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1

Inertial confinement fusion (ICF) review  

Science Conference Proceedings (OSTI)

During its 1996 winter study JASON reviewed the DOE Inertial Confinement Fusion (ICF) program. This included the National Ignition Facility (NIF) and proposed studies. The result of the review was to comment on the role of the ICF program in support of the DOE Science Based Stockpile Stewardship program.

Hammer, D.; Dyson, F.; Fortson, N.; Novick, B.; Panofsky, W.; Rosenbluth, M.; Treiman, S.; York, H.

1996-03-01T23:59:59.000Z

2

Inertial-confinement-fusion targets  

DOE Green Energy (OSTI)

Inertial confinement fusion (ICF) targets are made as simple flat discs, as hollow shells or as complicated multilayer structures. Many techniques have been devised for producing the targets. Glass and metal shells are made by using drop and bubble techniques. Solid hydrogen shells are also produced by adapting old methods to the solution of modern problems. Some of these techniques, problems and solutions are discussed. In addition, the applications of many of the techniques to fabrication of ICF targets is presented.

Hendricks, C.D.

1981-11-16T23:59:59.000Z

3

Multishell inertial confinement fusion target  

DOE Patents (OSTI)

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

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

1987-01-01T23:59:59.000Z

4

Multishell inertial confinement fusion target  

DOE Patents (OSTI)

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

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

1984-01-01T23:59:59.000Z

5

Princeton Plasma Physics Lab - Inertial confinement fusion  

NLE Websites -- All DOE Office Websites (Extended Search)

inertial-confinement-fusion An inertial-confinement-fusion An experimental process that uses lasers to compress plasma to sufficiently high temperatures and densities for fusion to occur. Such experiments are carried out in places such as the National Ignition Facility at the Lawrence Livermore National Laboratory in Livermore, California. en Fusion through the eyes of a veteran science journalist http://www.pppl.gov/news/2013/07/fusion-through-eyes-veteran-science-journalist-1

Author Daniel Clery recently published "A Piece of the Sun," a 320-page narrative of the history of fusion research and the

6

Office of Inertial Confinement Fusion | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test Capabilities and Evaluation > Office of Inertial Confinement Fusion Office of Inertial...

7

Materials considerations for inertially-confined fusion reactors (ICFR)  

SciTech Connect

This paper discusses some of the material considerations for inertially confined fusion reactors. A comparison of the material considerations for inertially confined reactors is made with those of magnetically confined reactors. The lithium fall reactor concept is used as an example of the freedom from constraints intrinsic to inertially-confined fusion reactors.

Hovingh, J.

1978-06-05T23:59:59.000Z

8

Commercial applications of inertial confinement fusion  

SciTech Connect

This report describes the fundamentals of inertial-confinement fusion, some laser-fusion reactor (LFR) concepts, and attendant means of utilizing the thermonuclear energy for commercial electric power generation. In addition, other commercial energy-related applications, such as the production of fissionable fuels, of synthetic hydrocarbon-based fuels, and of process heat for a variety of uses, as well as the environmental and safety aspects of fusion energy, are discussed. Finally, the requirements for commercialization of laser fusion technologies are described.

Booth, L.A.; Frank, T.G. (comps.)

1977-05-01T23:59:59.000Z

9

Office of Inertial Confinement Fusion | National Nuclear Security  

NLE Websites -- All DOE Office Websites (Extended Search)

Inertial Confinement Fusion | National Nuclear Security Inertial Confinement Fusion | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Inertial Confinement Fusion Office of Inertial Confinement Fusion Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Inertial Confinement Fusion

10

Multishell inertial-confinement-fusion target  

DOE Patents (OSTI)

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

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

1981-06-01T23:59:59.000Z

11

Species separation in inertial confinement fusion fuels  

SciTech Connect

It is shown by means of multi-fluid particle-in-cell simulations that convergence of the spherical shock wave that propagates through the inner gas of inertial confinement fusion-relevant experiments is accompanied by a separation of deuterium (D) and tritium (T) ions across the shock front. Deuterons run ahead of the tritons due to their lower mass and higher charge-to-mass ratio and can reach the center several tens of picoseconds before the tritons. The rising edge of the DD and TT fusion rate is also temporally separated by the same amount, which should be an observable in experiments and would be a direct proof of the 'stratification conjecture' on the shock front [Amendt et al., Phys. Plasmas 18, 056308 (2011)]. Moreover, dephasing of the D and T shock components in terms of density and temperature leads to a degradation of the DT fusion yield as the converging shock first rebounds from the fuel center (shock yield). For the parameters of this study, the second peak in the fusion yield (compression yield) is strongly dependent on the choice of the flux limiter.

Bellei, C.; Amendt, P. A.; Wilks, S. C. [Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore, California 94550 (United States); Haines, M. G. [Blackett Laboratory, Imperial College, London SW7 2AZ (United Kingdom); Casey, D. T. [Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore, California 94550 (United States); Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States); Li, C. K.; Petrasso, R. [Plasma Science and Fusion Center, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States); Welch, D. R. [Voss Scientic, Albuquerque, New Mexico 87108 (United States)

2013-01-15T23:59:59.000Z

12

Shock convergence and mix dynamics in inertial confinement fusion  

E-Print Network (OSTI)

Understanding the phenomena of shock propagation and of turbulent mix induced by Rayleigh-Taylor (RT) instability growth is of critical importance for ignition and high gain in inertial confinement fusion (ICF). Capsule ...

Rygg, James Ryan

2006-01-01T23:59:59.000Z

13

Design considerations in inertially-confined fusion reactors  

SciTech Connect

This paper discusses the effects of short time pulses of energetic particles and waves typical of inertially-confined thermonuclear reactions on the first wall, blanket and shield of conceptual reactors. Several reactor designs are presented which attempt to cope with the various problems from the microexplosion debris. Fusion-fission hybrid reactors are also discussed. Emphasis is placed on the first-wall problems of laser-initiated, inertially confined fusion reactors using the deuterium-tritium fuel cycle.

Hovingh, J.

1976-08-01T23:59:59.000Z

14

LANL | Physics | Inertial Confinement Fusion and High Energy Density  

NLE Websites -- All DOE Office Websites (Extended Search)

Inertial confinement and high density Inertial confinement and high density plasma physics Using the world's most powerful lasers, Physics Division scientists are aiming to create thermonuclear burn in the laboratory. The experimental research of the Physics Division's Inertial Confinement Fusion program is conducted at the National Ignition Facility at Lawrence Livermore National Laboratory, the OMEGA Laser Facility at the University of Rochester, and the Trident Laser Facility at Los Alamos. Within inertial confinement fusion and the high energy density area, Los Alamos specializes in hohlraum energetics, symmetry tuning, warm dense matter physics, and hydrodynamics in ultra-extreme conditions. When complete, this research will enable the exploitation of fusion as an energy resource and will enable advanced research in stockpile stewardship

15

Inertial confinement fusion: present status and future potential  

DOE Green Energy (OSTI)

Power from inertial confinement fusion holds much promise for society. This paper points out many of the benefits relative to combustion of hydrocarbon fuels and fission power. Potential problems are also identified and put in perspective. The progress toward achieving inertial fusion power is described and results of recent work at the Lawrence Livermore National Laboratory are presented. Key phenomenological uncertainties are described and experimental goals for the Nova laser system are given. Several ICF reactor designs are discussed.

Hogan, W.J.

1984-07-16T23:59:59.000Z

16

Inertial Confinement Fusion Annual Report 1997  

SciTech Connect

The ICF Annual Report provides documentation of the achievements of the LLNL ICF Program during the fiscal year by the use of two formats: (1) an Overview that is a narrative summary of important results for the fiscal year and (2) a compilation of the articles that previously appeared in the ICF Quarterly Report that year. Both the Overview and Quarterly Report are also on the Web at http://lasers.llnl.gov/lasers/pubs/icfq.html. Beginning in Fiscal Year 1997, the fourth quarter issue of the ICF Quarterly was no longer printed as a separate document but rather included in the ICF Annual. This change provided a more efficient process of documenting our accomplishments with-out unnecessary duplication of printing. In addition we introduced a new document, the ICF Program Monthly Highlights. Starting with the September 1997 issue and each month following, the Monthly Highlights will provide a brief description of noteworthy activities of interest to our DOE sponsors and our stakeholders. The underlying theme for LLNL's ICF Program research continues to be defined within DOE's Defense Programs missions and goals. In support of these missions and goals, the ICF Program advances research and technology development in major interrelated areas that include fusion target theory and design, target fabrication, target experiments, and laser and optical science and technology. While in pursuit of its goal of demonstrating thermonuclear fusion ignition and energy gain in the laboratory, 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 of inertial fusion energy for civilian power production. ICF technologies continue to have spin-off applications for additional government and industrial use. In addition to these topics, the ICF Annual Report covers non-ICF funded, but related, laser research and development and associated applications. We also provide a short summary of the quarterly activities within Nova laser operations, Beamlet laser operations, and National Ignition Facility laser design. LLNL's ICF Program falls within DOE's national ICF program, which includes the Nova and Beamlet (LLNL), OMEGA (University of Rochester Laboratory for Laser Energetics), Nike (Naval Research Laboratory), and Trident (Los Alamos National Laboratory) laser facilities. The Particle Beam Fusion Accelerator (Z) and Saturn pulsed-power facilities are at Sandia National Laboratories. General Atomics, Inc., develops and provides many of the targets for the above experimental facilities. Many of the ICF Annual Report articles are co-authored with our colleagues from these other ICF institutions.

Correll, D

1998-06-01T23:59:59.000Z

17

Inertially confined fusion using heavy ion drivers  

Science Conference Proceedings (OSTI)

The various technical issues of HIF will be briefly reviewed in this paper. It will be seen that there are numerous areas in common in all the approaches to HIF. In the recent International Symposium on Heavy Ion Inertial Fusion, the attendees met in specialized workshop sessions to consider the needs for research in each area. Each of the workshop groups considered the key questions of this report: (1) Is this an appropriate time for international collaboration in HIF (2) Which problems are most appropriate for such collaboration (3) Can the sharing of target design information be set aside until other driver and systems issues are better resolved, by which time it might be supposed that there could be a relaxation of classification of target issues (4) What form(s) of collaboration are most appropriate, e.g., bilateral or multilateral (5) Can international collaboration be sensibly attempted without significant increases in funding for HIF The authors of this report share the conviction that collaboration on a broad scale is mandatory for HIF to have the resources, both financial and personnel, to progress to a demonstration experiment. Ultimately it may be possible for a single driver with the energy, power, focusibility, and pulse shape to satisfy the needs of the international community for target physics research. Such a facility could service multiple experimental chambers with a variety of beam geometries and target concepts.

