro, D. H.; Salmonson, J. [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States); Hoover, D. E.; Nikroo, A. [General Atomics, San Diego, California 92121 (United States); Peterson, K. J. [Sandia National Laboratory, Albuquerque, New Mexico 87125 (United States)

2014-07-15T23:59:59.000Z

285

Placing Fusion in the spectrum of energy development  

E-Print Network [OSTI]

Exponential growth phase: energy production irrelevant My observations based on this graph. · First of all: since the exponential growth stops at typically 1% of the final capacity, the energy production during is irrelevant for energy production. #12;Niek Lopes Cardozo, Placing fusion in the energy development spectrum

286

A Review of the U.S. Department of Energy's Inertial Fusion Energy Program  

E-Print Network [OSTI]

average power laser (HAPL), and Z-Pinch drivers and associated technologies, including fast ignition (FI solutions. Three types of ``drivers'' for fuel compres- sion are presently studied: high on these drivers, along with the specific type 1 University of California 2 University of Rochester, 3 Naval

Tillack, Mark

287

Inertial Confinement Fusion, High Energy Density Plasmas and an Energy Source on Earth  

E-Print Network [OSTI]

Lawrence Livermore National Laboratory American Association for the Advancement of Science February 13 Lawrence Livermore National Laboratory under contract No. W-7405-Eng-48. #12;Tabak Snowmass We are making be tested at the National Ignition Facility(NIF) · NIF is scheduled for completion by 2009 ­ Physics

288

Fusion barrier distributions in systems with finite excitation energy  

E-Print Network [OSTI]

Eigen-channel approach to heavy-ion fusion reactions is exact only when the excitation energy of the intrinsic motion is zero. In order to take into account effects of finite excitation energy, we introduce an energy dependence to weight factors in the eigen-channel approximation. Using two channel problem, we show that the weight factors are slowly changing functions of incident energy. This suggests that the concept of the fusion barrier distribution still holds to a good approximation even when the excitation energy of the intrinsic motion is finite. A transition to the adiabatic tunneling, where the coupling leads to a static potential renormalization, is also discussed.

K. Hagino; N. Takigawa; A. B. Balantekin

1997-06-24T23:59:59.000Z

289

Fusion energy science: Clean, safe, and abundant energy through innovative science and technology  

SciTech Connect (OSTI)

Fusion energy science combines the study of the behavior of plasmas--the state of matter that forms 99% of the visible universe--with a vision of using fusion--the energy source of the stars--to create an affordable, plentiful, and environmentally benign energy source for humankind. The dual nature of fusion energy science provides an unfolding panorama of exciting intellectual challenge and a promise of an attractive energy source for generations to come. The goal of this report is a comprehensive understanding of plasma behavior leading to an affordable and attractive fusion energy source.

None

2001-01-01T23:59:59.000Z

290

Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

E-Print Network [OSTI]

scenario in a notional generation IV example sodium fastCommittee and the Generation IV Interna- tional Forum.Generation IV roadmap - crosscutting fuels and materials R&D

Kramer, Kevin James

2010-01-01T23:59:59.000Z

291

Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

E-Print Network [OSTI]

low density, high heat capacity liquid at room temp, verydensity liquid that would have a high heat capacity so itLiquid Na H 2 O Good moderator, chemically stable, high volumetric heat capacity,

Kramer, Kevin James

2010-01-01T23:59:59.000Z

292

Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

E-Print Network [OSTI]

DT Deuterium-Tritium DU Depleted Uranium FIMA Fission ofengine loaded with depleted uranium. In Proc. PHYSOR 2010,in the form of depleted uranium (DU). The remaining ~3,075

Kramer, Kevin James

2010-01-01T23:59:59.000Z

293

Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

E-Print Network [OSTI]

DT Deuterium-Tritium DU Depleted Uranium FIMA Fission ofengine loaded with depleted uranium. In Proc. PHYSOR 2010,fuel layer comprised of depleted uranium contained in

Kramer, Kevin James

2010-01-01T23:59:59.000Z

294

Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

E-Print Network [OSTI]

the HTTR project. Nuclear Engineering and Design, 233:163measurements. Nuclear Engineering Design, 33(92), [87] L.R.in Engineering - Nuclear Engineering in the Graduate

Kramer, Kevin James

2010-01-01T23:59:59.000Z

295

The Path to Magnetic Fusion Energy  

E-Print Network [OSTI]

for U.S. fusion research. This presentation proposes a mission for a major new U.S. facility, leading-even behind us, it is now time to address the logically first of the combined physics and technology% Japan 13% U.S. 10% China 10% India 10% Russia 10% S. Korea China Europe India Japan (w/EU) South Korea U

Princeton Plasma Physics Laboratory

296

Status of Safety and Environmental Activities in the US Fusion Program  

SciTech Connect (OSTI)

This paper presents an overview of recent safety efforts in both magnetic and inertial fusion energy. Safety has been a part of fusion design and operations since the inception of fusion research. Safety research and safety design support have been provided for a variety of experiments in both the magnetic and inertial fusion programs. The main safety issues are reviewed, some recent safety highlights are discussed and the programmatic impacts that safety research has had are presented. Future directions in the safety and environmental area are proposed.

Petti, D A; Reyes, S; Cadwallader, L C; Latkowski, J F

2004-09-02T23:59:59.000Z

297

Status of Safety and Environmental Activities in the US Fusion Program  

SciTech Connect (OSTI)

This paper presents an overview of recent safety efforts in both magnetic and inertial fusion energy. Safety has been a part of fusion design and operations since the inception of fusion research. Safety research and safety design support have been provided for a variety of experiments in both the magnetic and inertial fusion programs. The main safety issues are reviewed, some recent safety highlights are discussed and the programmatic impacts that safety research has had are presented. Future directions in the safety and environmental area are proposed.

David A. Petti; Susana Reyes; Lee C. Cadwallader; Jeffery F. Latkowski

2004-09-01T23:59:59.000Z

298

Status of Safety and Environmental Activities in the U.S. Fusion Program  

SciTech Connect (OSTI)

This paper presents an overview of recent safety efforts in both magnetic and inertial fusion energy. Safety has been a part of fusion design and operations since the inception of fusion research. Safety research and safety design support have been provided for a variety of experiments in both the magnetic and inertial fusion programs. The main safety issues are reviewed, some recent safety highlights are discussed and the programmatic impacts that safety research has had are presented. Future directions in the safety and environmental area are proposed.

Petti, D.A. [Idaho National Engineering and Environmental Laboratory (United States); Reyes, S. [Lawrence Livermore National Laboratory (United States); Cadwallader, L.C. [Idaho National Engineering and Environmental Laboratory (United States); Latkowski, J.F. [Lawrence Livermore National Laboratory (United States)

2005-05-15T23:59:59.000Z

299

Fusion Engineering and Design 41 (1998) 393400 Economic goals and requirements for competitive fusion energy  

E-Print Network [OSTI]

optimization and selection in mind, tradeoffs among system power density, recirculating power, plant and methodology of cost projections for magnetic-fusion-energy central-station electric power plants have been near- term research and development programs, for fu- sion and other advanced generation systems

California at San Diego, University of

300

Masked-backlighter technique used to simultaneously image x-ray absorption and x-ray emission from an inertial confinement fusion plasma  

SciTech Connect (OSTI)

A method to simultaneously image both the absorption and the self-emission of an imploding inertial confinement fusion plasma has been demonstrated on the OMEGA Laser System. The technique involves the use of a high-Z backlighter, half of which is covered with a low-Z material, and a high-speed x-ray framing camera aligned to capture images backlit by this masked backlighter. Two strips of the four-strip framing camera record images backlit by the high-Z portion of the backlighter, while the other two strips record images aligned with the low-Z portion of the backlighter. The emission from the low-Z material is effectively eliminated by a high-Z filter positioned in front of the framing camera, limiting the detected backlighter emission to that of the principal emission line of the high-Z material. As a result, half of the images are of self-emission from the plasma and the other half are of self-emission plus the backlighter. The advantage of this technique is that the self-emission simultaneous with backlighter absorption is independently measured from a nearby direction. The absorption occurs only in the high-Z backlit frames and is either spatially separated from the emission or the self-emission is suppressed by filtering, or by using a backlighter much brighter than the self-emission, or by subtraction. The masked-backlighter technique has been used on the OMEGA Laser System to simultaneously measure the emission profiles and the absorption profiles of polar-driven implosions.

Marshall, F. J., E-mail: fredm@lle.rochester.edu; Radha, P. B. [Laboratory for Laser Energetics, University of Rochester, Rochester, New York 14623 (United States)

2014-11-15T23:59:59.000Z

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Paths to fusion energy The next 30 years, the next 10 years  

E-Print Network [OSTI]

Paths to fusion energy The next 30 years, the next 10 years S. Prager The fusion era A roadmap to fusion energy discussed in US present GA PPPL MIT Plasma confinement research program #12;Issues for a fusion roadmap · Trade

302

FUSION ENERGY SCIENCES SUMMER STUDY 2002 Gerald Navratil  

E-Print Network [OSTI]

-2003, and to the review of burning plasma science by the National Academy of Sciences called for by FESAC and EnergyPLANS FOR FUSION ENERGY SCIENCES SUMMER STUDY 2002 Gerald Navratil Columbia University American Physical Society - Division of Plasma Physics 2001 Annual Meeting, Long Beach, CA 29 October - 2 November

303

Fusion Power Associates 34th Annual Meeting  

E-Print Network [OSTI]

· There are a number of steps along the path ­ demonstrate ignition on the National Ignition Facility (NIF with polar drive on the NIF. Summary The development of commercial inertial fusion energy (IFE are ­ Recommendation 2-1:The target physics programs on NIF, Nike, Omega, and Z should receive continued high priority

304

Energy & technology review, April 1995  

SciTech Connect (OSTI)

This publication presents research overviews on projects from the Lawrence Livermore laboratory. This issue provides information on microsphere targets for inertial confinement fusion experiments; laser fabrication of berllium components; and the kinetic energy interceptor.

Bookless, W.A.; Stull, S. [eds.

1995-04-01T23:59:59.000Z

305

Science/Fusion Energy Sciences FY 2006 Congressional Budget Fusion Energy Sciences  

E-Print Network [OSTI]

radioactive waste. A science-based approach to fusion offers the most deliberate path to commercial fusion chips for computers and other electronic devices, advanced video displays, innovative materials coatings, and the efficient destruction of chemical and radioactive wastes. The FES program is also pushing the boundaries

306

Two-dimensional simulations of thermonuclear burn in ignition-scale inertial confinement fusion targets under compressed axial magnetic fields  

SciTech Connect (OSTI)

We report for the first time on full 2-D radiation-hydrodynamic implosion simulations that explore the impact of highly compressed imposed magnetic fields on the ignition and burn of perturbed spherical implosions of ignition-scale cryogenic capsules. Using perturbations that highly convolute the cold fuel boundary of the hotspot and prevent ignition without applied fields, we impose initial axial seed fields of 20100 T (potentially attainable using present experimental methods) that compress to greater than 4 10{sup 4} T (400 MG) under implosion, thereby relaxing hotspot areal densities and pressures required for ignition and propagating burn by ?50%. The compressed field is high enough to suppress transverse electron heat conduction, and to allow alphas to couple energy into the hotspot even when highly deformed by large low-mode amplitudes. This might permit the recovery of ignition, or at least significant alpha particle heating, in submarginal capsules that would otherwise fail because of adverse hydrodynamic instabilities.

Perkins, L. J.; Logan, B. G.; Zimmerman, G. B.; Werner, C. J. [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States)] [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States)

2013-07-15T23:59:59.000Z

307

ICENES `91:Sixth international conference on emerging nuclear energy systems. Program and abstracts  

SciTech Connect (OSTI)

This document contains the program and abstracts of the sessions at the Sixth International Conference on Emerging Nuclear Energy Systems held June 16--21, 1991 at Monterey, California. These sessions included: The plenary session, fission session, fission and nonelectric session, poster session 1P; (space propulsion, space nuclear power, electrostatic confined fusion, fusion miscellaneous, inertial confinement fusion, {mu}-catalyzed fusion, and cold fusion); Advanced fusion session, space nuclear session, poster session 2P, (nuclear reactions/data, isotope separation, direct energy conversion and exotic concepts, fusion-fission hybrids, nuclear desalting, accelerator waste-transmutation, and fusion-based chemical recycling); energy policy session, poster session 3P (energy policy, magnetic fusion reactors, fission reactors, magnetically insulated inertial fusion, and nuclear explosives for power generation); exotic energy storage and conversion session; and exotic energy storage and conversion; review and closing session.

Not Available

1991-12-31T23:59:59.000Z

308

Damage Threats and Response of Final Optics for Laser-Fusion Power Plants  

E-Print Network [OSTI]

Damage Threats and Response of Final Optics for Laser-Fusion Power Plants M. S. Tillack1 , S. A the various damage threats and also provides nominal goals for a power plant. These goals are driven-1597 The final optics for laser-IFE (inertial fusion energy) power plants will be exposed to a variety of damage

Tillack, Mark

309

Journal of Fusion Energy, VoL 10, No. 2. 1991 An Accelerated Fusion Power Development Plan1  

E-Print Network [OSTI]

considerably since the 1970's energy crisis. Once-vigorous energy programs have been cut to subcritical funding in water. The fusion process itself is clean: It leaves no polluting byproducts or ra- dioactive "ashes

310

Framework for a Road Map to Magnetic Fusion Energy Status Report  

E-Print Network [OSTI]

Framework for a Road Map to Magnetic Fusion Energy Status Report Dale Meade for U. S. Magnetic paths: 1) ITER plus Fusion Nuclear Science Facility leading to a Tokamak DEMO 2) ITER directly Fusion Program Leaders Working Group MIT Independent Activities Period Plasma Science and Fusion Center

311

Technology spinoffs from the Magnetic Fusion Energy Program  

SciTech Connect (OSTI)

This document briefly describes eight new spin-offs from the fusion program: (1) cray timesharing system, (2) CRT touch panel, (3) magneform, (4) plasma separation process, (5) homopolar resistance welding, (6) plasma diagnostic development, (7) electrodeless microwave lamp, and (8) superconducting energy storage. (MOW)

Not Available

1984-02-01T23:59:59.000Z

312

Fusion Energy An Industry-Led Initiative  

E-Print Network [OSTI]

- Sunlight and its derivatives - Fission energy based on breeders - Clean coal (several hundreds of years

313

Fusion Policy Advisory Committee (FPAC)  

SciTech Connect (OSTI)

This document is the final report of the Fusion Policy Advisory Committee. The report conveys the Committee's views on the matters specified by the Secretary in his charge and subsequent letters to the Committee, and also satisfies the provisions of Section 7 of the Magnetic Fusion Energy Engineering Act of 1980, Public Law 96-386, which require a triennial review of the conduct of the national Magnetic Fusion Energy program. Three sub-Committee's were established to address the large number of topics associated with fusion research and development. One considered magnetic fusion energy, a second considered inertial fusion energy, and the third considered issues common to both. For many reasons, the promise of nuclear fusion as a safe, environmentally benign, and affordable source of energy is bright. At the present state of knowledge, however, it is uncertain that this promise will become reality. Only a vigorous, well planned and well executed program of research and development will yield the needed information. The Committee recommends that the US commit to a plan that will resolve this critically important issue. It also outlines the first steps in a development process that will lead to a fusion Demonstration Power Plant by 2025. The recommended program is aggressive, but we believe the goal is reasonable and attainable. International collaboration at a significant level is an important element in the plan.

Not Available

1990-09-01T23:59:59.000Z

314

Journal of Fusion Energy, VoL 4, Nos. 2/3, 1985 Panel Discussion  

E-Print Network [OSTI]

Office of Fusion Energy (OFE). One might take as a reasonable assumption that first generation fusionJournal of Fusion Energy, VoL 4, Nos. 2/3, 1985 Panel Discussion Technology Research energy program. Based on the new program plan, the parameters are a broad scientific and technology

Abdou, Mohamed

315

The Fusion Energy Program: The Role of TPX and Alternate Concepts  

E-Print Network [OSTI]

The Fusion Energy Program: The Role of TPX and Alternate Concepts February 1995 OTA-BP-ETI-141 GPO, The Fusion Energy Program: The Role of TPX and Alternate Concepts, OTA-BP-ETI-141 (Washington, DC: U of alternate concept research as conducted in the U.S. fusion energy program. While the focus of the study

316

Laser Inertial Fusion-based  

E-Print Network [OSTI]

Speed Gas CoolingHigh Power Diode Arrays 3 W/cm2 cooling (average)100 kW peak power #12;8 #12;20 m Power Associates December 3rd, 2009 #12;#12;#12;Laser 2.8 MJ (1), 2.3 MJ (2) @ 15 Hz 14% Power cycle MWe Pumps / aux. power To grid 1001 MWe Process heat 1329 MWe 839 MWth LIFE power flow for a hotspot

317

MagnetoInertial Fusion Description  

E-Print Network [OSTI]

2009). The key point here is that breakeven-class MIF driver facilities, which already exist (e.g., ATLAS or Z/Z-Beamlet), cost US$200M compared to the multi-US$B ITER and NIF. For this reason alone, MIF introduced seed magnetic fields into the center of targets at the OMEGA laser facility, and compressed those

318

Stauts of the Laser Inertial Fusion Energy (LIFE) Hohlraum Point Design  

SciTech Connect (OSTI)

Progress on the hohlraum point design for the LIFE engine is described. New features in the original design [Amendt et al., Fus. Sci. Technol. 60, 49 (2011)] are incorporated that address the imperatives of low target cost, high manufacturing throughput, efficient and prompt material recycling, an ability for near-term testing of key target design uncertainties on the National Ignition Facility, and robustness to target chamber environment and injection insults. To this end, the novel use of Pb hohlraums and aerogel-supported liquid DT fuel loading within a high-density-carbon (HDC) ablator is implemented in the hohlraum point design.

Amendt, P; Dunne, M; Ho, D; Lasinski, B; Meeker, D; Ross, J S

2012-04-10T23:59:59.000Z

319

Inertial range turbulence in kinetic plasmas  

E-Print Network [OSTI]

The transfer of turbulent energy through an inertial range from the driving scale to dissipative scales in a kinetic plasma followed by the conversion of this energy into heat is a fundamental plasma physics process. A theoretical foundation for the study of this process is constructed, but the details of the kinetic cascade are not well understood. Several important properties are identified: (a) the conservation of a generalized energy by the cascade; (b) the need for collisions to increase entropy and realize irreversible plasma heating; and (c) the key role played by the entropy cascade--a dual cascade of energy to small scales in both physical and velocity space--to convert ultimately the turbulent energy into heat. A strategy for nonlinear numerical simulations of kinetic turbulence is outlined. Initial numerical results are consistent with the operation of the entropy cascade. Inertial range turbulence arises in a broad range of space and astrophysical plasmas and may play an important role in the thermalization of fusion energy in burning plasmas.

G. G. Howes

2007-11-27T23:59:59.000Z

320

IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 49 (2009) 104010 (12pp) doi:10.1088/0029-5515/49/10/104010  

E-Print Network [OSTI]

IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 49 (2009) 104010. Zwingmann CEA, IRFM, F-13108 St Paul-lez-Durance, France 1 Associazione EURATOM-ENEA sulla Fusione, C;Nucl. Fusion 49 (2009) 104010 G. Giruzzi et al 9 LJAD, U.M.R. C.N.R.S. No 6621, Universit´e de Nice

?cole Normale Supérieure

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

U.S. to Participate in Fusion Project Thursday, January 30, 2003 http://www.nytimes.com/aponline/national/AP-Fusion-Energy-Plan.html?pagewanted=  

E-Print Network [OSTI]

States plan to build a $5 billion fusion reactor, called the International Thermonuclear ExperimentalU.S. to Participate in Fusion Project Thursday, January 30, 2003 http://www.nytimes.com/aponline/national/AP-Fusion-Energy-Plan.html?pagewanted= print&position=top Page: 1 January 30, 2003 U.S. to Participate in Fusion Project By THE ASSOCIATED

322

Nuclear Fusion Energy Research Ghassan Antar  

E-Print Network [OSTI]

to address these issues. In particular there has been consistent emphasis on nuclear reactor accidents since the Chernobyl accident by the International Atomic Energy Agency (IAEA) and the World Meteorological

Shihadeh, Alan

323

January 25, 2008/ARR 1 Heat and Mass Transfer in Fusion Energy  

E-Print Network [OSTI]

January 25, 2008/ARR 1 Heat and Mass Transfer in Fusion Energy Applications: from the "Very Cold, CA January 25, 2008 #12;January 25, 2008/ARR 2 Unique Set of Conditions Associated with Fusion · Realization of fusion energy imposes considerable challenges in the areas of engineering, physics and material

Raffray, A. René

324

Multi-University Research to Advance Discovery Fusion Energy Science using a  

E-Print Network [OSTI]

Dept of Applied Physics and Applied Math, Columbia University, New York, NY Plasma Science and FusionMulti-University Research to Advance Discovery Fusion Energy Science using a Superconducting Center, MIT, Cambridge, MA Outline · Intermediate scale discovery fusion energy science needs support

325

January 14, 2014 MIT PSFC IAP Seminar Series Introduction to Fusion Energy Research  

E-Print Network [OSTI]

; to build a fusion reactor, and build a fusion power plant There has been tremendous progress in fusion energy research is an exciting, fast-moving international research area #12;January 14, 2014 MIT PSFC IAP car's gas engine Your fireplace Gravitational force: Falling water transforms potential energy

326

Energy payback and CO{sub 2} gas emissions from fusion and solar photovoltaic electric power plants. Final report to Department of Energy, Office of Fusion Energy Sciences  

SciTech Connect (OSTI)

A cradle-to-grave net energy and greenhouse gas emissions analysis of a modern photovoltaic facility that produces electricity has been performed and compared to a similar analysis on fusion. A summary of the work has been included in a Ph.D. thesis titled ''Life-cycle assessment of electricity generation systems and applications for climate change policy analysis'' by Paul J. Meier, and a synopsis of the work was presented at the 15th Topical meeting on Fusion Energy held in Washington, DC in November 2002. In addition, a technical note on the effect of the introduction of fusion energy on the greenhouse gas emissions in the United States was submitted to the Office of Fusion Energy Sciences (OFES).

Kulcinski, G.L.

2002-12-01T23:59:59.000Z

327

IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014001 (11pp) doi:10.1088/0029-5515/50/1/014001  

E-Print Network [OSTI]

IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014001 its worth. Looking at the way forward, this vision constitutes a strong basis to harness fusion energy Cabinet of the French High Commissioner for Atomic Energy CEA, 91191 Gif-sur-Yvette, France Received 19

328

Princeton Plasma Physics Lab - Fusion energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 - SeptemberMicroneedles for4-16 FOR Primary Author Last Nameenergy The energy

329

NIF-0205-10331 Clean Energy  

E-Print Network [OSTI]

Lawrence Livermore National Laboratory--1960 3 days later Lawrence Livermore National Laboratory--1960 3P8430 #12;NIF-0205-10331 15EIM/sb P8434 Clean Energy: Humankind's Challenge #12;The National Ignition Facility P8435NIF-0105-10154-r2 31EIM/sb Magnetic Fusion Energy Inertial Fusion Energy Biggest

330

Workshop on Accelerators for Heavy Ion Fusion: Summary Report of the Workshop  

SciTech Connect (OSTI)

The Workshop on Accelerators for Heavy Ion Fusion was held at Lawrence Berkeley National Laboratory May 23-26, 2011. The workshop began with plenary sessions to review the state of the art in HIF (heavy ion fusion), followed by parallel working groups, and concluded with a plenary session to review the results. There were five working groups: IFE (inertial fusion energy) targets, RF approach to HIF, induction accelerator approach to HIF, chamber and driver interface, ion sources and injectors.

Seidl, P.A.; Barnard, J.J.

2011-04-29T23:59:59.000Z

331

The National Ignition Facility: Status and Plans for Laser Fusion and High-Energy-Density Experimental Studies  

E-Print Network [OSTI]

The National Ignition Facility (NIF) currently under construction at the University of California Lawrence Livermore National Laboratory (LLNL) is a 192-beam, 1.8-megajoule, 500-terawatt, 351-nm laser for inertial confinement fusion (ICF) and high-energy-density experimental studies. NIF is being built by the Department of Energy and the National Nuclear Security Agency (NNSA) to provide an experimental test bed for the U.S. Stockpile Stewardship Program to ensure the country's nuclear deterrent without underground nuclear testing. The experimental program will encompass a wide range of physical phenomena from fusion energy production to materials science. Of the roughly 700 shots available per year, about 10% will be dedicated to basic science research. Laser hardware is modularized into line replaceable units (LRUs) such as deformable mirrors, amplifiers, and multi-function sensor packages that are operated by a distributed computer control system of nearly 60,000 control points. The supervisory control room presents facility-wide status and orchestrates experiments using operating parameters predicted by physics models. A network of several hundred front-end processors (FEPs) implements device control. The object-oriented software system is implemented in the Ada and Java languages and emphasizes CORBA distribution of reusable software objects. NIF is currently scheduled to provide first light in 2004 and will be completed in 2008.

E. I. Moses

2001-11-09T23:59:59.000Z

332

Fusion Energy Advisory Committee: Advice and recommendations to the US Department of Energy in response to the charge letter of September 1, 1992  

SciTech Connect (OSTI)

This document is a compilation of the written records that relate to the Fusion Energy Advisory Committee`s deliberations with regard to the Letter of Charge received from the Director of Energy Research, dated September 1, 1992. During its sixth meeting, held in March 1993, FEAC provided a detailed response to the charge contained in the letter of September 1, 1992. In particular, it responded to the paragraph: ``I would like the Fusion Energy Advisory Committee (FEAC) to evaluate the Neutron Interactive Materials Program of the Office of Fusion Energy (OFE). Materials are required that will satisfy the service requirements of components in both inertial and magnetic fusion reactors -- including the performance, safety, economic, environmental, and recycle/waste management requirements. Given budget constraints, is our program optimized to achieve these goals for DEMO, as well as to support the near-term ITER program?`` Before FEAC could generate its response to the charge in the form of a letter report, one member, Dr. Parker, expressed severe concerns over one of the conclusions that the committee had reached during the meeting. It proved necessary to resolve the issue in public debate, and the matter was reviewed by FEAC for a second time, during its seventh meeting, held in mid-April, 1993. In order to help it to respond to this charge in a timely manner, FEAC established a working group, designated Panel No. 6, which reviewed the depth and breadth of the US materials program, and its interactions and collaborations with international programs. The panel prepared background material, included in this report as Appendix I, to help FEAC in its deliberations.

Not Available

1993-04-01T23:59:59.000Z

333

Fusion Energy Sciences Review Meeting Logistics  

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

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334

Hydrogen Hydrogen FusionFusionFusionFusionFusionFusion  

E-Print Network [OSTI]

100.000 years LNGS Laboratori Nazionali del Gran Sasso Borexino THE THERMONUCLEAR FUSION REACTIONHydrogen Hydrogen Fusion Deuterium FusionFusionFusionFusionFusionFusion THE SUN AS BOREXINO SEES

Heiz, Ulrich

335

Designing Radiation Resistance in Materials for Fusion Energy  

SciTech Connect (OSTI)

Proposed fusion and advanced (Generation IV) fission energy systems require high performance materials capable of satisfactory operation up to neutron damage levels approaching 200 atomic displacements per atom with large amounts of transmutant hydrogen and helium isotopes. After a brief overview of fusion reactor concepts and radiation effects phenomena in structural and functional (non-structural) materials, three fundamental options for designing radiation resistance are outlined: Utilize matrix phases with inherent radiation tolerance, select materials where vacancies are immobile at the design operating temperatures, or construct high densities of point defect recombination sinks. Environmental and safety considerations impose several additional restrictions on potential materials systems, but reduced activation ferritic/martensitic steels (including thermomechanically treated and oxide dispersion strengthened options) and silicon carbide ceramic composites emerge as robust structural materials options. Materials modeling (including computational thermodynamics) and advanced manufacturing methods are poised to exert a major impact in the next ten years.