Herrmannsfeldt, W.B. (Stanford Linear Accelerator Center, Menlo Park, CA (United States)); Bangerter, R.O. (Lawrence Berkeley Lab., CA (United States)); Bock, R. (Gesellschaft fuer Schwerionenforschung mbH, Darmstadt (Germany)); Hogan, W.J.; Lindl, J.D. (Lawrence Livermore National Lab., CA (United States))

1991-10-01T23:59:59.000Z

18

Inertially confined fusion using heavy ion drivers  

Science Conference Proceedings (OSTI)

The various technical issues of HIF will be briefly reviewed in this paper. It will be seen that there are numerous areas in common in all the approaches to HIF. In the recent International Symposium on Heavy Ion Inertial Fusion, the attendees met in specialized workshop sessions to consider the needs for research in each area. Each of the workshop groups considered the key questions of this report: (1) Is this an appropriate time for international collaboration in HIF? (2) Which problems are most appropriate for such collaboration? (3) Can the sharing of target design information be set aside until other driver and systems issues are better resolved, by which time it might be supposed that there could be a relaxation of classification of target issues? (4) What form(s) of collaboration are most appropriate, e.g., bilateral or multilateral? (5) Can international collaboration be sensibly attempted without significant increases in funding for HIF? The authors of this report share the conviction that collaboration on a broad scale is mandatory for HIF to have the resources, both financial and personnel, to progress to a demonstration experiment. Ultimately it may be possible for a single driver with the energy, power, focusibility, and pulse shape to satisfy the needs of the international community for target physics research. Such a facility could service multiple experimental chambers with a variety of beam geometries and target concepts.

Herrmannsfeldt, W.B. [Stanford Linear Accelerator Center, Menlo Park, CA (United States); Bangerter, R.O. [Lawrence Berkeley Lab., CA (United States); Bock, R. [Gesellschaft fuer Schwerionenforschung mbH, Darmstadt (Germany); Hogan, W.J.; Lindl, J.D. [Lawrence Livermore National Lab., CA (United States)

1991-10-01T23:59:59.000Z

19

Inertial Confinement Fusion R&D and Nuclear Proliferation  

Science Conference Proceedings (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

20

Inertial Confinement Fusion and the National Ignition Facility (NIF)  

SciTech Connect

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 confinement fusion" 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

Inertial confinement fusion | Princeton Plasma Physics Lab  

NLE Websites -- All DOE Office Websites (Extended Search)

Join Our Mailing List A Collaborative National Center for Fusion & Plasma Research Search form Search Search Home About Overview Learn More Visiting PPPL History...

22

Inertial confinement fusion method producing line source radiation fluence  

DOE Patents (OSTI)

An inertial confinement fusion method in which target pellets are imploded in sequence by laser light beams or other energy beams at an implosion site which is variable between pellet implosions along a line. The effect of the variability in position of the implosion site along a line is to distribute the radiation fluence in surrounding reactor components as a line source of radiation would do, thereby permitting the utilization of cylindrical geometry in the design of the reactor and internal components.

Rose, Ronald P. (Peters Township, Washington County, PA)

1984-01-01T23:59:59.000Z

23

Progress in inertial confinement fusion at Lawrence Livermore National Laboratory  

SciTech Connect

The goals of the Inertial Fusion Program at the Lawrence Livermore National Laboratory are to study matter under extreme conditions of temperature and pressure and to produce fusion energy from inertially confined fusion fuel. With the conclusion of recent multi-kilojoule 0.53 ..mu..m experiments on Novette, we have demonstrated vastly improved plasma conditions compared to those previously obtained at LLNL with similar energies at 1.06 ..mu..m and elsewhere with 10 ..mu..m radiation. The lower preheat environment obtainable with short wavelength light has led to 3X improvements in the compression of targets on Novette compared to similar targets on Shiva with 1.06 ..mu..m. Subsequent experiments on Nova with short wavelength light will begin in 1985. They are expected to demonstrate the necessary compression conditions required for high gain fusion to occur when irradiated with a multi-megajoule driver. These recent results, together with improved calculations, and innovations in driver and reactor technology, indicate that high gain inertial fusion will occur and is a viable candidate for fusion power production in the future.

Holzrichter, J.F.

1984-08-06T23:59:59.000Z

24

Diagnostic measurements related to laser driven inertial confinement fusion  

SciTech Connect

Scientists at the Lawrence Livermore Laboratory have been conducting laser driven inertial confinement fusion experiments for over five years. The first proof of the thermonuclear burn came at the Janus target irradiation facility in the spring of 1975. Since that time three succeedingly higher energy facilities have been constructed at Livermore, Cyclops, Argus and Shiva, where increased fusion efficiency has been demonstrated. A new facility, called Nova, is now in the construction phase and we are hopeful that scientific break even (energy released compared to incident laser energy on target) will be demonstrated here in early 1980's. Projected progress of the Livermore program is shown.

Campbell, D.E.

1979-09-11T23:59:59.000Z

25

Consequences of intensity constraints on inertial confinement fusion  

SciTech Connect

It is shown that the conflicting requirements of high implosion efficiency (low corona temperature) and adequate energy transport (high corona temperature) can, together with other effects, limit useful infrared light intensities to values on the order of 100 Tw/cm/sup 2/. Increased interest in ultraviolet lasers, for which this intensity constraint is expected to be less severe, and the entry of charged-particle drivers in the inertial confinement fusion (ICF) competition are consequences of this limitation. Analytical results based on a simple model are presented which show how the gain of an ICF target is modified by the existence of an arbitrary intensity constraint.

Kidder, R.E.

1979-09-13T23:59:59.000Z

26

Next-generation laser for Inertial Confinement Fusion  

Science Conference Proceedings (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

27

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

28

Heat transfer in inertial confinement fusion reactor systems  

SciTech Connect

The short time and deposition distance for the energy from inertial fusion products results in local peak power densities on the order of 10/sup 18/ watts/m/sup 3/. This paper presents an overview of the various inertial fusion reactor designs which attempt to reduce these peak power intensities and describes the heat transfer considerations for each design.

Hovingh, J.

1980-04-23T23:59:59.000Z

29

Ignition and Inertial Confinement Fusion at The National Ignition Facility  

SciTech Connect

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

30

Heat transfer in inertial confinement fusion reactor systems  

SciTech Connect

The transfer of energy produced by the interaction of the intense pulses of short-ranged fusion microexplosion products with materials is one of the most difficult problems in inertially-confined fusion (ICF) reactor design. The short time and deposition distance for the energy results in local peak power densities on the order of 10/sup 18/ watts/m/sup 3/. High local power densities may cause change of state or spall in the reactor materials. This will limit the structure lifetimes for ICF reactors of economic physical sizes, increasing operating costs including structure replacement and radioactive waste management. Four basic first wall protection methods have evolved: a dry-wall, a wet-wall, a magnetically shielded wall, and a fluid wall. These approaches are distinguished by the way the reactor wall interfaces with fusion debris as well as the way the ambient cavity conditions modify the fusion energy forms and spectra at the first wall. Each of these approaches requires different heat transfer considerations.

Hovingh, J.

1979-05-14T23:59:59.000Z

31

HEAVY ION INERTIAL FUSION  

E-Print Network (OSTI)

in the Tokamak Fusion Test Reactor which will be completedDrivers and Reactors for Inertial Confinement Fusion, K.A.

Keefe, D.

2008-01-01T23:59:59.000Z

32

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

33

Inertial Confinement Fusion quarterly report, January--March 1995. Volume 5, No. 2  

Science Conference Proceedings (OSTI)

The ICF quarterly report is published by the Inertial Confinement Fusion Program at the Lawrence Livermore National Laboratory. Topics included this quarter include: the role of the National Ignition Facility in the development of Inertial Confinement Fusion, laser-plasma interactions in large gas-filled hohlraums, evolution of solid-state induction modulators for a heavy-ion recirculator, the National Ignition Facility project, and terminal-level relaxation in Nd-doped laser material.

NONE

1995-09-01T23:59:59.000Z

34

HEAVY ION INERTIAL FUSION  

E-Print Network (OSTI)

Accelerators as Drivers for Inertially Confined Fusion, W.B.LBL-9332/SLAC-22l (1979) Fusion Driven by Heavy Ion Beams,OF CALIFORNIA f Accelerator & Fusion Research Division

Keefe, D.

2008-01-01T23:59:59.000Z

35

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

SciTech Connect

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

36

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

E-Print Network (OSTI)

Basics of Inertial Confinement Fusion John Lindl NIF and Photon Science Directorate Chief Scientist (NIC) · Opportunities for the future on NIF #12;Fusion can be accomplished in three different ways density) 102 103 104 105 500 50 5 0.5 Capsule energy (KJ) NIF Relaxed pressure and stability requirements

37

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

Science Conference Proceedings (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

38

The VISTA spacecraft: Advantages of ICF (Inertial Confinement Fusion) for interplanetary fusion propulsion applications  

SciTech Connect

Inertial Confinement Fusion (ICF) is an attractive engine power source for interplanetary manned spacecraft, especially for near-term missions requiring minimum flight duration, because ICF has inherent high power-to-mass ratios and high specific impulses. We have developed a new vehicle concept called VISTA that uses ICF and is capable of round-trip manned missions to Mars in 100 days using A.D. 2020 technology. We describe VISTA's engine operation, discuss associated plasma issues, and describe the advantages of DT fuel for near-term applications. Although ICF is potentially superior to non-fusion technologies for near-term interplanetary transport, the performance capabilities of VISTA cannot be meaningfully compared with those of magnetic-fusion systems because of the lack of a comparable study of the magnetic-fusion systems. We urge that such a study be conducted.

Orth, C.D.; Klein, G.; Sercel, J.; Hoffman, N.; Murray, K.; Chang-Diaz, F.

1987-10-02T23:59:59.000Z

39

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

Science Conference Proceedings (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

40

Inertial Confinement Fusion: Quarterly report, April-June 1996  

SciTech Connect

The lead article, `Ion-beam propagation in a low-density reactor chamber for heavy-ion inertial fusion` (p. 89), explores the ability of heavy-ion beams to be adequately transported and focused in an IFE reactor. The next article, `Efficient production and applications of 2- to 10-keV x rays by laser-heated underdense radiators` (p. 96), explores the ability of the NIF to produce sufficient high-energy x rays for diagnostic backlighting, target preheating, or uniform irradiation of large test objects for Nuclear Weapons Effects Testing. For capsule implosion experiments, the increasing energies and distances involved in the NIF compared to Nova require the development of new diagnostics methods. The article `Fusion reaction-rate measurements--Nova and NIF` (p. 115) first reviews the use of time-resolved neutron measurements on Nova to monitor fusion burn histories and then explores the limitations of that technique, principally Doppler broadening, for the proposed NIF. It also explores the use of gamma rays on Nova, thereby providing a proof-of-principle for using gamma rays for monitoring fusion burn histories on the NIF. The articles `The energetics of gas-filled hohlraums` (p. 110) and `Measurements of laser- speckle-induced perturbations in laser-driven foils` (p. 123) report measurements on Nova of two important aspects of implosion experiments. The first characterizes the amount of energy lost from a hohlraum by stimulated Brillouin and Raman scattering as a function of gas fill and laser-beam uniformity. The second of these articles shows that the growth of density nonuniformities implanted on smooth capsule surfaces by laser speckle can be correlated with the effects of physical surface roughness. The article `Laser-tissue interaction modeling with the LATIS computer program` (p. 103) explores the use of modeling to enhance the effectiveness--maximize desired effects and minimize collateral damage--of lasers for medical purposes.