Zinkle, Steven J [University of Tennessee (UT)] [University of Tennessee (UT); Snead, Lance Lewis [ORNL] [ORNL

2014-01-01T23:59:59.000Z

336

IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014006 (6pp) doi:10.1088/0029-5515/50/1/014006  

E-Print Network [OSTI]

.57.-z, 89.30.Ji 1. Laser and laser fusion from past and present to future In 1917, Albert EinsteinIOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014006 energized implosion could be utilized for energy generation. Today, there are many facilities worldwide

337

IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 49 (2009) 095020 (12pp) doi:10.1088/0029-5515/49/9/095020  

E-Print Network [OSTI]

IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 49 (2009) 095020-scale fluctuations, in contrast to present day experiments where, in general, relatively low energy fast ions of alpha particles produced in DT reactions as the main heating source. Fusion alphas, with small

Zonca, Fulvio

338

Journul of Fusion Energy. Yo/. 5. No. 2. 1986 Introduction to Panel Discussions  

E-Print Network [OSTI]

Journul of Fusion Energy. Yo/. 5. No. 2. 1986 -- Introduction to Panel Discussions Whither Fusion Research? Robert L. Hirsch' . An unnamed former fusion program director retired and felt he needed some friend appeared before the major monk for his annual two words, which were, " Room cold." The monk nodded

339

Fusion Lecture Summary Eugene S. Evans  

E-Print Network [OSTI]

March 31, 2010 2 / 15 #12;National Ignition Facility (NIF) location: Lawrence Livermore National. Evans (2010) Fusion Lecture Summary March 31, 2010 1 / 15 #12;Outline 1 Overview of NIF Specifications Timeline Goals 2 Inertial Confinement Fusion (ICF) 3 Science at NIF 4 Fusion and the Future Laser Inertial

Budker, Dmitry

340

ENERGY ISSUES WORKING GROUP ON LONG-TERM VISIONS FOR FUSION POWER  

E-Print Network [OSTI]

ENERGY ISSUES WORKING GROUP ON LONG-TERM VISIONS FOR FUSION POWER Don Steiner, Jeffrey Freidberg Farrokh Najmabadi William Nevins , and John Perkins The Energy Issues Working Group on Long-Term Visions energy production in the next century? 2. What is fusion's potential for penetrating the energy market

Najmabadi, Farrokh

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

An Assessment of the Department of Energy's Office of Fusion Energy  

E-Print Network [OSTI]

competences and with regard for appropriate balance. This project was supported by the Department of Energy reserved. Printed in the United States of America #12;The National Academy of Sciences is a privateAn Assessment of the Department of Energy's Office of Fusion Energy Sciences Program NATIONAL

342

Beryllium pressure vessels for creep tests in magnetic fusion energy  

SciTech Connect (OSTI)

Beryllium has interesting applications in magnetic fusion experimental machines and future power-producing fusion reactors. Chief among the properties of beryllium that make these applications possible is its ability to act as a neutron multiplier, thereby increasing the tritium breeding ability of energy conversion blankets. Another property, the behavior of beryllium in a 14-MeV neutron environment, has not been fully investigated, nor has the creep behavior of beryllium been studied in an energetic neutron flux at thermodynamically interesting temperatures. This small beryllium pressure vessel could be charged with gas to test pressures around 3, 000 psi to produce stress in the metal of 15,000 to 20,000 psi. Such stress levels are typical of those that might be reached in fusion blanket applications of beryllium. After contacting R. Powell at HEDL about including some of the pressure vessels in future test programs, we sent one sample pressure vessel with a pressurizing tube attached (Fig. 1) for burst tests so the quality of the diffusion bond joints could be evaluated. The gas used was helium. Unfortunately, budget restrictions did not permit us to proceed in the creep test program. The purpose of this engineering note is to document the lessons learned to date, including photographs of the test pressure vessel that show the tooling necessary to satisfactorily produce the diffusion bonds. This document can serve as a starting point for those engineers who resume this task when funds become available.

Neef, W.S.

1990-07-20T23:59:59.000Z

343

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

SciTech Connect (OSTI)

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.

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

1994-03-01T23:59:59.000Z

344

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

SciTech Connect (OSTI)

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.

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

1988-11-01T23:59:59.000Z

345

On the nuclear interaction. Potential, binding energy and fusion reaction  

E-Print Network [OSTI]

The nuclear interaction is responsible for keeping neutrons and protons joined in an atomic nucleus. Phenomenological nuclear potentials, fitted to experimental data, allow one to know about the nuclear behaviour with more or less success where quantum mechanics is hard to be used. A nuclear potential is suggested and an expression for the potential energy of two nuclear entities, either nuclei or nucleons, is developed. In order to estimate parameters in this expression, some nucleon additions to nuclei are considered and a model is suggested as a guide of the addition process. Coulomb barrier and energy for the addition of a proton to each one of several nuclei are estimated by taking into account both the nuclear and electrostatic components of energy. Studies on the binding energies of several nuclei and on the fusion reaction of two nuclei are carried out.

I. Casinos

2008-05-22T23:59:59.000Z

346

ICF & High Energy Density (HED) Research Future Directions and Plans  

E-Print Network [OSTI]

and ICF activities Energy Balance FY08 Getting the Job Done First credible ignition attempt FYNSP 20 YearsICF & High Energy Density (HED) Research Future Directions and Plans Fusion Power Associates of Defense Science and Inertial Fusion National Nuclear Security Administration US Dept. of Energy #12

347

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

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartment of Energy 601 High26-OPAM63-OPAMGuidanceAVTA …Ford Fusion HEV

348

NERSC Role in Fusion Energy Science Research Katherine Yelick  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Opticalhttp://www.fnal.gov/directorate/nalcal/nalcal02_07_05_files/nalcal.gif Directorate -News,Advanced ScientificFusion

349

Fusion Energy Division annual progress report, period ending December 31, 1989  

SciTech Connect (OSTI)

The Fusion Program of Oak Ridge National Laboratory (ORNL) carries out research in most areas of magnetic confinement fusion. The program is directed toward the development of fusion as an energy source and is a strong and vital component of both the US fusion program and the international fusion community. Issued as the annual progress report of the ORNL Fusion Energy Division, this report also contains information from components of the Fusion Program that are carried out by other ORNL organizations (about 15% of the program effort). The areas addressed by the Fusion Program and discussed in this report 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. Highlights from program activities are included in this report.

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

1991-07-01T23:59:59.000Z

350

Feb-15 2000 1 D.Jassby ELECTRICAL ENERGY REQUIREMENTS FOR ATW AND FUSION  

E-Print Network [OSTI]

Feb-15 2000 1 D.Jassby ELECTRICAL ENERGY REQUIREMENTS FOR ATW AND FUSION NEUTRONS by D.L. JASSBY the electrical energy requirements of accelerator (ATW) and fusion plants designed to transmute nuclides the same electrical energy requirement per available blanket neutron when the blanket coverage

351

Feb15 2000 1 D.Jassby ELECTRICAL ENERGY REQUIREMENTS FOR ATW AND FUSION  

E-Print Network [OSTI]

Feb15 2000 1 D.Jassby ELECTRICAL ENERGY REQUIREMENTS FOR ATW AND FUSION NEUTRONS by D.L. JASSBY the electrical energy requirements of accelerator (ATW) and fusion plants designed to transmute nuclides the same electrical energy requirement per available blanket neutron when the blanket coverage

352

Magnetized Target Fusion (MTF): A Low-Cost Fusion Development Path  

SciTech Connect (OSTI)

Simple transport-based scaling laws are derived to show that a density and time regime intermediate between conventional magnetic confinement and conventional inertial confinement offers attractive reductions in system size and energy when compared to magnetic confinement and attractive reductions in heating power and intensity when compared to inertial confinement. This intermediate parameter space appears to be readily accessible by existing and near term pulsed power technologies. Hence, the technology of the Megagauss conference opens up an attractive path to controlled thermonuclear fusion.

Lindemuth, I.R.; Siemon, R.E.; Kirkpatrick, R.C.; Reinovsky, R.E.

1998-10-19T23:59:59.000Z

353

IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 49 (2009) 055018 (13pp) doi:10.1088/0029-5515/49/5/055018  

E-Print Network [OSTI]

IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 49 (2009) 055018 experimental and theoretical status of the most basic issues of FRC stability, confinement, and current drive field line linear systems as fusion reactors. We also develop scaling relations for extrapolation from

Washington at Seattle, University of

354

ROLE OF FUSION ENERGY FOR THE 21 CENTURY ENERGY MARKET AND DEVELOPMENT STRATEGY WITH INTERNATIONAL THERMONUCLEAR EXPERIMENTAL  

E-Print Network [OSTI]

THERMONUCLEAR EXPERIMENTAL REACTOR Rôle de l'énergie de fusion dans la production énergétique du 21 e siècle etROLE OF FUSION ENERGY FOR THE 21 CENTURY ENERGY MARKET AND DEVELOPMENT STRATEGY WITH INTERNATIONAL be improved to contribute to this issue. Fusion is an energy source of the Sun and the Star. It is a quite

355

LANL Fusion Energy Sciences ResearchLANL Fusion Energy Sciences Research G. A. Wurden  

E-Print Network [OSTI]

for the U.S. Department of Energy's NNSA UNCLASSIFIED #12;| Los Alamos National Laboratory | Abstract mitigation (US-ITER) Operated by Los Alamos National Security, LLC for the U.S. Department of Energy's NNSA Alamos National Security, LLC for the U.S. Department of Energy's NNSA UNCLASSIFIED April 2013

356

CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority Fusion Technology at  

E-Print Network [OSTI]

, very challenging heat transfer and material problem critical to the success of fusion which drives 10 of 11 Some current research at CCFE · "Heat Transfer enhancement for fusion power plant divertors at CCFE David Hancock #12;PhD and Masters Open Day 15th November 2012slide 2 of 11 Objectives · The role

357

Observation of strong electromagnetic fields around laser-entrance holes of ignition-scale hohlraums in inertial-confinement fusion experiments at the National Ignition Facility  

E-Print Network [OSTI]

Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, MA 02139 USA 2 Lawrence Livermore National Laboratory, Livermore, CA 94550 USA 3 Los Alamos National Laboratory, Los Alamos, NM) experiments utilizing ignition-scaled hohlraums at the National Ignition Facility (NIF). A striking

358

Observation of nuclear fusion driven by a pyroelectric crystalQ1  

E-Print Network [OSTI]

in a room temperature solid-state setting, including `cold' fusion5 and `bubble' fusion6 , have met.............................................................. Observation of nuclear fusion driven ............................................................................................................................................................................. While progress in fusion research continues with magnetic1 and inertial2 confinement, alternative

Gimzewski, James

359

George Sips 21st IAEA Fusion Energy Conference, Chengdu, China, 16-21 October 2006 1  

E-Print Network [OSTI]

George Sips 21st IAEA Fusion Energy Conference, Chengdu, China, 16-21 October 2006 1, EURATOM-Association, D-85748, Germany G. Tardini1, C. Forest2, O. Gruber1, P. Mc Carthy3, A. Gude1, L Fusion Energy Conference, Chengdu, China, 16-21 October 2006 2 Motivation: ITER performance Mukhovatov V

360

THE PATH TOWARD MAGNETIC FUSION ENERGY DEMONSTRATON AND THE ROLE OF ITER  

E-Print Network [OSTI]

/chemical/mechanical/electromagnetic interactions. Nuclear components are located inside the vacuum vessel where tolerance for failure is low to enable a transition to fusion energy demonstration (DEMO). Fusion Nuclear Science and Technology (FNST energy system. FNST development requires DT plasma-based testing facilities in which the main loading

Abdou, Mohamed

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Fusion Energy Sciences Advisory Committee Meeting March 1-2, 2007  

E-Print Network [OSTI]

Fusion Energy Sciences Advisory Committee Meeting March 1-2, 2007 Marriott Hotel/301-590-0044 9751 Approval Professor Stewart Prager, FESAC Chair 8:35 Annual Ethics Briefing Office of the General Counsel. Raymond L. Orbach, Under Secretary of Science 12:30 Lunch 1:30 Fusion Energy Sciences FY 2008 Budget Tom

362

Fusion Energy Sciences Advisory Committee Meeting March 7-8, 2011  

E-Print Network [OSTI]

Fusion Energy Sciences Advisory Committee Meeting March 7-8, 2011 Agenda DoubleTree Bethesda Hotel Ethics Briefing Mr. Brian Plesser, Office of the General Counsel 9:00 Welcome, Meeting Agenda, Associate Director for Fusion Energy Sciences 12:30 Lunch 1:30 ITER Update: Accomplishments, Status

363

IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014004 (14pp) doi:10.1088/0029-5515/50/1/014004  

E-Print Network [OSTI]

IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014004 of nuclear energy in the form of nuclear fission were established with the nuclear powered submarine Research and Energy®, 48 Oakland Street, Princeton, NJ 08540, USA E-mail: dmeade@pppl.gov Received 6 August

364

Role of atomic collisions in fusion  

SciTech Connect (OSTI)

Atomic physics issues have played a large role in controlled fusion research. A general discussion of the present role of atomic processes in both magnetic and inertial controlled fusion work is presented.

Post, D.E.

1982-04-01T23:59:59.000Z

365

Fusion Energy Division progress report, January 1, 1992--December 31, 1994  

SciTech Connect (OSTI)

The report covers all elements of the ORNL Fusion Program, including those implemented outside the division. Non-fusion work within FED, much of which is based on the application of fusion technologies and techniques, is also discussed. The ORNL Fusion Program includes research and development in most areas of magnetic fusion research. The program is directed toward the development of fusion as an energy source and is a strong and vital component of both the US and international fusion efforts. The research discussed in this report includes: experimental and theoretical research on magnetic confinement concepts; engineering and physics of existing and planned devices; development and testing of plasma diagnostic tools and techniques; assembly and distribution of databases on atomic physics and radiation effects; development and testing of technologies for heating and fueling fusion plasmas; and development and testing of materials for fusion devices. The activities involving the use of fusion technologies and expertise for non-fusion applications ranged from semiconductor manufacturing to environmental management.

Sheffield, J.; Baker, C.C.; Saltmarsh, M.J.; Shannon, T.E.

1995-09-01T23:59:59.000Z

366

P h y s i c a l O c e a n o g r a p h y D i v i s i o n Near-inertial Energy Pathways  

E-Print Network [OSTI]

understanding of the near-inertial energy flux from the mixed layer to the ocean interior, an important element of the ocean's energy budget. Through this effort, a new hourly- interpolated drifter product with an explicitP h y s i c a l O c e a n o g r a p h y D i v i s i o n Near-inertial Energy Pathways Renellys

367

Atomic Physics in the Quest for Fusion Energy and ITER  

SciTech Connect (OSTI)

The urgent quest for new energy sources has led developed countries, representing over half of the world population, to collaborate on demonstrating the scientific and technological feasibility of magnetic fusion through the construction and operation of ITER. Data on high-Z ions will be important in this quest. Tungsten plasma facing components have the necessary low erosion rates and low tritium retention but the high radiative efficiency of tungsten ions leads to stringent restrictions on the concentration of tungsten ions in the burning plasma. The influx of tungsten to the burning plasma will need to be diagnosed, understood and stringently controlled. Expanded knowledge of the atomic physics of neutral and ionized tungsten will be important to monitor impurity influxes and derive tungsten concentrations. Also, inert gases such as argon and xenon will be used to dissipate the heat flux flowing to the divertor. This article will summarize the spectroscopic diagnostics planned for ITER and outline areas where additional data is needed.

Charles H. Skinner

2008-02-27T23:59:59.000Z

368

fusion  

National Nuclear Security Administration (NNSA)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart of the Review of theOFFICE OF8/%2A en Responding to Emergencies7/%2A

369

Power of the Sun: NERSC and Fusion Energy Science  

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

Research Scientific Computing Center (NERSC), established in 1974 as the Controlled Thermonuclear Research Computer Center and later renamed the National Magnetic Fusion...

370

Current state of magnetic-fusion energy research  

SciTech Connect (OSTI)

With the improved understanding of plasma physics, progress is being made on several approaches to magnetic confinement for controlled thermonuclear fusion.

Johnson, J.L.; Weimer, K.E.

1983-02-01T23:59:59.000Z

371

Fusion of $^{6}$Li with $^{159}$Tb} at near barrier energies  

E-Print Network [OSTI]

Complete and incomplete fusion cross sections for $^{6}$Li+$^{159}$Tb have been measured at energies around the Coulomb barrier by the $\\gamma$-ray method. The measurements show that the complete fusion cross sections at above-barrier energies are suppressed by $\\sim$34% compared to the coupled channels calculations. A comparison of the complete fusion cross sections at above-barrier energies with the existing data of $^{11,10}$B+$^{159}$Tb and $^{7}$Li+$^{159}$Tb shows that the extent of suppression is correlated with the $\\alpha$-separation energies of the projectiles. It has been argued that the Dy isotopes produced in the reaction $^{6}$Li+$^{159}$Tb, at below-barrier energies are primarily due to the $d$-transfer to unbound states of $^{159}$Tb, while both transfer and incomplete fusion processes contribute at above-barrier energies.

M. K. Pradhan; A. Mukherjee; P. Basu; A. Goswami; R. Kshetri; R. Palit; V. V. Parkar; M. Ray; Subinit Roy; P. Roy Chowdhury; M. Saha Sarkar; S. Santra

2011-06-10T23:59:59.000Z

372

Fusion of {sup 6}Li with {sup 159}Tb at near-barrier energies  

SciTech Connect (OSTI)

Complete and incomplete fusion cross sections for {sup 6}Li + {sup 159}Tb have been measured at energies around the Coulomb barrier by the {gamma}-ray method. The measurements show that the complete fusion cross sections at above-barrier energies are suppressed by {approx}34% compared to coupled-channel calculations. A comparison of the complete fusion cross sections at above-barrier energies with the existing data for {sup 11,10}B + {sup 159}Tb and {sup 7}Li + {sup 159}Tb shows that the extent of suppression is correlated with the {alpha} separation energies of the projectiles. It has been argued that the Dy isotopes produced in the reaction {sup 6}Li + {sup 159}Tb at below-barrier energies are primarily due to the d transfer to unbound states of {sup 159}Tb, while both transfer and incomplete fusion processes contribute at above-barrier energies.

Pradhan, M. K.; Mukherjee, A.; Basu, P.; Goswami, A.; Kshetri, R.; Roy, Subinit; Chowdhury, P. Roy; Sarkar, M. Saha; Palit, R.; Parkar, V. V.; Santra, S.; Ray, M. [Nuclear Physics Division, Saha Institute of Nuclear Physics, 1/AF, Bidhan Nagar, Kolkata-700064 (India); Department of Nuclear and Atomic Physics, Tata Institute of Fundamental Research, Mumbai-400005 (India); Nuclear Physics Division, Bhabha Atomic Research Centre, Mumbai-400085 (India); Department of Physics, Behala College, Parnasree, Kolkata-700060 (India)

2011-06-15T23:59:59.000Z

373

Fusion Engineering and Design 81 (2006) 16391645 Thermo-mechanical analysis of a micro-engineered  

E-Print Network [OSTI]

laser (HAPL) program goal is to develop a laser inertial fusion reactor using a solid first wall (FW of X-rays, ions, and neutrons assumed unimpeded by any gas in the chamber. X-rays and ions have shallow such a small volume [6]. Shallow energy absorption leads to fast expansion in the surface while the bulk

Ghoniem, Nasr M.

2006-01-01T23:59:59.000Z

374

University of California, San Diego UCSD-ENG-105 Fusion Division  

E-Print Network [OSTI]

of various threats. The full range of damage threats in a laser-IFE power plant includes laser damage and optic response in inertial fusion energy (IFE) power plants and simulation of those phenomena through for a laser-IFE power plant and to field both small and medium scale prototypes for testing. The top level

Krstic, Miroslav

375

Energy chief tells Jersey: Fusion's back Secretary, at top research lab in Plainsboro, says country resuming international effort  

E-Print Network [OSTI]

plan to build a $5 billion fusion reactor, called the International Thermonuclear Experimental ReactorEnergy chief tells Jersey: Fusion's back Secretary, at top research lab in Plainsboro, says country States plans to resume participation in an international collaboration to develop fusion energy

376

Nuclear Data for Fusion Energy Technologies: Requests, Status and Development Needs  

SciTech Connect (OSTI)

The current status of nuclear data evaluations for fusion technologies is reviewed. Well-qualified data are available for neutronics and activation calculations of fusion power reactors and the next-step device ITER, the International Thermonuclear Experimental Reactor. Major challenges for the further development of fusion nuclear data arise from the needs of the long-term fusion programme. In particular, co-variance data are required for uncertainty assessments of nuclear responses. Further, the nuclear data libraries need to be extended to higher energies above 20 MeV to enable neutronics and activation calculations of IFMIF, the International Fusion Material Irradiation Facility. A significant experimental effort is required in this field to provide a reliable and sound database for the evaluation of cross-section data in the higher energy range.

Fischer, U. [Association FZK-Euratom, Forschungszentrum Karlsruhe, Institut fuer Reaktorsicherheit, Postfach 3640, D-76021 Karlsruhe (Germany); Batistoni, P. [Associazione Euratom-ENEA sulla Fusione, ENEA Fusion Divison, Via E. Fermi 27, I-00044 Frascati (Italy); Cheng, E. [TSI Research, Inc., P.O. Box 2754, Rancho Santa Fe, CA 92067 (United States); Forrest, R.A. [Euratom/UKAEA Fusion Association, Culham Science Centre, Abingdon, Oxfordshire OX14 3DB (United Kingdom); Nishitani, T. [Fusion Neutronics Laboratory, JAERI, Tokai-mura, Naka-gun, Ibaraki-ken 319-1195 (Japan)

2005-05-24T23:59:59.000Z

377

Realizing Technologies for Magnetized Target Fusion  

SciTech Connect (OSTI)

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.

Wurden, Glen A. [Los Alamos National Laboratory

2012-08-24T23:59:59.000Z

378

FES Science Network Requirements - Report of the Fusion Energy Sciences Network Requirements Workshop Conducted March 13 and 14, 2008  

E-Print Network [OSTI]

of Energy, Office of Science, Advanced Scientific Computingthe Directors of the Office of Science, Office of AdvancedDivision, and the Office of Fusion Energy Sciences.

Dart, Eli

2008-01-01T23:59:59.000Z

379

Is nuclear fusion a sustainable energy form? A. M. Bradshaw  

E-Print Network [OSTI]

multipliers foreseen for fusion power plants, in particular beryllium, represent a major supply problem, or virtual, limitlessness of supply, which can be defined, albeit arbitrarily, as corresponding to a few

380

IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 53 (2013) 042001 (3pp) doi:10.1088/0029-5515/53/4/042001  

E-Print Network [OSTI]

IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 53 (2013) 042001 Extreme Environment, School of Nuclear Engineering, Purdue University, West Lafayette, IN, USA Received 9 directly (e.g. by spectroscopy), integration of the post-exposure W deposition showed that a net effective

Harilal, S. S.

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

| International Atomic Energy Agency Nuclear Fusion Nucl. Fusion 54 (2014) 043016 (8pp) doi:10.1088/0029-5515/54/4/043016  

E-Print Network [OSTI]

| International Atomic Energy Agency Nuclear Fusion Nucl. Fusion 54 (2014) 043016 (8pp) doi:10. Hassanein Center for Materials under Extreme Environment, School of Nuclear Engineering, Purdue University the developed volume-of-fluid magnetohydrodynamic code. The effects of plasma velocity and magnetic field

Harilal, S. S.

382

| International Atomic Energy Agency Nuclear Fusion Nucl. Fusion 54 (2014) 023004 (9pp) doi:10.1088/0029-5515/54/2/023004  

E-Print Network [OSTI]

| International Atomic Energy Agency Nuclear Fusion Nucl. Fusion 54 (2014) 023004 (9pp) doi:10 Tatyana Sizyuk and Ahmed Hassanein Center for Materials under Extreme Environment, School of Nuclear for publication 17 December 2013 Published 21 January 2014 Abstract The plasma shielding effect is a well

Harilal, S. S.

383

and INTERNATIONAL ATOMIC ENERGY AGENCYIOP PUBLISHING NUCLEAR FUSION Nucl. Fusion 48 (2008) 024016 (13pp) doi:10.1088/0029-5515/48/2/024016  

E-Print Network [OSTI]

and INTERNATIONAL ATOMIC ENERGY AGENCYIOP PUBLISHING NUCLEAR FUSION Nucl. Fusion 48 (2008) 024016 devices Milan Rajkovi´c1 , Milos Skori´c2 , Knut Sølna3 and Ghassan Antar4 1 Institute of Nuclear Sciences the issue of estimating the variable power law behavior of spectral densities is addressed. The analysis

Solna, Knut

384

IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 52 (2012) 013005 (11pp) doi:10.1088/0029-5515/52/1/013005  

E-Print Network [OSTI]

#12;IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 52 (2012-vaguelette decomposition. After validation of the new method using an academic test case and numerical data obtained, but the associated vessel erosion also impairs the awaited viability of long lasting discharges. It is thus

Farge, Marie

385

Technical Feasibility of Fusion Energy Extension of the Fusion Program and Basic  

E-Print Network [OSTI]

-Fired Power Plant 31 1.3.4 Radioactive Waste and Environmental Adaptability 35 1.3.4.1 Classification of the Radioactive Waste 35 1.3.4.2 Long Term Risks of Radioactive Waste Disposal from a Fusion Reactor and A Light of Minor Actinides 54 1.3.7.3 Production of Radioactive Isotopes 55 1.3.7.4 Development of Multipurpose Use

386

TabletopAccelerator Breaks`Cold Fusion'Jinx ButWon'tYield Energy,Physicists Say  

E-Print Network [OSTI]

TabletopAccelerator Breaks`Cold Fusion'Jinx ButWon'tYield Energy,Physicists Say A crystal with a strange property is at the heart of a clever method for inducing nuclear fusion in a tabletop-sized device-rays for medical therapies. Although the field of room-temperature fusion is littered with scandals and dubious

387

U. S. FUSION ENERGY FUTURE John A. Schmidt, Dan Jassby, Scott Larson, Maria Pueyo, and Paul H. Rutherford  

E-Print Network [OSTI]

with fusion development plans in Japan and Europe [e.g. 2]. The primary source of energy demand projections that was used as a basis for this assessment was the World Energy Council/IIASA Global Energy Perspectives [3U. S. FUSION ENERGY FUTURE John A. Schmidt, Dan Jassby, Scott Larson, Maria Pueyo, and Paul H

388

Perspective on Fusion Energy Presentation at TWAS-ARO Meeting Bibliotheca Alexandria  

E-Print Network [OSTI]

for Energy Science & Technology (UCLA) President, Council of Energy Research and Education Leaders, CEREL (electricity ~ $1 trillion / yr) The world energy use is growing - to lift people out of poverty, to improve be used to produce electricity and hydrogen, and for desalination. 4 #12;8 Fusion Research is about

Abdou, Mohamed

389

Systematics of heavy-ion fusion hindrance at extreme sub-barrier energies.  

SciTech Connect (OSTI)

The recent discovery of hindrance in heavy-ion induced fusion reactions at extreme sub-barrier energies represents a challenge for theoretical models. Previously, it has been shown that in medium-heavy systems, the onset of fusion hindrance depends strongly on the 'stiffness' of the nuclei in the entrance channel. In this work, we explore its dependence on the total mass and the Q-value of the fusing systems and find that the fusion hindrance depends in a systematic way on the entrance channel properties over a wide range of systems.