Correll, D.

1996-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "inertial confinement fusion" 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

Inertial confinement fusion quarterly report, July--September 1994. Volume 4, Number 4  

Science Conference Proceedings (OSTI)

The ICF Quarterly continues with six articles in this issue describing recent developments in the Inertial Confinement Fusion (ICF) Program at Lawrence Livermore National Laboratory. The topics include plasma characterization, production of millimeter scale-length plasmas for studying laser-plasma instabilities, hohlraum physics, three-dimensional hydrodynamic modeling, crystal growth, and laser-beam smoothing.

Honea, E. [ed.

1994-09-01T23:59:59.000Z

42

A review of Vlasov-Fokker-Planck numerical modeling of inertial confinement fusion plasma  

Science Conference Proceedings (OSTI)

The interaction of intense lasers with solid matter generates a hot plasma state that is well described by the Vlasov-Fokker-Planck equation. Accurate and efficient modeling of the physics in these scenarios is highly pertinent, because it relates to ... Keywords: Computational, Fast electron transport, Fokker-Planck, Inertial confinement fusion, Laser, Magnetic field, Plasma, Vlasov

A. G. R. Thomas; M. Tzoufras; A. P. L. Robinson; R. J. Kingham; C. P. Ridgers; M. Sherlock; A. R. Bell

2012-02-01T23:59:59.000Z

43

ION ACCELERATORS AS DRIVERS FOR INERTIAL CONFINEMENT FUSION  

E-Print Network (OSTI)

and Controlled Nuclear Fusion Research, Brussels, Belgium,of the Heavy Ion Fusion Workshop held at Brookhaven NationalReport, Hearthfire Heavy Ion Fusion, October 1, 1979 - March

Faltens, A.

2010-01-01T23:59:59.000Z

44

Simulating the magnetized liner inertial fusion plasma confinement with smaller-scale experiments  

Science Conference Proceedings (OSTI)

The recently proposed magnetized liner inertial fusion approach to a Z-pinch driven fusion [Slutz et al., Phys. Plasmas 17, 056303 (2010)] is based on the use of an axial magnetic field to provide plasma thermal insulation from the walls of the imploding liner. The characteristic plasma transport regimes in the proposed approach cover parameter domains that have not been studied yet in either magnetic confinement or inertial confinement experiments. In this article, an analysis is presented of the scalability of the key physical processes that determine the plasma confinement. The dimensionless scaling parameters are identified and conclusion is drawn that the plasma behavior in scaled-down experiments can correctly represent the full-scale plasma, provided these parameters are approximately the same in two systems. This observation is important in that smaller-scale experiments typically have better diagnostic access and more experiments per year are possible.

Ryutov, D. D. [Lawrence Livermore National Laboratory, Livermore, California 94551 (United States); Cuneo, M. E.; Herrmann, M. C.; Sinars, D. B.; Slutz, S. A. [Sandia National Laboratories, Albuquerque, New Mexico 87185 (United States)

2012-06-15T23:59:59.000Z

45

New Insight into Gridded Inertial Electrostatic Confinement (IEC) Fusion Devices  

Science Conference Proceedings (OSTI)

Alternate Concepts & Magnets / Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2)

G. L. Kulcinski et al.

46

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

Science Conference Proceedings (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

47

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

Science Conference Proceedings (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

48

Primary heat transfer loop design for the Cascade inertial confinement fusion reactor  

Science Conference Proceedings (OSTI)

This study investigates a heat exchanger and balance of plant design to accompany the Cascade inertial confinement fusion reaction chamber concept. The concept uses solid Li/sub 2/O or other lithium-ceramic granules, held to the wall of a rotating reaction chamber by centrifugal action, as a tritium breeding blanket and first wall protection. The Li/sub 2/O granules enter the chamber at 800 K and exit at 1200 K after absorbing the thermal energy produced by the fusion process.

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

1984-05-01T23:59:59.000Z

49

Pre-Amplifier Module for Laser Inertial Confinement Fusion  

SciTech Connect

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

Heebner, J E; Bowers, M W

2008-02-06T23:59:59.000Z

50

K-alpha conversion efficiency measurments for x-ray scattering in inertial confinement fusion plasmas  

SciTech Connect

The conversion efficiency of ultra short-pulse laser radiation to K-{alpha} x-rays has been measured for various chlorine-containing targets to be used as x-ray scattering probes of dense plasmas. The spectral and temporal properties of these sources will allow spectrally-resolved x-ray scattering probing with picosecond temporal resolution required for measuring the plasma conditions in inertial confinement fusion experiments. Simulations of x-ray scattering spectra from these plasmas show that fuel capsule density, capsule ablator density, and shock timing information may be inferred.

Kritcher, A L; Neumayer, P; Urry, M K; Robey, H; Niemann, C; Landen, O L; Morse, E; Glenzer, S H

2006-11-21T23:59:59.000Z

51

Driving high-gain shock-ignited inertial confinement fusion targets by green laser light  

Science Conference Proceedings (OSTI)

Standard direct-drive inertial confinement fusion requires UV light irradiation in order to achieve ignition at total laser energy of the order of 1 MJ. The shock-ignition approach opens up the possibility of igniting fusion targets using green light by reducing the implosion velocity and laser-driven ablation pressure. An analytical model is derived, allowing to rescale UV-driven targets to green light. Gain in the range 100-200 is obtained for total laser energy in the range 1.5-3 MJ. With respect to the original UV design, the rescaled targets are less sensitive to irradiation asymmetries and hydrodynamic instabilities, while operating in the same laser-plasma interaction regime.

Atzeni, Stefano; Marocchino, Alberto; Schiavi, Angelo [Dipartimento SBAI, Universita di Roma 'La Sapienza' and CNISM, Via A. Scarpa 14-16, I-00161 Roma (Italy)

2012-09-15T23:59:59.000Z

52

Inertial confinement fusion quarterly report, April--June 1994. Volume 4, Number 3  

SciTech Connect

This issue of the ICF Quarterly contains six articles covering a wide range of activities within the Inertial Confinement Fusion (ICF) Program. It concentrates on target design; theoretical spectral analysis of ICF capsule surfaces; laser fusion experimental methods; and an alternative ICF design, based on ultrafast, ultrapowerful lasers. A key issue for the success of the ICF process is the hydrodynamic stability of the imploding capsule. There are two primary sources of instability growth in the ICF process: (1) asymmetries in the x-ray flux that drive the compression lead to asymmetric in the imploding surface; (2) imperfections on the capsule surface can grow into large perturbations, degrading the capsule performance. In recent years, a great deal of effort, both experimentally and theoretically, has been spent to enhance the Program`s ability to measure, model, and minimize instability growth during an implosion. Four the articles in this issue discuss this subject.

Shaw, M.J. [ed.

1994-06-01T23:59:59.000Z

53

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

SciTech Connect

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

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

1980-01-01T23:59:59.000Z

54

KrF laser path to high gain ICF (inertial confinement fusion) laboratory microfusion facility  

SciTech Connect

The krypton-fluoride laser has many desirable features for inertial confinement fusion. Because it is a gas laser capable of operation with high efficiency, it is the only known laser candidate capable of meeting the driver requirements for inertial fusion energy (IFE) production. Los Alamos National Laboratory has defined a program plan to develop KrF lasers for IFE production. This plan develops the KrF laser and demonstrates the target performance in single-pulse facilities. A 100-kJ Laser Target Test Facility (LTTF) is proposed as the next step, to be followed by a 3 to 10-MJ Laboratory Microfusion Facility (LMF). The LTTF will resolve many target physics issues and accurately define the driver energy required for the LMF. It is also proposed that the technology development for IFE, such as the high-efficiency, high-reliability, repetitively pulsed driver, the reactor, mass production of targets, and the mechanism of injecting targets be developed in parallel with the single-pulse facilities. 11 refs., 4 figs.

Harris, D.B.; Sullivan, J.A.; Figueiro, J.F.; Cartwright, D.C.; McDonald, T.E.; Hauer, A.A.; Coggeshall, S.V.; Younger, S.M.

1990-01-01T23:59:59.000Z

55

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)

Energy spectra and spectrally resolved one-dimensional fluence images of self-emitted charged-fusion products (14.7 MeV D[superscript 3]He protons) are routinely measured from indirectly driven inertial-confinement fusion ...

Li, C. K.

56

Production and measurement of engineered surfaces for inertial confinement fusion research  

SciTech Connect

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

57

Interactive tools designed to study mix in inertial confinement fusion implosions  

SciTech Connect

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

58

Summary of research for the Inertial Confinement Fusion Program at Los Alamos National Laboratory  

SciTech Connect

The information presented in this report is a summary of the status of the Inertial Confinement Fusion (ICF) program at the Los Alamos National Laboratory as of February 1985. This report contains material on the existing high-power CO/sub 2/ laser driver (Antares), the program to determine the potential of KrF as an ICF driver, heavy-ion accelerators as drivers for ICF, target fabrication for ICF, and a summary of our understanding of laser-plasma interactions. A classified companion report contains material on our current understanding of capsule physics and lists the contributions to the Laboratory's weapons programs made by the ICF program. The information collected in these two volumes is meant to serve as a report on the status of some of the technological components of the Los Alamos ICF program rather than a detailed review of specific technical issues.

Cartwright, D.C. (comp.)

1985-03-01T23:59:59.000Z

59

Inertial Confinement Fusion Quarterly Report: April--June 1993. Volume 3, Number 3  

SciTech Connect

This issue of the ICF Quarterly contains six articles describing recent advances in Lawrence Livermore National Laboratory`s inertial confinement fusion (ICF) program. The current emphasis of the ICF program is in support of DOE`s National Ignition Facility (NIF) initiative for demonstrating ignition and gain with a 1-2 MJ glass laser. The articles describe recent Nova experiments and investigations tailored towards enhancing understanding of the key physics and technological issues for the NIF. Titles of the articles are: development of large-aperture KDP crystals; inner-shell photo-ionized X-ray lasers; X-ray radiographic measurements of radiation-driven shock and interface motion in solid density materials; the role of nodule defects in laser-induced damage of multilayer optical coatings; techniques for Mbar to near-Gbar equation-of-state measurements with the Nova laser; parametric instabilities and laser-beam smoothing.

MacGowan, B.J.; Kotowski, M.; Schleich, D. [eds.

1993-11-01T23:59:59.000Z

60

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

Science Conference Proceedings (OSTI)

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

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

1980-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "inertial confinement fusion" 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

Inertial confinement fusion reaction chamber and power conversion system study. Final report  

Science Conference Proceedings (OSTI)

This report summarizes the results of the second year of a two-year study on the design and evaluation of the Cascade concept as a commercial inertial confinement fusion (ICF) reactor. We developed a reactor design based on the Cascade reaction chamber concept that would be competitive in terms of both capital and operating costs, safe and environmentally acceptable in terms of hazard to the public, occupational exposure and radioactive waste production, and highly efficient. The Cascade reaction chamber is a double-cone-shaped rotating drum. The granulated solid blanket materials inside the rotating chamber are held against the walls by centrifugal force. The fusion energy is captured in a blanket of solid carbon, BeO, and LiAlO/sub 2/ granules. These granules are circulated to the primary side of a ceramic heat exchanger. Primary-side granule temperatures range from 1285 K at the LiAlO/sub 2/ granule heat exchanger outlet to 1600 K at the carbon granule heat exchanger inlet. The secondary side consists of a closed-cycle gas turbine power conversion system with helium working fluid, operating at 1300 K peak outlet temperature and achieving a thermal power conversion efficiency of 55%. The net plant efficiency is 49%. The reference design is a plant producing 1500 MW of D-T fusion power and delivering 815 MW of electrical power for sale to the utility grid. 88 refs., 44 figs., 47 tabs.

Maya, I.; Schultz, K.R.; Bourque, R.F.; Cheng, E.T.; Creedon, R.L.; Norman, J.H.; Price, R.J.; Porter, J.; Schuster, H.L.; Simnad, M.J.

1985-10-01T23:59:59.000Z

62

Mechanism for magnetic field generation and growth in Rayleigh-Taylor unstable inertial confinement fusion plasmas  

Science Conference Proceedings (OSTI)

Rayleigh-Taylor instabilities (RTI) in inertial confinement fusion (ICF) implosions are expected to generate magnetic fields at the gas-ice interface and at the ice-ablator interface. The focus here is on the gas-ice interface where the temperature gradient is the largest. A Hall-MHD model is used to study the magnetic field generation and growth for 2-D single-mode and multimode RTI in a stratified two-fluid plasma, the two fluids being ions and electrons. Self-generated magnetic fields are observed and these fields grow as the RTI progresses via the {nabla}n{sub e} Multiplication-Sign {nabla}T{sub e} term in the generalized Ohm's law. Srinivasan et al.[Phys. Rev. Lett. 108, 165002 (2012)] present results of the magnetic field generation and growth, and some scaling studies in 2-dimensions. The results presented here study the mechanism behind the magnetic field generation and growth, which is related to fluid vorticity generation by RTI. The magnetic field wraps around the bubbles and spikes and concentrates in flux bundles at the perturbed gas-ice interface where fluid vorticity is large. Additionally, the results of Srinivasan et al.[Phys. Rev. Lett. 108, 165002 (2012)] are described in greater detail. Additional scaling studies are performed to determine the growth of the self-generated magnetic field as a function of density, acceleration, perturbation wavelength, Atwood number, and ion mass.

Srinivasan, Bhuvana; Tang Xianzhu [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, New Mexico 87545 (United States)

2012-08-15T23:59:59.000Z

63

Pulsed power considerations for electron beam pumped krypton fluoride lasers for inertial confinement fusion applications  

SciTech Connect

The Los Alamos National Laboratory inertial confinement fusion (ICF) program is developing the krypton-fluoride excimer laser for use as an ICF driver. The KrF laser has a number of inherent characteristics that make it a promising driver candidate, such as short wavelength (0.25 {mu}m), broad bandwidth to target (>100 cm{sup {minus}1}), pulse-shaping with high dynamic range, and the potential for high overall efficiency (>5%) and repetitive operation. The large KrF laser amplifiers needed for ICF drivers are electron-beam pumped. A key issue for all laser ICF drivers is cost, and a leading cost component of a KrF laser driver is associated with the pulsed power and electron diode. Therefore, the efficient generation of electron beams is a high priority. The Los Alamos ICF program is investigating pulsed-power and diode designs and technologies to further the development of affordable KrF laser ICF drivers. 12 refs., 8 figs.

Rose, E.A.; McDonald, T.E.; Rosocha, L.A.; Harris, D.B.; Sullivan, J.A. (Los Alamos National Lab., NM (USA)); Smith, I.D. (Pulse Sciences, Inc., San Leandro, CA (USA))

1991-01-01T23:59:59.000Z

64

Precision Manufacturing of Inertial Confinement Fusion Double Shell Laser Targets for OMEGA  

SciTech Connect

Double shell targets have been built by Lawrence Livermore National Laboratory (LLNL) for inertial confinement fusion (ICF) experiments on the Omega laser at the University of Rochester and as a prelude to similar experiments on NIF. Of particular interest to ICF studies are high-precision double shell implosion targets for demonstrating thermonuclear ignition without the need for cryogenic preparation. Because the ignition tolerance to interface instabilities is rather low, the manufacturing requirements for smooth surface finishes and shell concentricity are particularly strict. This paper describes a deterministic approach to manufacturing and controlling error sources in each component. Included is the design philosophy of why certain manufacturing techniques were chosen to best reduce the errors within the target. The manufacturing plan developed for this effort created a deterministic process that, once proven, is repeatable. By taking this rigorous approach to controlling all error sources during the manufacture of each component and during assembly, we have achieved the overall 5 {micro}m dimensional requirement with sub-micron surface flaws. Strengths and weaknesses of the manufacturing process will be discussed.

Amendt, P A; Bono, M J; Hibbard, R L; Castro, C; Bennett, D W

2003-11-21T23:59:59.000Z

65

Investigation of radial wire arrays for inertial confinement fusion and radiation effects science.  

SciTech Connect

Radial wire arrays provide an alternative x-ray source for Z-pinch driven Inertial Confinement Fusion. These arrays, where wires are positioned radially outwards from a central cathode to a concentric anode, have the potential to drive a more compact ICF hohlraum. A number of experiments were performed on the 7MA Saturn Generator. These experiments studied a number of potential risks in scaling radial wire arrays up from the 1MA level, where they have been shown to provide similar x-ray outputs to larger diameter cylindrical arrays, to the higher current levels required for ICF. Data indicates that at 7MA radial arrays can obtain higher power densities than cylindrical wire arrays, so may be of use for x-ray driven ICF on future facilities. Even at the 7MA level, data using Saturn's short pulse mode indicates that a radial array should be able to drive a compact hohlraum to temperatures {approx}92eV, which may be of interest for opacity experiments. These arrays are also shown to have applications to jet production for laboratory astrophysics. MHD simulations require additional physics to match the observed behavior.

Serrano, Jason Dimitri; Bland, Simon Nicholas (Imperial College, London); McBride, Ryan D.; Chittenden, Jeremy Paul (Imperial College, London); Suzuki-Vidal, Francisco Andres (Imperial College, London); Jennings, Christopher A.; Hall, Gareth Neville (Imperial College, London); Ampleford, David J.; Peyton, Bradley Philip; Lebedev, Sergey V. (Imperial College, London); Cleveland, Monica; Rogers, Thomas John; Cuneo, Michael Edward; Coverdale, Christine Anne; Jones, Brent Manley; Jones, Michael C.

2010-02-01T23:59:59.000Z

66

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

SciTech Connect

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

67

Inertial confinement fusion. ICF quarterly report, October 1993--December 1993, Volume 4, Number 1  

Science Conference Proceedings (OSTI)

In the 1990 National Academy of Sciences (NAS) report of its review of the U.S. Inertial Confinement Fusion (ICF) Program, it was recommended that a high priority be placed on completing the Precision Nova Project and its associated experimental campaign. Since fiscal year 1990, the lab has therefore campaigned vigorously on Nova and in its supporting laboratories to develop the Precision Nova capabilities needed to perform the stressful target experiments recommended in the 1990 NAS report. The activities to enable these experiments have been directed at improvements in three areas - the Nova laser, target fabrication capabilities, and target diagnostics. As summarized in the five articles in this report, the Precision Nova improvements have been successfully completed. These improvements have had a positive impact on target performance and on the ability to diagnose the results, as evidenced by the HEP-1 experimental results. The five articles generally concentrate on improvements to the capabilities rather than on the associated target physics experiments. Separate abstracts are included for each paper.

Powell, H.T.; Schleich, D.P.; Murphy, P.W. [eds.

1994-05-01T23:59:59.000Z

68

Overview of the VISTA Spacecraft Concept Powered by Inertial Confinement Fusion  

DOE Green Energy (OSTI)

VISTA was conceived through a detailed systems analysis as a viable, realistic, and defensible spacecraft concept based on advanced ICF technology but existing or near-term technology for other systems. It is a conical self-contained single-stage piloted spacecraft in which a magnetic thrust chamber directs the plasma emissions from inertial confinement fusion (ICF) targets into a rearward exhaust. VISTA's propulsion system is therefore unique because it is based on (1) a rather mature technology (ICF), which is known to work with sufficient driver input; (2) direct heating of all expellant by the fusion process, thus providing high mass flow rates without significant degradation of jet efficiency; and (3) a magnetic thrust chamber, which avoids the plasma thermalization and resultant degradation of specific impulse that are unavoidable with the use of mechanical thrust chambers. VISTA therefore has inherently high power/mass ratios and high specific impulses. With advanced ICF technology, ultra-fast roundtrips (RTs) to objects within the solar system are possible (e.g., {ge}145 days RT to Mars, {ge}7 years RT to Pluto). Such short-duration missions are imperative to minimize the human physiological deteriorations arising from zero gravity and the cosmic-radiation. In addition, VISTA offers on-board artificial gravity and propellant-based shielding from cosmic rays, thus reducing the physiological deteriorations to insignificant levels. In this paper, we give an overview of the various vehicle systems for this concept, estimate the general missions performance capabilities for interplanetary missions, and describe in detail the performance for the baseline mission of a piloted roundtrip to Mars with a 100-ton payload. Items requiring further research include a reduction of the wet mass from its baseline value of 6,000 metric tons, and the development of fast ignition or its equivalent to provide target gains in excess of several hundred. With target gains well above several hundred, there is no other known technology that can compete with VISTA's performance.

Orth, C D

2000-11-21T23:59:59.000Z

69

On the Utility of Antiprotons as Drivers for Inertial Confinement Fusion  

DOE Green Energy (OSTI)

By contrast to the large mass, complexity and recirculating power of conventional drivers for inertial confinement fusion (ICF), antiproton annihilation offers a specific energy of 90MJ/{micro}g and thus a unique form of energy packaging and delivery. In principle, antiproton drivers could provide a profound reduction in system mass for advanced space propulsion by ICF. We examine the physics underlying the use of antiprotons ({bar p}) to drive various classes of high-yield ICF targets by the methods of volumetric ignition, hotspot ignition and fast ignition. The useable fraction of annihilation deposition energy is determined for both {bar p}-driven ablative compression and {bar p}-driven fast ignition, in association with 0-D and 1-D target burn models. Thereby, we deduce scaling laws for the number of injected antiprotons required per capsule, together with timing and focal spot requirements. The kinetic energy of the injected antiproton beam required to penetrate to the desired annihilation point is always small relative to the deposited annihilation energy. We show that heavy metal seeding of the fuel and/or ablator is required to optimize local deposition of annihilation energy and determine that a minimum of {approx}3x10{sup 15} injected antiprotons will be required to achieve high yield (several hundred megajoules) in any target configuration. Target gains - i.e., fusion yields divided by the available p - {bar p} annihilation energy from the injected antiprotons (1.88GeV/{bar p}) - range from {approx}3 for volumetric ignition targets to {approx}600 for fast ignition targets. Antiproton-driven ICF is a speculative concept, and the handling of antiprotons and their required injection precision - temporally and spatially - will present significant technical challenges. The storage and manipulation of low-energy antiprotons, particularly in the form of antihydrogen, is a science in its infancy and a large scale-up of antiproton production over present supply methods would be required to embark on a serious R&D program for this application.