Jiang, C. L.; Back, B. B.; Esbensen, H.; Janssens, R. V. F.; Rehm, K. E.; Physics

2006-01-01T23:59:59.000Z

390

Systematics of heavy-ion fusion hindrance at extreme sub-barrier energies  

E-Print Network [OSTI]

The recent discovery of hindrance in heavy-ion induced fusion reactions at extreme sub-barrier energies represents a challenge for theoretical models. Previously, it has been shown that in medium-heavy systems, the onset of fusion hindrance depends strongly on the "stiffness" of the nuclei in the entrance channel. In this work, we explore its dependence on the total mass and the $Q$-value of the fusing systems and find that the fusion hindrance depends in a systematic way on the entrance channel properties over a wide range of systems.

C. L. Jiang; B. B. Back; H. Esbensen; R. V. F. Janssens; abd K. E. Rehm

2005-08-01T23:59:59.000Z

391

Systematics of heavy-ion fusion hindrance at extreme sub-barrier energies  

SciTech Connect (OSTI)

The recent discovery of hindrance in heavy-ion induced fusion reactions at extreme sub-barrier energies represents a challenge for theoretical models. Previously, it has been shown that in medium-heavy systems, the onset of fusion hindrance depends strongly on the ''stiffness'' of the nuclei in the entrance channel. In this work, we explore its dependence on the total mass and the Q-value of the fusing systems and find that the fusion hindrance depends in a systematic way on the entrance channel properties over a wide range of systems.

Jiang, C.L.; Back, B.B.; Esbensen, H.; Janssens, R.V.F.; Rehm, K.E. [Physics Division, Argonne National Laboratory, Argonne, Illinois 60439 (United States)

2006-01-15T23:59:59.000Z

392

Energy-Dependence of Nucleus-Nucleus Potential and Friction Parameter in Fusion Reactions  

E-Print Network [OSTI]

Applying a macroscopic reduction procedure on the improved quantum molecular dynamics (ImQMD) model, the energy dependences of the nucleus-nucleus potential, the friction parameter, and the random force characterizing a one-dimensional Langevin-type description of the heavy-ion fusion process are investigated. Systematic calculations with the ImQMD model show that the fluctuation-dissipation relation found in the symmetric head-on fusion reactions at energies just above the Coulomb barrier fades out when the incident energy increases. It turns out that this dynamical change with increasing incident energy is caused by a specific behavior of the friction parameter which directly depends on the microscopic dynamical process, i.e., on how the collective energy of the relative motion is transferred into the intrinsic excitation energy. It is shown microscopically that the energy dissipation in the fusion process is governed by two mechanisms: One is caused by the nucleon exchanges between two fusing nuclei, and the other is due to a rearrangement of nucleons in the intrinsic system. The former mechanism monotonically increases the dissipative energy and shows a weak dependence on the incident energy, while the latter depends on both the relative distance between two fusing nuclei and the incident energy. It is shown that the latter mechanism is responsible for the energy dependence of the fusion potential and explains the fading out of the fluctuation-dissipation relation.

Kai Wen; Fumihiko Sakata; Zhu-Xia Li; Xi-Zhen Wu; Ying-Xun Zhang; Shan-Gui Zhou

2014-11-08T23:59:59.000Z

393

Applications of Skyrme energy-density functional to fusion reactions for synthesis of superheavy nuclei  

E-Print Network [OSTI]

The Skyrme energy-density functional approach has been extended to study the massive heavy-ion fusion reactions. Based on the potential barrier obtained and the parameterized barrier distribution the fusion (capture) excitation functions of a lot of heavy-ion fusion reactions are studied systematically. The average deviations of fusion cross sections at energies near and above the barriers from experimental data are less than 0.05 for 92% of 76 fusion reactions with $Z_1Z_2fusion reactions, for example, the $^{238}$U-induced reactions and $^{48}$Ca+$^{208}$Pb the capture excitation functions have been reproduced remarkable well. The influence of structure effects in the reaction partners on the capture cross sections are studied with our parameterized barrier distribution. Through comparing the reactions induced by double-magic nucleus $^{48}$Ca and by $^{32}$S and $^{35}$Cl, the 'threshold-like' behavior in the capture excitation function for $^{48}$Ca induced reactions is explored and an optimal balance between the capture cross section and the excitation energy of the compound nucleus is studied. Finally, the fusion reactions with $^{36}$S, $^{37}$Cl, $^{48}$Ca and $^{50}$Ti bombarding on $^{248}$Cm, $^{247,249}$Bk, $^{250,252,254}$Cf and $^{252,254}$Es, and as well as the reactions lead to the same compound nucleus with Z=120 and N=182 are studied further. The calculation results for these reactions are useful for searching for the optimal fusion configuration and suitable incident energy in the synthesis of superheavy nuclei.

Ning Wang; Xizhen Wu; Zhuxia Li; Min Liu; Werner Scheid

2006-09-18T23:59:59.000Z

394

Applications of Skyrme energy-density functional to fusion reactions for synthesis of superheavy nuclei  

SciTech Connect (OSTI)

The Skyrme energy-density functional approach has been extended to study massive heavy-ion fusion reactions. Based on the potential barrier obtained and the parametrized barrier distribution the fusion (capture) excitation functions of a lot of heavy-ion fusion reactions are studied systematically. The average deviations of fusion cross sections at energies near and above the barriers from experimental data are less than 0.05 for 92% of 76 fusion reactions with Z{sub 1}Z{sub 2}<1200. For the massive fusion reactions, for example, the {sup 238}U-induced reactions and {sup 48}Ca+{sup 208}Pb, the capture excitation functions have been reproduced remarkably well. The influence of structure effects in the reaction partners on the capture cross sections is studied with our parametrized barrier distribution. By comparing the reactions induced by double-magic nucleus {sup 48}Ca and by {sup 32}S and {sup 35}Cl, the ''threshold-like'' behavior in the capture excitation function for {sup 48}Ca-induced reactions is explored and an optimal balance between the capture cross section and the excitation energy of the compound nucleus is studied. Finally, the fusion reactions with {sup 36}S, {sup 37}Cl, {sup 48}Ca, and {sup 50}Ti bombarding {sup 248}Cm, {sup 247,249}Bk, {sup 250,252,254}Cf, and {sup 252,254}Es, as well as the reactions leading to the same compound nucleus with Z=120 and N=182, are studied further. The calculation results for these reactions are useful for searching for the optimal fusion configuration and suitable incident energy in the synthesis of superheavy nuclei.

Wang Ning; Scheid, Werner [Institute for Theoretical Physics at Justus-Liebig-University, D-35392 Giessen (Germany); Wu Xizhen; Liu Min [China Institute of Atomic Energy, Beijing 102413 (China); Li Zhuxia [China Institute of Atomic Energy, Beijing 102413 (China); Institute of Theoretical Physics, Chinese Academic of Science, Beijing 100080 (China); Nuclear Theory Center of National Laboratory of Heavy Ion Accelerator, Lanzhou 730000 (China)

2006-10-15T23:59:59.000Z

395

Fusion and Direct Reactions of Halo Nuclei at Energies around the Coulomb Barrier  

E-Print Network [OSTI]

The present understanding of reaction processes involving light unstable nuclei at energies around the Coulomb barrier is reviewed. The effect of coupling to direct reaction channels on elastic scattering and fusion is investigated, with the focus on halo nuclei. A list of definitions of processes is given, followed by a review of the experimental and theoretical tools and information presently available. The effect of couplings on elastic scattering and fusion is studied with a series of model calculations within the coupled-channels framework. The experimental data on fusion are compared to "bare" no-coupling one-dimensional barrier penetration model calculations. On the basis of these calculations and comparisons with experimental data, conclusions are drawn from the observation of recurring features. The total fusion cross sections for halo nuclei show a suppression with respect to the "bare" calculations at energies just above the barrier that is probably due to single neutron transfer reactions. The data for total fusion are also consistent with a possible sub-barrier enhancement; however, this observation is not conclusive and other couplings besides the single-neutron channels would be needed in order to explain any actual enhancement. We find that a characteristic feature of halo nuclei is the dominance of direct reactions over fusion at near and sub-barrier energies; the main part of the cross section is related to neutron transfers, while calculations indicate only a modest contribution from the breakup process.

N. Keeley; R. Raabe; N. Alamanos; J. L. Sida

2007-02-16T23:59:59.000Z

396

Status of the HAPL Program Laser Fusion Energy  

E-Print Network [OSTI]

-optics Government Labs 1. NRL 2. LLNL 3. SNL 4. LANL 5. ORNL 6. PPPL 7. SRNL Industry 1. General Atomics 2. L3/PSD 3 still need to do Electricity or Hydrogen Generator Reaction chamber Spherical pellet Pellet factory* Threat spectra Fusion Test Facility: Gain > 50 @ 500 kJ 2 different simulations** Simulations Codes

397

A Plan for the Deveiopment of Magnetic Fusion Energy  

E-Print Network [OSTI]

source for meeting future base-loadelectricity needs. Fusion fuel supply is widely available, controlof plasma-wall interactions, tritium processing, developmentof low-activationradiation-damage that relies more heavily on internationalcollaboration. Since about 611 billion (1990 dollars) have been spent

398

Improved Magnetic Fusion Energy Economics Via Massive Resistive Electromagnets  

E-Print Network [OSTI]

for magnetic fusion reactors and instead using resistive magnet designs based on cheap copper or aluminum maintenance cost To put the capital cost issue into perspective, consider the following comparison, which incorporate niobium, a rare and expensive material compared to copper or aluminum. In addition to the direct

399

Historical Perspective on the United States Fusion Program  

SciTech Connect (OSTI)

Progress and Policy is traced over the approximately 55 year history of the U. S. Fusion Program. The classified beginnings of the effort in the 1950s ended with declassification in 1958. The effort struggled during the 1960s, but ended on a positive note with the emergence of the tokamak and the promise of laser fusion. The decade of the 1970s was the 'Golden Age' of fusion, with large budget increases and the construction of many new facilities, including the Tokamak Fusion Test Reactor (TFTR) and the Shiva laser. The decade ended on a high note with the passage of the Magnetic Fusion Energy Engineering Act of 1980, overwhelming approved by Congress and signed by President Carter. The Act called for a '$20 billion, 20 year' effort aimed at construction of a fusion Demonstration Power Plant around the end of the century. The U. S. Magnetic Fusion Energy program has been on a downhill slide since 1980, both in terms of budgets and the construction of new facilities. The Inertial Confinement Fusion program, funded by Department of Energy Defense Programs, has faired considerably better, with the construction of many new facilities, including the National Ignition Facility (NIF)

Dean, Stephen O

2005-04-15T23:59:59.000Z

400

Scientific Issues and Gaps for High-Performance Steady-State Burning-Plasmas Fusion Innovation Research and Energy  

E-Print Network [OSTI]

Innovation Research and Energy Princeton, NJ 08540 Introduction Fusion energy is a potential energy source for an electricity producing power plant. Recently, the FESAC Priorities, Gaps and Opportunities Panel identified, and extracting plasma exhaust power) Theme C ­ Harnessing the Power of Fusion (extracting neutron power, breeding

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Recent EFDA work on Pulsed DEMO, August 2012, TOFE T N Todd Culham Centre for Fusion Energy, Oxfordshire  

E-Print Network [OSTI]

) · Start-up power requirements, energy storage strategy · Energy storage systems available Energy, Oxfordshire The Future of Nuclear Power: Fusion Recent EFDA work on pulsed DEMO The UK fusion experimental demonstrations of simultaneous HH, N etc... But is ITB OK in DEMO (sustainable)? Alpha confinement

402

THE FOREST AND THE TREES The development of fusion energy only occupies a very small part of the  

E-Print Network [OSTI]

THE FOREST AND THE TREES Jay Kesner MIT PSFC The development of fusion energy only occupies a very small part of the world's energy picture and the fusion community often has difficulty seeing the forest and scientifically and also whether it will provide a path to commercial energy. Looking at the "forest", big

403

on the Establishment of the ITER International Fusion Energy Organization for the Joint Implementation of the ITER Project  

E-Print Network [OSTI]

AGREEMENT on the Establishment of the ITER International Fusion Energy Organization for the Joint Fusion Energy Organization Article 2 Purpose of the ITER Organization Article 3 Functions of the ITER://fusionforenergy.europa.eu/downloads/aboutf4e/l_35820061216en00620081.pdf #12;Preamble The European Atomic Energy Community (hereinafter

404

Solid state laser technology for inertial confinement fusion: A collection of articles from ''Energy and Technology Review''  

SciTech Connect (OSTI)

This paper contains reprinted articles that record several milestones in laser research at LLNL. ''Neodymium-Glass Laser Research and Development at LLNL'' recounts the history of the Laser Program and our work on neodymium-glass lasers. ''Nova Laser Technology'' describes the capabilities of the Nova laser and some of its uses. ''Building Nova: Industry Relations and Technology Transfer'' illustrates the Laboratory's commitment to work with US industry in technology development. ''Managing the Nova Laser Project'' details the organization and close monitoring of costs and schedules during the construction of the Nova laser facility. The article ''Optical Coatings by the Sol-Gel Process,'' describes our chemical process for making the damage-resistant, antireflective silica coatings used on the Nova laser glass. The technical challenges in designing and fabricating the KDP crystal arrays used to convert the light wave frequency of the Nova lasers are reported in ''Frequency Conversion of the Nova Laser.'' Two articles, ''Eliminating Platinum Inclusions in Laser Glass'' and ''Detecting Microscopic Inclusions in Optical Glass,'' describe how we dealt with the problem of damaging metal inclusions in the Nova laser glass. The last article reprinted here, ''Auxilliary Target Chamber for Nova,'' discusses the diversion of two of Nova's ten beamlines into a secondary chamber for the purpose of increasing our capacity for experimentation.

Not Available

1988-06-01T23:59:59.000Z

405

Accelerator & Fusion Research Division: 1993 Summary of activities  

SciTech Connect (OSTI)

The Accelerator and Fusion Research Division (AFRD) is not only one of the largest scientific divisions at LBL, but also the one of the most diverse. Major efforts include: (1) investigations in both inertial and magnetic fusion energy; (2) operation of the Advanced Light Source, a state-of-the-art synchrotron radiation facility; (3) exploratory investigations of novel radiation sources and colliders; (4) research and development in superconducting magnets for accelerators and other scientific and industrial applications; and (5) ion beam technology development for nuclear physics and for industrial and biomedical applications. Each of these topics is discussed in detail in this book.

Chew, J.

1994-04-01T23:59:59.000Z

406

Fusion of light proton-rich exotic nuclei at near-barrier energies  

E-Print Network [OSTI]

We study theoretically fusion of the light proton-rich exotic nuclei $^{17}$F and $^8$B at near-barrier energies in order to investigate the possible role of breakup processes on their fusion cross sections. To this end, coupled channel calculations are performed considering the couplings to the breakup channels of these projectiles. In case of $^{17}$F, the coupling arising out of the inelastic excitation from the ground state to the bound excited state and its couplings to the continuum have also been taken into consideration. It is found that the inelastic excitation/breakup of $^{17}$F affect the fusion cross sections very nominally even for a heavy target like Pb. On the other hand, calculations for fusion of the one-proton halo nucleus $^8$B on a Pb target show a significant suppression of the complete fusion cross section above the Coulomb barrier. This is due to the larger breakup probability of $^8$B as compared to that of $^{17}$F. However, even for $^8$B, there is little change in the complete fusion cross sections as compared to the no-coupling case at sub-barrier energies.

P. Banerjee; K. Krishan; S. Bhattacharya; C. Bhattacharya

2002-02-08T23:59:59.000Z

407

Senator Dianne Feinstein Statement on the Fusion Energy Sciences Act of 2001  

E-Print Network [OSTI]

, keeping natural gas prices reasonable, and bringing new supplies of power online are the key objectives I and polluting. Beyond expanding renewable energy sources such as those from the sun and the wind, fusion holds energy source with major environmental advantages. As a co-sponsor of this legislation, I hope to see

408

The Administration's Proposed Budget for Fusion Energy Sciences in FY 2015  

E-Print Network [OSTI]

The Administration's Proposed Budget for Fusion Energy Sciences in FY 2015 E.J. Synakowski Associate Director Office of Science, U.S. Department of Energy March 7, 2014 #12;This proposal reflects reveal that ITER has significant problems to overcome. This proposal supports the Administration

409

A lower cost development path for heavy ion fusion  

SciTech Connect (OSTI)

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.

Hogan, W.J. [Lawrence Livermore National Lab., CA (United States); Meier, W.R. [Shafer (W.J.) Associates, Inc., Wakefield, MA (United States)

1993-05-19T23:59:59.000Z

410

A novel method for modeling the neutron time of flight (nTOF) detector response in current mode to inertial confinement fusion experiments.  

SciTech Connect (OSTI)

There are several machines in this country that produce short bursts of neutrons for various applications. A few examples are the Zmachine, operated by Sandia National Laboratories in Albuquerque, NM; the OMEGA Laser Facility at the University of Rochester in Rochester, NY; and the National Ignition Facility (NIF) operated by the Department of Energy at Lawrence Livermore National Laboratory in Livermore, California. They all incorporate neutron time of flight (nTOF) detectors which measure neutron yield, and the shapes of the waveforms from these detectors contain germane information about the plasma conditions that produce the neutrons. However, the signals can also be %E2%80%9Cclouded%E2%80%9D by a certain fraction of neutrons that scatter off structural components and also arrive at the detectors, thereby making analysis of the plasma conditions more difficult. These detectors operate in current mode - i.e., they have no discrimination, and all the photomultiplier anode charges are integrated rather than counted individually as they are in single event counting. Up to now, there has not been a method for modeling an nTOF detector operating in current mode. MCNPPoliMiwas developed in 2002 to simulate neutron and gammaray detection in a plastic scintillator, which produces a collision data output table about each neutron and photon interaction occurring within the scintillator; however, the postprocessing code which accompanies MCNPPoliMi assumes a detector operating in singleevent counting mode and not current mode. Therefore, the idea for this work had been born: could a new postprocessing code be written to simulate an nTOF detector operating in current mode? And if so, could this process be used to address such issues as the impact of neutron scattering on the primary signal? Also, could it possibly even identify sources of scattering (i.e., structural materials) that could be removed or modified to produce %E2%80%9Ccleaner%E2%80%9D neutron signals? This process was first developed and then applied to the axial neutron time of flight detectors at the ZFacility mentioned above. First, MCNPPoliMi was used to model relevant portions of the facility between the source and the detector locations. To obtain useful statistics, variance reduction was utilized. Then, the resulting collision output table produced by MCNPPoliMi was further analyzed by a MATLAB postprocessing code. This converted the energy deposited by neutron and photon interactions in the plastic scintillator (i.e., nTOF detector) into light output, in units of MeVee%D1%84 (electron equivalent) vs time. The time response of the detector was then folded into the signal via another MATLAB code. The simulated response was then compared with experimental data and shown to be in good agreement. To address the issue of neutron scattering, an %E2%80%9CIdeal Case,%E2%80%9D (i.e., a plastic scintillator was placed at the same distance from the source for each detector location) with no structural components in the problem. This was done to produce as %E2%80%9Cpure%E2%80%9D a neutron signal as possible. The simulated waveform from this %E2%80%9CIdeal Case%E2%80%9D was then compared with the simulated data from the %E2%80%9CFull Scale%E2%80%9D geometry (i.e., the detector at the same location, but with all the structural materials now included). The %E2%80%9CIdeal Case%E2%80%9D was subtracted from the %E2%80%9CFull Scale%E2%80%9D geometry case, and this was determined to be the contribution due to scattering. The time response was deconvolved out of the empirical data, and the contribution due to scattering was then subtracted out of it. A transformation was then made from dN/dt to dN/dE to obtain neutron spectra at two different detector locations.

Nelson, Alan J. [University of New Mexico, Albuquerque, NM; Cooper, Gary Wayne [University of New Mexico, Albuquerque, NM; Ruiz, Carlos L.; Chandler, Gordon Andrew; Fehl, David Lee; Hahn, Kelly Denise; Leeper, Ramon Joe; Smelser, Ruth Marie; Torres, Jose A.

2013-09-01T23:59:59.000Z

411

Energy Efficient Distributed Data Fusion In Multihop Wireless Sensor Networks  

E-Print Network [OSTI]

of routing tree establishment, transmission energy planninglarge gap of energy between the single-hop tree and theThe routing tree ?nding and the transmission energy planning

Huang, Yi

2010-01-01T23:59:59.000Z

412

Report of the Integrated Program Planning Activity for the DOE Fusion Energy Sciences Program  

SciTech Connect (OSTI)

This report of the Integrated Program Planning Activity (IPPA) has been prepared in response to a recommendation by the Secretary of Energy Advisory Board that, ''Given the complex nature of the fusion effort, an integrated program planning process is an absolute necessity.'' We, therefore, undertook this activity in order to integrate the various elements of the program, to improve communication and performance accountability across the program, and to show the inter-connectedness and inter-dependency of the diverse parts of the national fusion energy sciences program. This report is based on the September 1999 Fusion Energy Sciences Advisory Committee's (FESAC) report ''Priorities and Balance within the Fusion Energy Sciences Program''. In its December 5,2000, letter to the Director of the Office of Science, the FESAC has reaffirmed the validity of the September 1999 report and stated that the IPPA presents a framework and process to guide the achievement of the 5-year goals listed in the 1999 report. The National Research Council's (NRC) Fusion Assessment Committee draft final report ''An Assessment of the Department of Energy's Office of Fusion Energy Sciences Program'', reviewing the quality of the science in the program, was made available after the IPPA report had been completed. The IPPA report is, nevertheless, consistent with the recommendations in the NRC report. In addition to program goals and the related 5-year, 10-year, and 15-year objectives, this report elaborates on the scientific issues associated with each of these objectives. The report also makes clear the relationships among the various program elements, and cites these relationships as the reason why integrated program planning is essential. In particular, while focusing on the science conducted by the program, the report addresses the important balances between the science and energy goals of the program, between the MFE and IFE approaches, and between the domestic and international aspects of the program. The report also outlines a process for establishing a database for the fusion research program that will indicate how each research element fits into the overall program. This database will also include near-term milestones associated with each research element, and will facilitate assessments of the balance within the program at different levels. The Office of Fusion Energy Sciences plans to begin assembling and using the database in the Spring of 2001 as we receive proposals from our laboratories and begin to prepare our budget proposal for Fiscal Year 2003.

None

2000-12-01T23:59:59.000Z

413

anterior cervical fusion: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

414

alkaline phosphatase fusion: Topics by E-print Network  

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Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

415

antibody fusion proteins: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

416

abl fusion gene: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

417

acyltransferase gfp fusion: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

418

albumin fusion proteins: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

419

anatomical information fusion: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

420

antigen fusion proteins: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

affects myoblast fusion: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

422

anterior spinal fusion: Topics by E-print Network  

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Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

423

anterior vertebral fusion: Topics by E-print Network  

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Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

424

anterior interbody fusion: Topics by E-print Network  

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Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

425

acquired motor fusion: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

426

angiography fusion images: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

427

alloy fusion safety: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

428

altered fusion transcript: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

429

artificial gene fusion: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

430

activate membrane fusion: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

431

Journal of Fusion Energy, Vol. 20, No. 3, September 2001 ( 2002) Report of the FESAC Panel on a Burning Plasma Program  

E-Print Network [OSTI]

- ence, although it is not designed to be the sole burning plasma facility in the world.Fusion energy methods of energy production, are strong reasons to pursue fusion energy now. vened for this purposeJournal of Fusion Energy, Vol. 20, No. 3, September 2001 ( 2002) Report of the FESAC Panel

Najmabadi, Farrokh

432

A Combinational Approach to the Fusion, De-noising and Enhancement of Dual-Energy X-Ray Luggage Images  

E-Print Network [OSTI]

dual-energy X-ray images for better object classification and threat detection. The fusion stepA Combinational Approach to the Fusion, De-noising and Enhancement of Dual-Energy X-Ray Luggage-based noise reduction technique which is very efficient in removing background noise from fused X-ray images

Abidi, Mongi A.

433

Inertial Confinement Fusion | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

advanced science and technology portfolio, the Office of ICF is working to produce thermonuclear burn conditions in the laboratory, to develop laboratory capabilities that will...

434

Reviewers Comments on the 5th Symposium and the Status of Fusion Research 2003  

SciTech Connect (OSTI)

Better to understand the status of fusion research in the year 2003 we will first put the research in its historical context. Fusion power research, now beginning its sixth decade of continuous effort, is unique in the field of scientific research. Unique in its mixture of pure and applied research, unique in its long-term goal and its promise for the future, and unique in the degree that it has been guided and constrained by national and international governmental policy. Though fusion research's goal has from the start been precisely defined, namely, to obtain a net release of energy from controlled nuclear fusion reactions between light isotopes (in particular those of hydrogen and helium) the difficulty of the problem has spawned in the past a very wide variety of approaches to the problem. Some of these approaches have had massive international support for decades, some have been pursued only at a ''shoestring'' level by dedicated groups in small research laboratories or universities. In discussing the historical and present status of fusion research the implications of there being two distinctly different approaches to achieving net fusion power should be pointed out. The first, and oldest, approach is the use of strong magnetic fields to confine the heated fuel, in the form of a plasma and at a density typically four or five orders of magnitude smaller than the density of the atmosphere. In steady state this fusion fuel density is still sufficient to release fusion energy at the rate of many megawatts per cubic meter. The plasma confinement times required for net energy release in this regime are long--typically a second or more, representing an extremely difficult scientific challenge --witness the five decades of research in magnetic fusion, still without having reaching that goal. The second, more recently initiated approach, is of course the ''inertial'' approach. As its name implies, the ''confinement'' problem is solved ''inertially,'' that is by compressing and heating a tiny pellet of frozen fusion fuel in nanoseconds, such that before disassembly the pellet fuses and releases its energy as a micro-explosion. The first, and most thoroughly investigated means to create this compression and heating is to use multiple laser beams, with total energies of megajoules, focused down to impinge uniformly on the pellet target. To illustrate the extreme difference between the usual magnetic confinement regime at that of inertial fusion, there are twenty orders of magnitude in fusion power density (ten orders of magnitude in plasma density) between the two regimes. In principle fusion power systems could operate at any density between these extremes, if means were to be found to exploit this possibility.

Post, R F

2005-02-03T23:59:59.000Z

435

U.S. Signs International Fusion Energy Agreement; Large-Scale, Clean Fusion  

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436

An innovative accelerator-driven inertial electrostatic confinement device using converging ion beams  

SciTech Connect (OSTI)

Fundamental physics issues facing development of fusion power on a small-scale are assessed with emphasis on the idea of Inertial Electrostatic Confinement (IEC). The authors propose a new concept of accelerator-driven IEC fusion, termed Converging Beam Inertial Electrostatic Confinement (CB-IEC). CB-IEC offers a number of innovative features that make it an attractive pathway toward resolving fundamental physics issues and assessing the ultimate viability of the IEC concept for power generation.

Bauer, T. H.; Wigeland, R. A.