Perkins, L J; Orth, C D; Tabak, M

2003-10-20T23:59:59.000Z

70

VISTA -- A Vehicle for Interplanetary Space Transport Application Powered by Inertial Confinement Fusion  

DOE Green Energy (OSTI)

Inertial Confinement Fusion (ICF) is an ideal technology to power self-contained single-stage piloted (manned) spacecraft within the solar system because of its inherently high power/mass ratios and high specific impulses (i.e., high exhaust velocities). These technological advantages are retained when ICF is utilized with a magnetic thrust chamber, which avoids the plasma thermalization and resultant degradation of specific impulse that are unavoidable with the use of mechanical thrust chambers. We started with Rod Hyde's 1983 description of an ICF-powered engine concept using a magnetic thrust chamber, and conducted a more detailed systems study to develop a viable, realistic, and defensible spacecraft concept based on ICF technology projected to be available in the first half of the 21st century. The results include an entirely new conical spacecraft conceptual design utilizing near-existing radiator technology. We describe the various vehicle systems for this new concept, estimate the missions performance capabilities for general missions to the planets within the solar system, and describe in detail the performance for the baseline mission of a piloted roundtrip to Mars with a 100-ton payload. For this mission, we show that roundtrips totaling {ge}145 days are possible with advanced DT fusion technology and a total (wet) spacecraft mass of about 6000 metric tons. Such short-duration missions are advantageous to minimize the known cosmic-radiation hazards to astronauts, and are even more important to minimize the physiological deteriorations arising from zero gravity. These ICF-powered missions are considerably faster than those available using chemical or nuclear-electric-propulsion technologies with minimum-mass vehicle configurations. VISTA also offers onboard artificial gravity and propellant-based shielding from cosmic rays, thus reducing the known hazards and physiological deteriorations to insignificant levels. We emphasize, however, that the degree to which an ICF-powered vehicle can outperform a vehicle using any other realistic technology depends on the degree to which terrestrial-based ICF research can develop the necessary energy gain from ICF targets. With aggressive progress in such terrestrial research, VISTA will be able to make roundtrip missions to Pluto in {approx}7 years, and missions to points just beyond the solar system within a human lifetime.

Orth, C D

2005-03-31T23:59:59.000Z

71

Simultaneous usage of pinhole and penumbral apertures for imaging small scale neutron sources from inertial confinement fusion experiments  

SciTech Connect

Inertial confinement fusion experiments at the National Ignition Facility are designed to understand the basic principles of creating self-sustaining fusion reactions by laser driven compression of deuterium-tritium (DT) filled cryogenic plastic capsules. The neutron imaging diagnostic provides information on the distribution of the central fusion reaction region and the surrounding DT fuel by observing neutron images in two different energy bands for primary (13-17 MeV) and down-scattered (6-12 MeV) neutrons. From this, the final shape and size of the compressed capsule can be estimated and the symmetry of the compression can be inferred. These experiments provide small sources with high yield neutron flux. An aperture design that includes an array of pinholes and penumbral apertures has provided the opportunity to image the same source with two different techniques. This allows for an evaluation of these different aperture designs and reconstruction algorithms.

Guler, N.; Volegov, P.; Danly, C. R.; Grim, G. P.; Merrill, F. E.; Wilde, C. H. [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, New Mexico 87545 (United States)

2012-10-15T23:59:59.000Z

72

NNSA Defense Programs Inertial Confinement Fusion Ignition and High Yield Campaign  

E-Print Network (OSTI)

and the NIF Project #12;2 Outline · National Nuclear Security Administration · ICF Campaign and Stewardship overview · NIF Use Plan ­ Defense Science Board review (Ignition 2010) · Recent progress ­ NIF, OMEGA, Z Confinement Fusion Acting Director Dr. Richard K. Thorpe NA-161 Office of the NIF Project Acting Director

73

Neutron Transport and Nuclear Burnup Analysis for the Laser Inertial Confinement Fusion-Fission Energy (LIFE) Engine  

Science Conference Proceedings (OSTI)

Lawrence Livermore National Laboratory is currently developing a hybrid fusion-fission nuclear energy system, called LIFE, to generate power and burn nuclear waste. We utilize inertial confinement fusion to drive a subcritical fission blanket surrounding the fusion chamber. It is composed of TRISO-based fuel cooled by the molten salt flibe. Low-yield (37.5 MJ) targets and a repetition rate of 13.3 Hz produce a 500 MW fusion source that is coupled to the subcritical blanket, which provides an additional gain of 4-8, depending on the fuel. In the present work, we describe the neutron transport and nuclear burnup analysis. We utilize standard analysis tools including, the Monte Carlo N-Particle (MCNP) transport code, ORIGEN2 and Monteburns to perform the nuclear design. These analyses focus primarily on a fuel composed of depleted uranium not requiring chemical reprocessing or enrichment. However, other fuels such as weapons grade plutonium and highly-enriched uranium are also under consideration. In addition, we have developed a methodology using {sup 6}Li as a burnable poison to replace the tritium burned in the fusion targets and to maintain constant power over the lifetime of the engine. The results from depleted uranium analyses suggest up to 99% burnup of actinides is attainable while maintaining full power at 2GW for more than five decades.

Kramer, K J; Latkowski, J F; Abbott, R P; Boyd, J K; Powers, J J; Seifried, J E

2008-10-24T23:59:59.000Z

74

Inertial Confinement Fusion Target Component Fabrication and Technology Development report. Annual report, October 1, 1992--September 30, 1993  

Science Conference Proceedings (OSTI)

On December 30, 1990, the US Department of Energy entered into a contract with General Atomics (GA) to be the Inertial Confinement Fusion Target Component Fabrication and Technology Development Support contractor. This report documents the technical activities which took place under this contract during the period of October 1, 1992 through September 30, 1993. During this period, GA was assigned 18 tasks in support of the Inertial Confinement Fusion program and its laboratories. These tasks included ``Capabilities Activation`` and ``Capabilities Demonstration`` to enable us to begin production of glass and composite polymer capsules. Capsule delivery tasks included ``Small Glass Shell Deliveries`` and ``Composite Polymer Capsules`` for Lawrence Livermore National Laboratory (LLNL) and Los Alamos National Laboratory (LANL). We also were asked to provide direct ``Onsite Support`` at LLNL and LANL. We continued planning for the transfer of ``Micromachining Equipment from Rocky Flats`` and established ``Target Component Micromachining and Electroplating Facilities`` at GA. We fabricated over 1100 films and filters of 11 types for Sandia National Laboratory and provided full-time onsite engineering support for target fabrication and characterization. We initiated development of methods to make targets for the Naval Research Laboratory. We investigated spherical interferometry, built an automated capsule sorter, and developed an apparatus for calorimetric measurement of fuel fill for LLNL. We assisted LANL in the ``Characterization of Opaque b-Layered Targets.`` We developed deuterated and UV-opaque polymers for use by the University of Rochester`s Laboratory for Laser Energetics (UR/LLE) and devised a triple-orifice droplet generator to demonstrate the controlled-mass nature of the microencapsulation process.

Steinman, D. [ed.

1994-03-01T23:59:59.000Z

75

Inertial confinement fusion target component fabrication and technology development support: Annual report, October 1, 1993--September 30, 1994  

Science Conference Proceedings (OSTI)

On December 30, 1990, the US Department of Energy entered into a contract with General Atomics (GA) to be the Inertial Confinement Fusion (ICF) Target Component Fabrication and Technology Development Support contractor. During the period, GA was assigned 17 tasks in support of the Inertial Confinement Fusion program and its laboratories. This year they achieved full production capabilities for the micromachining, dimensional characterization and gold plating of hohlraums. They fabricated and delivered 726 gold-plated mandrels of 27 different types to LLNL and 48 gold-plated mandrels of two different types to LANL. They achieved full production capabilities in composite capsule production ad delivered in excess of 240 composite capsules. They continuously work to improve performance and capabilities. They were also directed to dismantle, remove, and disposition all equipment at the previous contractor (KMSF) that had radioactive contamination levels low enough that they could be exposed to the general public without radiological constraints. GA was also directed to receive and store the tritium fill equipment. They assisted LANL in the development of techniques for characterization of opaque targets. They developed deuterated and UV-opaque polymers for use by the University of Rochester`s Laboratory for Laser Energetics (UR/LLE) and devised a triple-orifice droplet generator to demonstrate the controlled-mass nature of the microencapsulation process. The ICF program is anticipating experiments at NIF and the Omega Upgrade. Both facilities will require capsules containing layered D{sub 2} or D-T fuel. They continued engineering and assembly of equipment for a cryogenic target handling system for UR/LLE that will fill, transport, layer, and characterize targets filled with cryogenic deuterium or deuterium-tritium fuel, and insert these cryogenic targets into the OMEGA Upgrade target chamber for laser implosion experiments.

Hoppe, M. [ed.

1995-04-01T23:59:59.000Z

76

Inertial Confinement Fusion quarterly report, January-March 1998, volume 8, number 2  

SciTech Connect

The coupling of laser light with plasmas is one of the key physics issues for the use of high-power lasers for inertial fusion, high-energy-density physics, and scientific stockpile stewardship. The coupling physics is extremely rich and challenging, particularly in the large plasmas to be accessed on the National Ignition Facility (NIF). The coupling mechanisms span the gamut from classical inverse bremsstrahlung absorption to a variety of nonlinear optical processes. These include stimulated Raman scattering (SRS) from electron plasma waves, stimulated Brillouin scattering (SBS) from ion sound waves, resonant decay into electron plasma and ion sound waves, and laser beam filamentation. These processes depend on laser intensity and produce effects such as changes in the efficiency and location of the energy deposition or generation of a component of very energetic electrons, which can preheat capsules. Coupling physics issues have an extremely high leverage. The coupling models are clearly very important ingredients for detailed calculations of laser-irradiated target behavior. Improved understanding and models enable a more efficient use of laser facilities, which becomes even more important as these facilities become larger and more expensive. Advances in the understanding also allow a more timely and cost-effective identification of new applications of high-power lasers, such as for generation of high-temperature hohlraums and compact x-ray sources, or for discovery of advanced fusion schemes. Finally, the interaction of intense electromagnetic waves with ionized media is a fundamental topic of interest to numerous areas of applied science and is an excellent test bed for advancing plasma science and computational modeling of complex phenomena. This issue of the ICF Quarterly Report is dedicated to laser--plasma interactions. The eight articles present a cross section of the broad progress in understanding the key interaction issues, such as laser beam bending, spraying, and scattering, as well as scaling the Nova results to NIF.