1999-12-08T23:59:59.000Z

437

IOP PUBLISHING and INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR FUSION Nucl. Fusion 50 (2010) 014005 (5pp) doi:10.1088/0029-5515/50/1/014005  

E-Print Network [OSTI]

with international collaboration towards the early use of fusion energy to meet the urgent needs for energy of three as shown in figure 2. Meanwhile, China's resources are poorly balanced. It uses 11% of world coal, 13% hydropower, but only 2.5% of the oil and 1.2% of the gas on the Earth. This means

438

Uniformity of fuel target implosion in Heavy Ion Fusion  

E-Print Network [OSTI]

In inertial confinement fusion the target implosion non-uniformity is introduced by a driver beams' illumination non-uniformity, a fuel target alignment error in a fusion reactor, the target fabrication defect, et al. For a steady operation of a fusion power plant the target implosion should be robust against the implosion non-uniformities. In this paper the requirement for the implosion uniformity is first discussed. The implosion uniformity should be less than a few percent. A study on the fuel hotspot dynamics is also presented and shows that the stagnating plasma fluid provides a significant enhancement of vorticity at the final stage of the fuel stagnation. Then non-uniformity mitigation mechanisms of the heavy ion beam (HIB) illumination are also briefly discussed in heavy ion inertial fusion (HIF). A density valley appears in the energy absorber, and the large-scale density valley also works as a radiation energy confinement layer, which contributes to a radiation energy smoothing. In HIF a wobbling he...

Kawata, S; Suzuki, T; Karino, T; Barada, D; Ogoyski, A I; Ma, Y Y

2015-01-01T23:59:59.000Z

439

Fusion Energy for Power Production: Status Assessment, Identification of Challenges and Strategic Plan for Commercialization  

E-Print Network [OSTI]

1 Fusion Energy for Power Production: Status Assessment, Identification of Challenges and Strategic in the Technical Assessment Committee (TAC) and 4) EPRI being the Program Manager for the project. Establish Plan for Commercialization March 2011 Phase I. Status Assessment and Identification of Challenges

440

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

E-Print Network [OSTI]

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

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

2006-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

A comparison of mainline and alternate approaches to fusion energy  

SciTech Connect (OSTI)

The tokamak and tandem mirror concepts are compared with alternate confinement concepts using the criteria established in DOE/ET-0047, ''An Evaluation of Alternate Magnetic Fusion Concepts 1977.'' The concepts are evaluated and rated in each of three broad categories: confidence in physics and technology, and reactor desirability. The STARFIRE and MARS reactors are used as a basis for comparing the mainline tokamak and tandem mirror concepts with the alternate concepts evaluated in DOE/ET-0047. Two recent alternate concepts, the ohmically heated toroidal experiment (OHTE) and the compact reversed field pinch reactor (CRFPR), are also evaluated. Results indicate that the physics of the mainline tokamaks and tandem mirrors is better understood than that of most alternate concepts. Both mainline concepts rank near the middle for technology requirements, and both rank near or at the bottom when compared with the reactor desirability of alternate concepts.

Hayman, P.W.; Roth, J.R.

1985-02-01T23:59:59.000Z

442

Multimodal Options for Materials Research to Advance the Basis for Fusion Energy in the ITER Era  

SciTech Connect (OSTI)

Well-coordinated international fusion materials research on multiple fundamental feasibility issues can serve an important role during the next ten years. An overview is given of the current state-of-the-art of major materials systems that are candidates for next-step fusion reactors, including a summary of existing knowledge regarding operating temperature and neutron irradiation fluence limits due to high temperature strength and radiation damage considerations, coolant compatibility information, and current industrial manufacturing capabilities. There are two inter-related overarching objectives of fusion materials research to be performed in the next decade: 1) understanding materials science phenomena in the demanding DT fusion energy environment, and 2) Using this improved understanding to develop and qualify materials to provide the basis for next-step facility construction authorization by funding agencies and public safety licensing authorities. The critical issues and prospects for development of high performance fusion materials are discussed along with recent research results and planned activities of the international materials research community.

Zinkle, Steven J [ORNL; Mslang, Anton [Karlsruhe Institute of Technology, Karlsruhe, Germany; Muroga, Takeo [National Institute for Fusion Science, Toki, Japan; Tanigawa, H. [Japan Atomic Energy Agency (JAEA)

2013-01-01T23:59:59.000Z

443

Life Pure Fusion Target Designs: Status and Prospects  

SciTech Connect (OSTI)

Analysis and radiation-hydrodynamics simulations for expected high-gain fusion target performance on a demonstration 1-GWe Laser Inertial Fusion Energy (LIFE) power plant are presented. The required laser energy driver is 2.2 MJ at a 0.351-{mu}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 near-term experimental resolution of the key physics uncertainties on the National Ignition Facility.

Amendt, P; Dunne, M; Ho, D; Lindl, J

2011-10-20T23:59:59.000Z

444

Secretary of Energy Advisory Board SLAC National Accelerator...  

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

Goodwin 11:45 AM - 12:30 PM Energy of the Future - National Ignition Facility (NIF) and Laser Inertial Fusion Energy (LIFE) Ed Moses 12:30 PM - 1:45 PM Lunch Break 2:00 PM - 2:30...

445

Development of Fusion Nuclear Technologies at Japan Atomic Energy Research Institute  

SciTech Connect (OSTI)

An overview of the present status of development of fusion nuclear technologies at Japan Atomic Energy Research Institute is presented. A tritium handling system for the ITER was designed, and the technology for each component of this system was demonstrated successfully. An ultraviolet laser with a wavelength of 193 nm was found quite effective for removing tritium from in-vessel components of D-T fusion reactors. Blanket technologies have been developed for the test blanket module of the ITER and for advanced blankets for DEMO reactors. This blanket is composed of ceramic Li{sub 2}TiO{sub 3} breeder pebbles and neutron multiplier beryllium pebbles, whose diameter ranges from 0.2 to 2 mm, contained in a box structure made of a reduced-activation ferritic steel, F82H. Mechanical properties of F82H under a thermal neutron irradiation at up to 50 displacements per atom (dpa) were obtained in a temperature range from 200 to 500 deg. C. Design of the International Fusion Materials Irradiation Facility (IFMIF) has been developed to obtain engineering data for candidate materials for DEMO reactors under a simulated fusion neutron irradiation up to 100 to 200 dpa, and basic development of the key technologies to construct the IFMIF is now under way as an International Energy Agency international collaboration.

Seki, Masahiro; Yamanishi, Toshihiko; Shu, Wataru; Nishi, Masataka; Hatano, Toshihisa; Akiba, Masato; Takeuchi, Hiroshi; Nakamura, Kazuyuki; Sugimoto, Masayoshi; Shiba, Kiyoyuki; Jitsukawa, Shiro; Ishitsuka, Etsuo; Tsuji, Hiroshi [Japan Atomic Energy Research Institute (Japan)

2002-07-15T23:59:59.000Z

446

Thermal Performance of Deep-Burn Fusion-Fission Hybrid Waste in a Repository  

SciTech Connect (OSTI)

The Laser Inertial Confinement Fusion Fission Energy (LIFE) Engine [1] combines a neutron-rich but energy-poor inertial fusion system with an energy-rich but neutron-poor subcritical fission blanket. Because approximately 80% of the LIFE Engine energy is produced from fission, the requirements for laser efficiency and fusion target performance are relaxed, compared to a pure-fusion system, and hence a LIFE Engine prototype can be based on target performance in the first few years of operation of the National Ignition Facility (NIF) at Lawrence Livermore National Laboratory (LLNL). Similarly, because of the copious fusion neutrons, the fission blanket can be run in a subcritical, driven, mode, without the need for control rods or other sophisticated reactivity control systems. Further, because the fission blanket is inherently subcritical, fission fuels that can be used in LIFE Engine designs include thorium, depleted uranium, natural uranium, spent light water reactor fuel, highly enriched uranium, and plutonium. Neither enrichment nor reprocessing is required for the LIFE Engine fuel cycle, and burnups to 99% fraction of initial metal atoms (FIMA) being fissioned are envisioned. This paper discusses initial calculations of the thermal behavior of spent LIFE fuel following completion of operation in the LIFE Engine [2]. The three time periods of interest for thermal calculations are during interim storage (probably at the LIFE Engine site), during the preclosure operational period of a geologic repository, and after closure of the repository.

Blink, J A; Chipman, V; Farmer, J; Shaw, H; Zhao, P

2008-11-25T23:59:59.000Z

447

Magneto-Inertial Fusion (Magnetized Target Fusion)( g g )  

E-Print Network [OSTI]

, 2011 U N C L A S S I F I E D Operated by the Los Alamos National Security, LLC for the DOE/NNSA Slide 1 for the DOE/NNSA Slide 2 Some MIF-IFE reactor considerations #12;A Wide Range of Driver/Target Combinations for the DOE/NNSA S. A. Slutz, et al., Phys. Plasmas 17, 056303 (2010) A. G. Lynn, et al, Rev. Sci. Instr. 81

448

Sandia National Laboratories: DOE Office of Fusion Energy  

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

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449

Current Status of DiscussionCurrent Status of DiscussionCurrent Status of DiscussionCurrent Status of Discussion on Roadmap of Fusion Energyon Roadmap of Fusion Energy  

E-Print Network [OSTI]

of fusion has dramatically changed since the accident of the Fukushima Dai-ichi nuclear power stationnuclear-ichi accident Exploration of ocean, telecommunication, space transportation and satellite, new energy atomic after the Fukushima Dai-ichi accident R&D for safety, prevention of disaster, proliferation and nuclear

450

| International Atomic Energy Agency Nuclear Fusion Nucl. Fusion 54 (2014) 033008 (8pp) doi:10.1088/0029-5515/54/3/033008  

E-Print Network [OSTI]

localized modes (ELMs) or plasma disruptions [1, 2], the high thermal energy can be deposited on localized areas of plasma- facing components (PFC) in fusion devices [3, 4]. Among high-Z materials, pure tungsten (W) demonstrates the highest resistance against thermal loads under plasma disruption conditions

Harilal, S. S.

451

Safeguard Requirements for Fusion Power Plants  

SciTech Connect (OSTI)

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.

Robert J. Goldston and Alexander Glaser

2012-08-10T23:59:59.000Z

452

Contributions of Burning Plasma Physics Experiment to Fusion Energy Goals  

E-Print Network [OSTI]

materials and care in design. ?Have operational reliability and high availability: · Ease of maintenance. of Electrical & Computer Eng. And Center for Energy Research University of California, San Diego, Burning Plasma

453

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

SciTech Connect (OSTI)

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.

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.

1987-09-10T23:59:59.000Z

454

Fusion Simulation Project. Workshop sponsored by the U.S. Department of Energy Rockville, MD, May 16-18, 2007  

SciTech Connect (OSTI)

The mission of the Fusion Simulation Project is to develop a predictive capability for the integrated modeling of magnetically confined plasmas. This FSP report adds to the previous activities that defined an approach to integrated modeling in magnetic fusion. These previous activities included a Fusion Energy Sciences Advisory Committee panel that was charged to study integrated simulation in 2002. The report of that panel [Journal of Fusion Energy 20, 135 (2001)] recommended the prompt initiation of a Fusion Simulation Project. In 2003, the Office of Fusion Energy Sciences formed a steering committee that developed a project vision, roadmap, and governance concepts [Journal of Fusion Energy 23, 1 (2004)]. The current FSP planning effort involved forty-six physicists, applied mathematicians and computer scientists, from twenty-one institutions, formed into four panels and a coordinating committee. These panels were constituted to consider: Status of Physics Components, Required Computational and Applied Mathematics Tools, Integration and Management of Code Components, and Project Structure and Management. The ideas, reported here, are the products of these panels, working together over several months and culminating in a three-day workshop in May 2007.

None

2007-05-16T23:59:59.000Z

455

Fusion Simulation Project. Workshop Sponsored by the U.S. Department of Energy, Rockville, MD, May 16-18, 2007  

SciTech Connect (OSTI)

The mission of the Fusion Simulation Project is to develop a predictive capability for the integrated modeling of magnetically confined plasmas. This FSP report adds to the previous activities that defined an approach to integrated modeling in magnetic fusion. These previous activities included a Fusion Energy Sciences Advisory Committee panel that was charged to study integrated simulation in 2002. The report of that panel [Journal of Fusion Energy 20, 135 (2001)] recommended the prompt initiation of a Fusion Simulation Project. In 2003, the Office of Fusion Energy Sciences formed a steering committee that developed a project vision, roadmap, and governance concepts [Journal of Fusion Energy 23, 1 (2004)]. The current FSP planning effort involved forty-six physicists, applied mathematicians and computer scientists, from twenty-one institutions, formed into four panels and a coordinating committee. These panels were constituted to consider: Status of Physics Components, Required Computational and Applied Mathematics Tools, Integration and Management of Code Components, and Project Structure and Management. The ideas, reported here, are the products of these panels, working together over several months and culminating in a three-day workshop in May 2007.

Kritz, A.; Keyes, D.

2007-05-18T23:59:59.000Z

456

Inertial Frames and Clock Rates  

E-Print Network [OSTI]

This article revisits the historiography of the problem of inertial frames. Specifically, the case of the twins in the clock paradox is considered to see that some resolutions implicitly assume inertiality for the non-accelerating twin. If inertial frames are explicitly identified by motion with respect to the large scale structure of the universe, it makes it possible to consider the relative inertiality of different frames.

Subhash Kak

2012-02-13T23:59:59.000Z

457

The role of surface energy coefficients and nuclear surface diffuseness in the fusion of heavy-ions  

E-Print Network [OSTI]

We discuss the effect of surface energy coefficients as well as nuclear surface diffuseness in the proximity potential and ultimately in the fusion of heavy-ions. Here we employ different versions of surface energy coefficients. Our analysis reveals that these technical parameters can influence the fusion barriers by a significant amount. A best set of these parameters is also given that explains the experimental data nicely.