Kruer, W

1998-03-31T23:59:59.000Z

77

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

E-Print Network (OSTI)

29 The Fission-fusion Hybrid - iii - General DiscussionInteraction in Heavy Ion Fusion BIBLIOGRAPHY HEAVY IONReactor Designs . . . 27 Pure Fusion Power Reactor Tritium

Herrmannsfeldt, W.b.

2010-01-01T23:59:59.000Z

78

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

E-Print Network (OSTI)

BEAMS QF A P.ELLET FUSION REACTOR BY.fiUADRUPOLJ"DOUBLETS,prefer much smaller fusion reactors. In view of the evidencecertain that soie pure fusion reactor scenarios exist with

Herrmannsfeldt, W.b.

2010-01-01T23:59:59.000Z

79

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

80

Fusion-Fission Hybrid Using a D-D Cylindrical Inertial Electrostatic Confinement (IEC) Driver  

Science Conference Proceedings (OSTI)

Fusion-Fission Hybrids and Transmutation / Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems

George H. Miley; Bradley Boyer

Note: This page contains sample records for the topic "inertial confinement fusion" from the National Library of EnergyBeta (NLEBeta).
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81

Non-Electric Applications of the Inertial Electrostatic Confinement Fusion Concept  

Science Conference Proceedings (OSTI)

Alternate Concepts/Applications / Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 1), Nashville, Tennessee, August 27-31, 2012

Gerald L. Kulcinski; John F. Santarius

82

Kinetic simulations of stimulated Raman backscattering and related processes for the shock-ignition approach to inertial confinement fusion  

Science Conference Proceedings (OSTI)

A detailed description of stimulated Raman backscattering and related processes for the purpose of inertial confinement fusion requires multi-dimensional kinetic simulations of a full speckle in a high-temperature, large-scale, inhomogeneous plasma. In particular for the shock-ignition scheme operating at high laser intensities, kinetic aspects are predominant. High- (I{lambda}{sub o}{sup 2}{approx}5x10{sup 15}W{mu}m{sup 2}/cm{sup 2}) as well as low-intensity (I{lambda}{sub o}{sup 2}{approx}10{sup 15}W{mu}m{sup 2}/cm{sup 2}) cases show the predominance of collisionless, collective processes for the interaction. While the two-plasmon decay instability and the cavitation scenario are hardly affected by intensity variation, inflationary Raman backscattering proves to be very sensitive. Brillouin backscattering evolves on longer time scales and dominates the reflectivities, although it is sensitive to the intensity. Filamentation and self-focusing do occur for all cases but on time scales too long to affect Raman backscattering.

Riconda, C.; Weber, S. [LULI, Universite Paris 6 - Ecole Polytechnique - CNRS - CEA, 75252 Paris (France); Tikhonchuk, V. T. [CELIA, Universite Bordeaux 1 - CNRS - CEA, 33405 Talence (France); Heron, A. [CPHT, Ecole Polytechnique - CNRS, 91128 Palaiseau (France)

2011-09-15T23:59:59.000Z

83

Improving Particle Confinement in Inertial Electrostatic Fusion for Spacecraft Power and  

E-Print Network (OSTI)

.................................... 10 Figure 2: IEC "Fusor" built by high-school student Brian McDermott (photo credit: Brian Mc as being conceived of by Philo T. Farnsworth, the inventor of television [20]. In IEC devices, fusion ions the idea of having a fusion reactor in their garage. Figure 2: IEC "Fusor" built by high-school student

84

Inertial confinement fusion with direct electric generation by magnetic flux comparession  

DOE Green Energy (OSTI)

A high-power-density laser-fusion-reactor concept in investigated in which directed kinetic enery imparted to a large mass of liquid lithium--in which the fusion target is centrally located--is maximized. In turn, this kinetic energy is converted directly to electricity with, potentially, very high efficiency by work done against a pulsed magnetic field applied exterior to the lithium. Because the concept maximizes the blanket thickness per unit volume of lithium, neutron-induced radioactivities in the reaction chamber wall can be many orders of magnitude less than is typical of D-T fusion reactor concepts.

Lasche, G.P.

1983-01-01T23:59:59.000Z

85

A 1. 5--4 Kelvin detachable cold-sample transfer system: Application to inertially confined fusion with spin-polarized hydrogens fuels  

DOE Green Energy (OSTI)

A compact cold-transfer apparatus for engaging and retrieving samples at liquid helium temperatures (1.5--4K), maintaining the samples at such temperatures for periods of hours, and subsequently inserting them in diverse apparatuses followed by disengagement, is described. The properties of several thermal radiation-insulating shrouds, necessary for very low sample temperatures, are presented. The immediate intended application is transportable target-shells containing highly spin-polarized deuterons in solid HD or D{sub 2} for inertially confined fusion (ICF) experiments. The system is also valuable for unpolarized high-density fusion fuels, as well as for other applications which are discussed. 9 refs., 6 figs.

Alexander, N.; Barden, J.; Fan, Q.; Honig, A.

1990-01-01T23:59:59.000Z

86

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

87

Status of inertial fusion  

SciTech Connect

The technology advancement to high-power beams has also given birth to new technologies. That class of Free Electron Lasers that employs rf linacs, synchrotrons, and storage rings - although the use the tools of High Energy Physics (HEP) - was developed well behind the kinetic energy frontier. The induction linac, however, is something of an exception; it was born directly from the needs of the magnetic fusion program, and was not motivated by a high-energy physics application. The heavy-ion approach to inertial fusion starts with picking from the rich menu of accelerator technologies those that have, ab initio, the essential ingredients needed for a power plant driver: multigap acceleration - which leads to reliability/lifetime; electrical efficiency; repetition rate; and beams that can be reliably focused over a suitably long distance. The report describes the programs underway in Heavy Ion Fusion Accelerator Research as well as listing expected advances in driver, target, and beam quality areas in the inertial fusion power program.

Keefe, D.

1987-04-01T23:59:59.000Z

88

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

SciTech Connect

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

89

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

90

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

Science Conference Proceedings (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

91

Neutron Transport and Nuclear Burnup Analysis for the Laser Inertial Confinement Fusion-Fission Energy (LIFE) Engine  

Science Conference Proceedings (OSTI)

Laser Fusion-Fission Hybrid / Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2)

Kevin J. Kramer; Jeffery F. Latkowski; Ryan P. Abbott; John K. Boyd; Jeffrey J. Powers; Jeffrey E. Seifried

92

Saturation of the Two-Plasmon Decay Instability in Long-Scale-Length Plasmas Relevant to Direct-Drive Inertial Confinement Fusion  

SciTech Connect

Measurements of the hot-electron generation by the two-plasmon-decay instability are made in plasmas relevant to direct-drive inertial confinement fusion. Density-scale lengths of 400 {micro}m at n{sub cr}/4 in planar CH targets allowed the two-plasmon-decay instability to be driven to saturation for vacuum intensities above ~3.5 x 10{sup 14} W cm{sup -2}. In the saturated regime, ~1% of the laser energy is converted to hot electrons. The hot-electron temperature is measured to increase rapidly from 25 to 90 keV as the laser beam intensity is increased from 2 to 7 x 10{sup 14} W cm{sup -2}. This increase in the hot-electron temperature is compared with predictions from nonlinear Zakharov models.

Yaakobi, B; Hu, S X; Chang, P -Y; Craxton, R S; Edgell, D H; Follett, R; Michel, D T; Myatt, J F; Seka, W; Short, R W; Solodov, A A

2012-04-20T23:59:59.000Z

93

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

SciTech Connect

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

94

Accelerators for heavy ion inertial fusion: Progress and plans  

SciTech Connect

The Heavy Ion Inertial Fusion Program is the principal part of the Inertial Fusion Energy Program in the Office of Fusion Energy of the U.S. Department of Energy. The emphasis of the Heavy Ion Program is the development of accelerators for fusion power production. Target physics research and some elements of fusion chamber development are supported in the much larger Inertial Confinement Fusion Program, a dual purpose (defense and energy) program in the Defense Programs part of the Department of Energy. The accelerator research program will establish feasibility through a sequence of scaled experiments that will demonstrate key physics and engineering issues at low cost compared to other fusion programs. This paper discusses progress in the accelerator program and outlines how the planned research will address the key economic issues of inertial fusion energy.

Bangerter, R.O.; Friedman, A.; Herrmannsfeldt, W.B.

1994-08-01T23:59:59.000Z

95

Economic potential of inertial fusion  

SciTech Connect

Beyond the achievement of scientific feasibility, the key question for fusion energy is: does it have the economic potential to be significantly cheaper than fission and coal energy. If fusion has this high economic potential then there are compelling commercial and geopolitical incentives to accelerate the pace of the fusion program in the near term, and to install a global fusion energy system in the long term. Without this high economic potential, fusion's success depends on the failure of all alternatives, and there is no real incentive to accelerate the program. If my conjectures on the economic potential of inertial fusion are approximately correct, then inertial fusion energy's ultimate costs may be only half to two-thirds those of advanced fission and coal energy systems. Relative cost escalation is not assumed and could increase this advantage. Both magnetic and inertial approaches to fusion potentially have a two-fold economic advantage which derives from two fundamental properties: negligible fuel costs and high quality energy which makes possible more efficient generation of electricity. The wining approach to fusion may excel in three areas: electrical generating efficiency, minimum material costs, and adaptability to manufacture in automated factories. The winning approach must also rate highly in environmental potential, safety, availability factor, lifetime, small 0 and M costs, and no possibility of utility-disabling accidents.

Nuckolls, J.H.

1984-04-01T23:59:59.000Z

96

Longitudinal Tracking of Direct Drive Inertial Fusion Targets  

Science Conference Proceedings (OSTI)

Technical Paper / The Technology of Fusion Energy - Inertial Fusion Technology: Targets and Chambers

J. D. Spalding; L. C. Carlson; M. S. Tillack; N. B. Alexander; D. T. Goodin; R. W. Petzoldt

97

Heavy-ion accelerator research for inertial fusion  

SciTech Connect

Thermonuclear fusion offers a most attractive long-term solution to the problem of future energy supplies: The fuel is virtually inexhaustible and the fusion reaction is notably free of long-lived radioactive by-products. Also, because the fuel is in the form of a plasma, there is no solid fuel core that could melt down. The DOE supports two major fusion research programs to exploit these virtues, one based on magnetic confinement and a second on inertial confinement. One part of the program aimed at inertial fusion is known as Heavy Ion Fusion Accelerator Research, or HIFAR. In this booklet, the aim is to place this effort in the context of fusion research generally, to review the brief history of heavy-ion fusion, and to describe the current status of the HIFAR program.

1987-08-01T23:59:59.000Z

98

Future of Inertial Fusion Energy  

Science Conference Proceedings (OSTI)

In the past 50 years, fusion R&D programs have made enormous technical progress. Projected billion-dollar scale research facilities are designed to approach net energy production. In this century, scientific and engineering progress must continue until the economics of fusion power plants improves sufficiently to win large scale private funding in competition with fission and non-nuclear energy systems. This economic advantage must be sustained: trillion dollar investments will be required to build enough fusion power plants to generate ten percent of the world's energy. For Inertial Fusion Energy, multi-billion dollar driver costs must be reduced by up to an order of magnitude, to a small fraction of the total cost of the power plant. Major cost reductions could be achieved via substantial improvements in target performance-both higher gain and reduced ignition energy. Large target performance improvements may be feasible through a combination of design innovations, e.g., ''fast ignition,'' propagation down density gradients, and compression of fusion fuel with a combination of driver and chemical energy. The assumptions that limit projected performance of fusion targets should be carefully examined. The National Ignition Facility will enable development and testing of revolutionary targets designed to make possible economically competitive fusion power plants.

Nuckolls, J H; Wood, L L

2002-09-04T23:59:59.000Z

99

The high current transport experiment for heavy ion inertial fusion  

E-Print Network (OSTI)

on Heavy Ion Inertial Fusion, Princeton, 1996, edited by J.Conference on Inertial Fusion Sciences and Applications (FOR HEAVY ION INERTIAL FUSION 1 L. R. Prost, D. Baca, F. M.

2004-01-01T23:59:59.000Z

100

Search for fusion power  

SciTech Connect

A brief review of the basics of fusion power is given. Both inertial confinement and magnetic confinement fusion are discussed.

Post, R.F.

1978-10-12T23:59:59.000Z

Note: This page contains sample records for the topic "inertial confinement fusion" 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

Laser Inertial Fusion Energy Control Systems  

Science Conference Proceedings (OSTI)

A Laser Inertial Fusion Energy (LIFE) facility point design is being developed at LLNL to support an Inertial Confinement Fusion (ICF) based energy concept. This will build upon the technical foundation of the National Ignition Facility (NIF), the world's largest and most energetic laser system. NIF is designed to compress fusion targets to conditions required for thermonuclear burn. The LIFE control systems will have an architecture partitioned by sub-systems and distributed among over 1000's of front-end processors, embedded controllers and supervisory servers. LIFE's automated control subsystems will require interoperation between different languages and target architectures. Much of the control system will be embedded into the subsystem with well defined interface and performance requirements to the supervisory control layer. An automation framework will be used to orchestrate and automate start-up and shut-down as well as steady state operation. The LIFE control system will be a high parallel segmented architecture. For example, the laser system consists of 384 identical laser beamlines in a 'box'. The control system will mirror this architectural replication for each beamline with straightforward high-level interface for control and status monitoring. Key technical challenges will be discussed such as the injected target tracking and laser pointing feedback. This talk discusses the the plan for controls and information systems to support LIFE.

Marshall, C; Carey, R; Demaret, R; Edwards, O; Lagin, L; Van Arsdall, P

2011-03-18T23:59:59.000Z

102

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

Paris-Sud XI, Université de

103

Inertial fusion: an energy-production option for the future  

SciTech Connect

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

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

1982-05-01T23:59:59.000Z

104

Homodyne target tracking for direct drive laser inertial fusion  

E-Print Network (OSTI)

National Laboratory. Inertial Fusion Energy: How IFE Works,Tracking of Direct Drive Inertial Fusion Targets."Fusion Science and Technology 52.3 (2007): 435-439. Tillack,

Spalding, Jon David

2009-01-01T23:59:59.000Z

105

INERTIAL FUSION DRIVEN BY INTENSE HEAVY-ION BEAMS  

E-Print Network (OSTI)

HIFAN 1830 INERTIAL FUSION DRIVEN BY INTENSE HEAVY-ION BEAMSAC02-05CH11231. INERTIAL FUSION DRIVEN BY INTENSE HEAVY-ION467 (1992). [38] R. W. Moir, Fusion Tech. 25, 5 (1994) [39

Sharp, W. M.

2011-01-01T23:59:59.000Z

106

Inertial fusion: strategy and economic potential  

SciTech Connect

Inertial fusion must demonstrate that the high target gains required for practical fusion energy can be achieved with driver energies not larger than a few megajoules. Before a multi-megajoule scale driver is constructed, inertial fusion must provide convincing experimental evidence that the required high target gains are feasible. This will be the principal objective of the NOVA laser experiments. Implosions will be conducted with scaled targets which are nearly hydrodynamically equivalent to the high gain target implosions. Experiments which demonstrate high target gains will be conducted in the early nineties when multi-megajoule drivers become available. Efficient drivers will also be demonstrated by this time period. Magnetic fusion may demonstrate high Q at about the same time as inertial fusion demonstrates high gain. Beyond demonstration of high performance fusion, economic considerations will predominate. Fusion energy will achieve full commercial success when it becomes cheaper than fission and coal. Analysis of the ultimate economic potential of inertial fusion suggests its costs may be reduced to half those of fission and coal. Relative cost escalation would increase this advantage. Fusions potential economic advantage derives from two fundamental properties: negligible fuel costs and high quality energy (which makes possible more efficient generation of electricity).

Nuckolls, J.H.

1983-01-01T23:59:59.000Z

107

Inertial Fusion Energy Studies on an Earth Simulator-Class Computer  

SciTech Connect

The U.S. is developing fusion energy based on inertial confinement of the burning fusion fuel, as a complement to the magnetic confinement approach. DOE's Inertial Fusion Energy (IFE) program within the Office of Fusion Energy Sciences (OFES) is coordinated with, and gains leverage from, the much larger Inertial Confinement Fusion program of the National Nuclear Security Administration (NNSA). Advanced plasma and particle beam simulations play a major role in the IFE effort, and the program is well poised to benefit from an Earth Simulator-class resource. Progress in all key physics areas of IFE, including heavy-ion ''drivers'' which impart the energy to the fusion fuel, the targets for both ion- and laser-driven approaches, and an advanced concept known as fast ignition, would be dramatically accelerated by an Earth Simulator-class resource.

Friedman, A; Stephens, R

2002-08-13T23:59:59.000Z

108

Target Tracking and Engagement for Inertial Fusion Energy - A Tabletop Demonstration  

Science Conference Proceedings (OSTI)

Technical Paper / The Technology of Fusion Energy - Inertial Fusion Technology: Targets and Chambers

Lane Carlson; Mark Tillack; Thomas Lorentz; Jon Spalding; Neil Alexander; Graham Flint; Dan Goodin; Ronald Petzoldt

109

Homodyne target tracking for direct drive laser inertial fusion  

E-Print Network (OSTI)

direct drive inertial fusion reactor (Sethian). HAPLsblock from the fusion reactor chamber. 4.3 Demonstration A.fusion reaction for generating electricity (see figure 1.1). In order for such a nuclear reactor

Spalding, Jon David

2009-01-01T23:59:59.000Z

110

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

E-Print Network (OSTI)

HYLIFE-II inertial con?nement fusion reactor design. FusionInertial Con?nement Fusion Reactors. PhD thesis, UniversityInertial Con?nement Fusion Reactor. PhD thesis, University

Debonnel, Christophe Sylvain

2006-01-01T23:59:59.000Z

111

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

NLE Websites -- All DOE Office Websites (Extended Search)

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

112

Rugged Packaging for Damage Resistant Inertial Fusion Energy Optics  

Science Conference Proceedings (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

113

Inertial Fusion Program. Progress report, January-December 1980  

Science Conference Proceedings (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

114

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

115

Inertial fusion with ultra-powerful lasers  

SciTech Connect

Ultra-high intensity lasers can be used to ignite ICF capsules with a few tens of kilojoules of light and can lead to high gain with as little as 100 kilojoules of incident laser light. We propose a scheme with three phases. First, a capsule is imploded as in the conventional approach to inertial fusion to assemble a high density fuel configuration. Second, a hole is bored through capsule corona composed of ablated material, pushing critical density close to the high density core of the capsule, by employing the ponderomotive force associated with high intensity laser light. Finally, the fuel is ignited by suprathermal electrons, produced in the high intensity laser plasma interactions, which propagate from critical density to this high density core. This paper reviews two models of energy gain in ICF capsules and explains why ultra-high intensity lasers allow access to the model producing the higher gains. This new scheme also drastically reduces the difficulty of the implosion and thereby allows lower quality fabrication and less stringent beam quality and symmetry requirements from the implosion driver. The difficulty of the fusion scheme is transferred to the technological difficulty of producing the ultra-high-intensity laser and of transporting this energy to the fuel.

Tabak, M.; Hammer, J.; Glinsky, M.; Kruer, W.; Wilks, S.; Woodworth, J.; Campbell, E.M.; Perry, M.D.; Mason, R.

1993-10-01T23:59:59.000Z

116

High-brightness, high-spatial-resolution, 6.151 keV x-ray imaging of inertial confinement fusion capsule implosion and complex hydrodynamics experiments on Sandia's Z accelerator (invited)  

SciTech Connect

When used for the production of an x-ray imaging backlighter source on Sandia National Laboratories' 20 MA, 100 ns rise-time Z accelerator [M. K. Matzen et al., Phys. Plasmas 12, 055503 (2005)], the terawatt-class, multikilojoule, 526.57 nm Z-Beamlet laser (ZBL) [P. K. Rambo et al., Appl. Opt. 44, 2421 (2005)], in conjunction with the 6.151 keV, Mn-He{sub {alpha}} curved-crystal imager [D. B. Sinars et al., Rev. Sci. Instrum. 75, 3672 (2004)], is capable of providing a high quality x radiograph per Z shot for various high-energy-density physics experiments. Enhancements to this imaging system during 2005 have led to the capture of inertial confinement fusion capsule implosion and complex hydrodynamics images of significantly higher quality. The three main improvements, all leading effectively to enhanced image plane brightness, were bringing the source inside the Rowland circle to approximately double the collection solid angle, replacing direct exposure film with Fuji BAS-TR2025 image plate (read with a Fuji BAS-5000 scanner), and generating a 0.3-0.6 ns, {approx}200 J prepulse 2 ns before the 1.0 ns, {approx}1 kJ main pulse to more than double the 6.151 keV flux produced compared with a single 1 kJ pulse. It appears that the 20{+-}5 {mu}m imaging resolution is limited by the 25 {mu}m scanning resolution of the BAS-5000 unit, and to this end, a higher resolution scanner will replace it. ZBL is presently undergoing modifications to provide two temporally separated images ('two-frame') per Z shot for this system before the accelerator closes down in summer 2006 for the Z-refurbished (ZR) upgrade. In 2008, after ZR, it is anticipated that the high-energy petawatt (HEPW) addition to ZBL will be completed, possibly allowing high-energy 11.2224 and 15.7751 keV K{alpha}{sub 1} curved-crystal imaging to be performed. With an ongoing several-year project to develop a highly sensitive multiframe ultrafast digital x-ray camera (MUDXC), it is expected that two-frame HEPW 11 and 16 keV imaging and four-frame ZBL 6.151 keV curved-crystal imaging will be possible. MUDXC will be based on the technology of highly cooled silicon and germanium photodiode arrays and ultrafast, radiation-hardened integrated circuitry.