Ishwar Dutt; Rajeev K. Puri

2010-05-06T23:59:59.000Z

458

Plasma Turbulence Simulations Reveal Promising Insight for Fusion Energy |  

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

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459

Large Scale Computing and Storage Requirements for Fusion Energy Sciences  

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

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460

Questions and answers about ITER and fusion energy  

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

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Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


461

Laser fusion experiment yields record energy at NIF | National Nuclear  

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

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462

Scientists discuss progress toward magnetic fusion energy at 2013 AAAS  

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

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463

Fusion Energy Greg Hammett & Russell Kulsred Princeton University  

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

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464

International Atomic Energy Agency holds conference on fusion roadmap |  

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

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465

Fusion Energy Sciences Network Requirements Review Final Report  

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

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466

Applying physics, teamwork to fusion energy science | Princeton Plasma  

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467

ITER: The International Thermonuclear Experimental Reactor and the nuclear weapons proliferation implications of thermonuclear-fusion energy  

E-Print Network [OSTI]

This paper contains two parts: (I) A list of "points" highlighting the strategic-political and military-technical reasons and implications of the very probable siting of ITER (the International Thermonuclear Experimental Reactor) in Japan, which should be confirmed sometimes in early 2004. (II) A technical analysis of the nuclear weapons proliferation implications of inertial- and magnetic-confinement fusion systems substantiating the technical points highlighted in the first part, and showing that while full access to the physics of thermonuclear weapons is the main implication of ICF, full access to large-scale tritium technology is the main proliferation impact of MCF. The conclusion of the paper is that siting ITER in a country such as Japan, which already has a large separated-plutonium stockpile, and an ambitious laser-driven ICF program (comparable in size and quality to those of the United States or France) will considerably increase its latent (or virtual) nuclear weapons proliferation status, and fo...

Gsponer, A; Gsponer, Andre; Hurni, Jean-Pierre

2004-01-01T23:59:59.000Z

468

First Observations of Nonhydrodynamic Mix at the Fuel-Shell Interface in Shock-Driven Inertial Confinement Implosions  

E-Print Network [OSTI]

A strong nonhydrodynamic mechanism generating atomic fuel-shell mix has been observed in strongly shocked inertial confinement fusion implosions of thin deuterated-plastic shells filled with [superscript 3]He gas. These ...

Amendt, P.

469

Large Scale Computing and Storage Requirements for Fusion Energy Sciences: Target 2017  

SciTech Connect (OSTI)

The National Energy Research Scientific Computing Center (NERSC) is the primary computing center for the DOE Office of Science, serving approximately 4,500 users working on some 650 projects that involve nearly 600 codes in a wide variety of scientific disciplines. In March 2013, NERSC, DOE?s Office of Advanced Scientific Computing Research (ASCR) and DOE?s Office of Fusion Energy Sciences (FES) held a review to characterize High Performance Computing (HPC) and storage requirements for FES research through 2017. This report is the result.

Gerber, Richard

2014-05-02T23:59:59.000Z

470

Spherical plasma oscillations in a reversed-polarity inertial-electrostatic confinement device  

SciTech Connect (OSTI)

A pulsed reversed-polarity inertial-electrostatic confinement device has been investigated experimentally using voltage and spectroscopic diagnostics. Large-amplitude oscillations were observed in the floating potential of the plasma immediately following the initiation of the discharge. It is postulated that the observations were the result of coherent ion oscillations within a harmonic potential well formed by a uniform electron density in the center of the device. A simple model of the system predicts the depth of this transient potential well to be approximately 100 V. Observations of the relative occupation of the third and fourth energy levels of hydrogen in the plasma indicated the formation of a Maxwellian electron energy distribution after 20 {mu}s. The results suggest a promising avenue toward a net fusion power gain by utilizing these oscillations to periodically compress and heat the plasma to thermonuclear densities and energies.

Tuft, C.; Khachan, J. [Plasma Physics, School of Physics, University of Sydney, New South Wales 2006 (Australia)

2010-11-15T23:59:59.000Z

471

Scientific Breakeven for Fusion Energy For the past 40 years, the IFE fusion research community has adopted: achieving a fusion gain of 1 as  

E-Print Network [OSTI]

scientific breakeven." E. Moses, Status of the NIF Project, Lawrence Livermore National Laboratory Report: "Laser fusion experiments, facilities, and diagnostics at Lawrence Livermore National Laboratory", by H of 1 defines scientific breakeven. (This is therefore a Livermore definition!) The recent National

472

Hindrance of Heavy-ion Fusion at Extreme Sub-Barrier Energies in Open-shell Colliding Systems  

E-Print Network [OSTI]

The excitation function for the fusion-evaporation reaction 64Ni+100Mo has been measured down to a cross-section of ~5 nb. Extensive coupled-channels calculations have been performed, which cannot reproduce the steep fall-off of the excitation function at extreme sub-barrier energies. Thus, this system exhibits a hindrance for fusion, a phenomenon that has been discovered only recently. In the S-factor representation introduced to quantify the hindrance, a maximum is observed at E_s=120.6 MeV, which corresponds to 90% of the reference energy E_s^ref, a value expected from systematics of closed-shell systems. A systematic analysis of Ni-induced fusion reactions leading to compound nuclei with mass A=100-200 is presented in order to explore a possible dependence of the fusion hindrance on nuclear structure.

C. L. Jiang; K. E. Rehm; H. Esbensen; R. V. F. Janssens; B. B. Back; P. Collon; C. N. Davids; J. P. Greene; D. J. Henderson; C. J. Lister; S. Kurtz; R. C. Pardo; T. Pennington; M. Paul; D. Peterson; D. Seweryniak; B. Shumard; S. Sinha; X. D. Tang; I. Tanihata; S. Zhu

2004-12-20T23:59:59.000Z

473

Dependence of the energies of fusion on the intermembrane separation: optimal and constrained  

E-Print Network [OSTI]

We calculate the characteristic energies of fusion between planar bilayers as afunction of the distance between them, measured from the hydrophobic/hydrophilic interface of one of the two nearest, cis, leaves to the other. The two leaves of each bilayer are of equal composition; 0.6 volume fraction of a lamellar-forming amphiphile, such as dioleoylphosphatidylcholine, and 0.4 volume fraction of a hexagonal-forming amphiphile, such as dioleoylphosphatidylethanolamine. Self-consistent field theory is employed to solve the model. We find that the largest barrier to fusion is that to create the metastable stalk. This barrier is the smallest, about 14.6 $k_BT$, when the bilayers are at a distance about 20 percent greater than the thickness of a single leaf, a distance which would correspond to between two and three nanometers for typical bilayers. The very size of the protein machinery which brings the membranes together can prevent them from reaching this optimum separation. For even modestly larger separations, we find a linear rate of increase of the free energy with distance between bilayers for the metastable stalk itself and for the barrier to the creation of this stalk. We estimate these rates for biological membranes to be about 7.1 $k_BT$/nm and 16.7 $k_BT$/nm respectively. The major contribution to this rate comes from the increased packing energy associated with the hydrophobic tails. From this we estimate, for the case of hemagglutinin, a free energy of 38 k_BT for the metastable stalk itself, and a barrier to create it of 73 k_BT. Such a large barrier would require that more than a single hemagglutinin molecule be involved in the fusion process, as is observed.

J. Y. Lee; M. Schick

2007-08-09T23:59:59.000Z

474

Novel Hybrid Monte Carlo/Deterministic Technique for Shutdown Dose Rate Analyses of Fusion Energy Systems  

SciTech Connect (OSTI)

The rigorous 2-step (R2S) method uses three-dimensional Monte Carlo transport simulations to calculate the shutdown dose rate (SDDR) in fusion reactors. Accurate full-scale R2S calculations are impractical in fusion reactors because they require calculating space- and energy-dependent neutron fluxes everywhere inside the reactor. The use of global Monte Carlo variance reduction techniques was suggested for accelerating the neutron transport calculation of the R2S method. The prohibitive computational costs of these approaches, which increase with the problem size and amount of shielding materials, inhibit their use in the accurate full-scale neutronics analyses of fusion reactors. This paper describes a novel hybrid Monte Carlo/deterministic technique that uses the Consistent Adjoint Driven Importance Sampling (CADIS) methodology but focuses on multi-step shielding calculations. The Multi-Step CADIS (MS-CADIS) method speeds up the Monte Carlo neutron calculation of the R2S method using an importance function that represents the importance of the neutrons to the final SDDR. Using a simplified example, preliminarily results showed that the use of MS-CADIS enhanced the efficiency of the neutron Monte Carlo simulation of an SDDR calculation by a factor of 550 compared to standard global variance reduction techniques, and that the increase over analog Monte Carlo is higher than 10,000.

Ibrahim, Ahmad M [ORNL] [ORNL; Peplow, Douglas E. [ORNL] [ORNL; Peterson, Joshua L [ORNL] [ORNL; Grove, Robert E [ORNL] [ORNL

2013-01-01T23:59:59.000Z

475

Fusion and Plasma Physics are at the Core of Nature's Most Powerful Self-Driven Systems  

E-Print Network [OSTI]

-D DIII-D JET FT ITER Ignitor, CIT, FIRE TFTR OmegaU direct drive Nova indirect drive Nova direct drive Laser D-T #12;Comparison of Typical Plasma Parameters for Inertial and Magnetic Fusion Inertial Magnetic is Confinement a Challenge for Magnetic Fusion? A D-T reactor at a fuel density of 1020 m-3 requires E ~ 1 second

476

X-Ray Energy Responses of Silicon Tomography Detectors Irradiated with Fusion Produced Neutrons  

SciTech Connect (OSTI)

In order to clarify the effects of fusion-produced neutron irradiation on silicon semiconductor x-ray detectors, the x-ray energy responses of both n- and p-type silicon tomography detectors used in the Joint European Torus (JET) tokamak (n-type) and the GAMMA 10 tandem mirror (p-type) are studied using synchrotron radiation at the Photon Factory of the National Laboratory for High Energy Accelerator Research Organization (KEK). The fusion neutronics source (FNS) of Japan Atomic Energy Research Institute (JAERI) is employed as well-calibrated D-T neutron source with fluences from 10{sup 13} to 10{sup 15} neutrons/cm{sup 2} onto these semiconductor detectors. Different fluence dependence is found between these two types of detectors; that is, (i) for the n-type detector, the recovery of the degraded response is found after the neutron exposure beyond around 10{sup 13} neutrons/cm{sup 2} onto the detector. A further finding is followed as a 're-degradation' by a neutron irradiation level over about 10{sup 14} neutrons/cm{sup 2}. On the other hand, (ii) the energy response of the p-type detector shows only a gradual decrease with increasing neutron fluences. These properties are interpreted by our proposed theory on semiconductor x-ray responses in terms of the effects of neutrons on the effective doping concentration and the diffusion length of a semiconductor detector.

Kohagura, J. [Plasma Research Centre, University of Tsukuba (Japan); Cho, T. [Plasma Research Centre, University of Tsukuba (Japan); Hirata, M. [Plasma Research Centre, University of Tsukuba (Japan); Numakura, T. [Plasma Research Centre, University of Tsukuba (Japan); Yokoyama, N. [Plasma Research Centre, University of Tsukuba (Japan); Fukai, T. [Plasma Research Centre, University of Tsukuba (Japan); Tomii, Y. [Plasma Research Centre, University of Tsukuba (Japan); Tokioka, S. [Plasma Research Centre, University of Tsukuba (Japan); Miyake, Y. [Plasma Research Centre, University of Tsukuba (Japan); Kiminami, S. [Plasma Research Centre, University of Tsukuba (Japan); Shimizu, K. [Plasma Research Centre, University of Tsukuba (Japan); Miyoshi, S. [Plasma Research Centre, University of Tsukuba (Japan); Hirano, K. [High Energy Accelerator Research Organization (Japan); Yoshida, M. [Japan Atomic Energy Research Institute (Japan); Yamauchi, M. [Japan Atomic Energy Research Institute (Japan); Kondoh, T. [Japan Atomic Energy Research Institute (Japan); Nishitani, T. [Japan Atomic Energy Research Institute (Japan)

2005-01-15T23:59:59.000Z

477

aml1-eto fusion protein: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

478

antibody-photosensitizer fusion protein: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

479

antibody-gdnf fusion protein: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

480

akar2-akap12 fusion protein: Topics by E-print Network  

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

Research and Energy Plasma Physics and Fusion Websites Summary: , .... Controlled Thermonuclear Fusion had great potential - Uncontrolled Thermonuclear fusion...

Note: This page contains sample records for the topic "inertial fusion energy" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


481

E-Print Network 3.0 - advanced fusion material Sample Search...  

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

Physics and Fusion 5 Fusion Energy Program Presentation to Summary: International Thermonuclear Experimental Reactor Plasma Technologies Fusion Technologies Advanced Materials......

482

E-Print Network 3.0 - advanced deuterium fusion Sample Search...  

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

Physics and Fusion 2 Fusion Energy Program Presentation to Summary: International Thermonuclear Experimental Reactor Plasma Technologies Fusion Technologies Advanced Materials......

483

Fusion-Fission of 16O+197Au at Sub-Barrier Energies  

E-Print Network [OSTI]

The recent discovery of heavy-ion fusion hindrance at far sub-barrier energies has focused much attention on both experimental and theoretical studies of this phenomenon. Most of the experimental evidence comes from medium-heavy systems such as Ni+Ni to Zr+Zr, for which the compound system decays primarily by charged-particle evaporation. In order to study heavier systems, it is, however, necessary to measure also the fraction of the decay that goes into fission fragments. In the present work we have, therefore, measured the fission cross section of 16O+197Au down to unprecedented far sub-barrier energies using a large position sensitive PPAC placed at backward angles. The preliminary cross sections will be discussed and compared to earlier studies at near-barrier energies. No conclusive evidence for sub-barrier hindrance was found, probably because the measurements were not extended to sufficiently low energies.

B. B. Back; C. L. Jiang; R. V. F. Janssens; D. J. Henderson; B. R. Shumard; C. J. Lister; D. Peterson; K. E. Rehm; I. Tanihata; X. Tang; X. Wang; S. Zhu

2006-06-06T23:59:59.000Z

484

Laser or charged-particle-beam fusion reactor with direct electric generation by magnetic flux compression  

DOE Patents [OSTI]

The invention is a laser or particle-beam-driven fusion reactor system which takes maximum advantage of both the very short pulsed nature of the energy release of inertial confinement fusion (ICF) and the very small volumes within which the thermonuclear burn takes place. The pulsed nature of ICF permits dynamic direct energy conversion schemes such as magnetohydrodynamic (MHD) generation and magnetic flux compression; the small volumes permit very compact blanket geometries. By fully exploiting these characteristics of ICF, it is possible to design a fusion reactor with exceptionally high power density, high n