Bennett, G. R.; Sinars, D. B.; Wenger, D. F.; Cuneo, M. E.; Adams, R. G.; Barnard, W. J.; Beutler, D. E.; Burr, R. A.; Campbell, D. V.; Claus, L. D.; Foresi, J. S.; Johnson, D. W.; Keller, K. L.; Lackey, C.; Leifeste, G. T.; McPherson, L. A.; Mulville, T. D.; Neely, K. A.; Rambo, P. K.; Rovang, D. C. [Sandia National Laboratories, P.O. Box 5800, Albuquerque, New Mexico 87185-1106 (United States)] (and others)

2006-10-15T23:59:59.000Z

117

Weapons Activities/ Inertial Confinement Fusion Ignition  

E-Print Network (OSTI)

component of the National Nuclear Security Administration's (NNSA) responsive infrastructure, supports NNSA an important component of the scientific and technical understanding required to assess the safety, security, and reliability of the Nation's nuclear weapons without nuclear testing. The program provides this capability

118

Weapons Activities/ Inertial Confinement Fusion Ignition  

E-Print Network (OSTI)

2012 Congressional Budget Campaign and a major goal for National Nuclear Security Administration (NNSA) and the U.S. Department of Energy (DOE). The ICF Campaign supports the NNSA's Stockpile Stewardship Program. The NIF provides NNSA extraordinary opportunities for scientific progress and discovery in the areas

119

Inertial Fusion Driven by Intense Heavy-Ion Beams  

NLE Websites -- All DOE Office Websites (Extended Search)

INERTIAL FUSION DRIVEN BY INTENSE HEAVY-ION BEAMS INERTIAL FUSION DRIVEN BY INTENSE HEAVY-ION BEAMS * W. M. Sharp # , A. Friedman, D. P. Grote, J. J. Barnard, R. H. Cohen, M. A. Dorf, S. M. Lund, L. J. Perkins, M. R. Terry, LLNL, Livermore, CA, USA B. G. Logan, F. M. Bieniosek, A. Faltens, E. Henestroza, J.-Y. Jung, J. W. Kwan, E. P. Lee, S. M. Lidia, P. A. Ni, L. L. Reginato, P. K. Roy, P. A. Seidl, J. H. Takakuwa, J.-L. Vay, W. L. Waldron, LBNL, Berkeley, CA, USA R. C. Davidson, E. P. Gilson, I. D. Kaganovich, H. Qin, E. Startsev, PPPL, Princeton, NJ, USA I. Haber, R. A. Kishek, University of Maryland, College Park, MD, USA A. E. Koniges, NERSC, Berkeley, CA, USA Abstract Intense heavy-ion beams have long been considered a promising driver option for inertial-fusion energy production. This paper briefly compares inertial

120

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

Science Conference Proceedings (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

Note: This page contains sample records for the topic "inertial confinement fusion" 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

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

SciTech Connect

Issues with coupling efficiency, beam illumination symmetry, and Rayleigh-Taylor instability are discussed for spherical heavy-ion-beam-driven targets with and without hohlraums. Efficient coupling of heavy-ion beams to compress direct-drive inertial fusion targets without hohlraums is found to require ion range increasing several-fold during the drive pulse. One-dimensional implosion calculations using the LASNEX inertial confinement fusion target physics code shows the ion range increasing fourfold during the drive pulse to keep ion energy deposition following closely behind the imploding ablation front, resulting in high coupling efficiencies (shell kinetic energy/incident beam energy of 16% to 18%). Ways to increase beam ion range while mitigating Rayleigh-Taylor instabilities are discussed for future work.

Logan, B.G.; Perkins, L.J.; Barnard, J.J.

2008-05-16T23:59:59.000Z

122

Knudsen Layer Reduction of Fusion Reactivity Kim Molvig and Nelson...  

NLE Websites -- All DOE Office Websites (Extended Search)

fusion cross section determine Gamow peak in the fusion reactivity. 2 Inertially confined fusion systems typically have plasma fuel enveloped by a cold non-reacting region or...

123

Praise and suggestions for fusion research from a utility industry...  

NLE Websites -- All DOE Office Websites (Extended Search)

Select and View High Resolution Images to Download Learn More Engineering Fusion energy Fusion reactor design Inertial confinement fusion Nuclear energy Plasma physics Tokamaks...

124

Ch. 37, Inertial Fusion Energy Technology  

DOE Green Energy (OSTI)

Nuclear fission, nuclear fusion, and renewable energy (including biofuels) are the only energy sources capable of satisfying the Earth's need for power for the next century and beyond without the negative environmental impacts of fossil fuels. Substantially increasing the use of nuclear fission and renewable energy now could help reduce dependency on fossil fuels, but nuclear fusion has the potential of becoming the ultimate base-load energy source. Fusion is an attractive fuel source because it is virtually inexhaustible, widely available, and lacks proliferation concerns. It also has a greatly reduced waste impact, and no danger of runaway reactions or meltdowns. The substantial environmental, commercial, and security benefits of fusion continue to motivate the research needed to make fusion power a reality. Replicating the fusion reactions that power the sun and stars to meet Earth's energy needs has been a long-sought scientific and engineering challenge. In fact, this technological challenge is arguably the most difficult ever undertaken. Even after roughly 60 years of worldwide research, much more remains to be learned. the magnitude of the task has caused some to declare that fusion is 20 years away, and always will be. This glib criticism ignores the enormous progress that has occurred during those decades, progress inboth scientific understanding and essential technologies that has enabled experiments producing significant amounts of fusion energy. For example, more than 15 megawatts of fusion power was produced in a pulse of about half a second. Practical fusion power plants will need to produce higher powers averaged over much longer periods of time. In addition, the most efficient experiments to date have required using about 50% more energy than the resulting fusion reaction generated. That is, there was no net energy gain, which is essential if fusion energy is to be a viable source of electricity. The simplest fusion fuels, the heavy isotopes of hydrogen (deuterium and tritium), are derived from water and the metal lithium, a relatively abundant resource. The fuels are virtually inexhaustible and they are available worldwide. Deuterium from one gallon of seawater would provide the equivalent energy of 300 gallons of gasoline, or over a half ton of coal. This energy is released when deuterium and tritium nuclei are fused together to form a helium nucleus and a neutron. The neutron is used to breed tritium from lithium. The energy released is carried by the helium nucleus (3.5 MeV) and the neutron (14 MeV). The energetic helium nucleus heats the fuel, helping to sustain the fusion reaction. Once the helium cools, it is collected and becomes a useful byproduct. A fusion power plant would produce no climate-changing gases.

Moses, E

2010-06-09T23:59:59.000Z

125

Secret high-temperature reactor concept for inertial fusion  

DOE Green Energy (OSTI)

The goal of our SCEPTRE project was to create an advanced second-generation inertial fusion reactor that offers the potential for either of the following: (1) generating electricity at 50% efficiency, (2) providing high temperature heat (850/sup 0/C) for hydrogen production, or (3) producing fissile fuel for light-water reactors. We have found that these applications are conceptually feasible with a reactor that is intrinsically free of the hazards of catastrophic fire or tritium release.

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

1983-01-01T23:59:59.000Z

126

Neutronics issues and inertial fusion energy: a summary of findings  

Science Conference Proceedings (OSTI)

We have analyzed and compared five major inertial fusion energy (IFE) and two representative magnetic fusion energy (MFE) power plant designs for their environment, safety, and health (ES&H) characteristics. Our work has focussed upon the neutronics of each of the designs and the resulting radiological hazard indices. The calculation of a consistent set of hazard indices allows comparisons to be made between the designs. Such comparisons enable identification of trends in fusion ES&H characteristics and may be used to increase the likelihood of fusion achieving its full potential with respect to ES&H characteristics. The present work summarizes our findings and conclusions. This work emphasizes the need for more research in low-activation materials and for the experimental measurement of radionuclide release fractions under accident conditions.

Latkowski, J. F., LLNL

1998-05-29T23:59:59.000Z

127

Semiconductor Laser Diode Pumps for Inertial Fusion Energy Lasers  

Science Conference Proceedings (OSTI)

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

Deri, R J

2011-01-03T23:59:59.000Z

128

Shock Attenuation in Two-Phase (Gas-Liquid) Jets for Inertial Fusion Applications.  

E-Print Network (OSTI)

??Z-Pinch IFE (Inertial Fusion Energy) reactor designs will likely utilize high yield targets (~ 3 GJ) at low repetition rates (~ 0.1 Hz). Appropriately arranged (more)

Lascar, Celine Claire

2007-01-01T23:59:59.000Z

129

Impact of beam transport method on chamber and driver design for heavy ion inertial fusion energy  

E-Print Network (OSTI)

et al. , HYLIFE-II: a molten-salt inertial fusion energyjetted and free-?owing molten salts such as ?ibe (see, for

Rose, D.V.; Welch, D.R.; Olson, C.L.; Yu, S.S.; Neff, S.; Sharp, W.M.

2002-01-01T23:59:59.000Z

130

Inertial fusion target development for ignition and energy  

SciTech Connect

The target needs of the next ICF experiments that will lead toward ignition and energy are different from those of today`s experiments. The future experiments on OMEGA Upgrade, GEKKO XII Upgrade, the National Ignition Facility and Megajoule will need large, precise, cryogenic targets. Development is needed on a number of aspects of these targets, including shell fabrication, characterization, cryogenic layering and target handling. However, coordinated R and D programs are in place and work is in process to carry out the needed development. It is vital to the success of inertial fusion that this work be sustained. Coordinated effort, like the National Cryogenic Target Program in the USA, will help make the development activities as efficient and effective as possible, and should be encouraged.

Schultz, K.R. [General Atomics, San Diego, CA (United States); Norimatsu, T. [Osaka Univ. (Japan). Inst. of Laser Engineering

1994-12-01T23:59:59.000Z

131

Fusion Engineering and Design 42 (1998) 537548 Chamber technology concepts for inertial fusion energy--three  

E-Print Network (OSTI)

to 650°C and has a low enough vapor pressure. Li and Li17Pb83 would also work but must be 1.5 m thick and increased pumping power features required by use of Li or Li17Pb83 suggest Flibe might be the lowest cost to a large variety of chamber design concepts for inertial fusion energy (IFE). Refs. [1­8] provide

Abdou, Mohamed

132

Inertial and inductive energy storage for fusion systems  

DOE Green Energy (OSTI)

Energy storage is necessary for all proposed fusion reactor systems. The plasma physics for confinement and primarily the energy transfer time determine the nature of the storage system. Discharge times vary from 0.7 ms for theta-pinch reactors to one to two seconds for tokamak reactors. Three classes of devices are available for energy storage--inductors, capacitors, and rotating machines. The transfer of the energy from the store imposes unusual switching requirements. The broad requirements for reactor energy stores and more specifically those for tokamak experimental power reactors (EPR) and for the Scyllac fusion test reactor (SFTR) will be presented. Assessments and comparisons of alternative energy storage and transfer systems for these devices are to be discussed. The state of the pulsed superconducting inductive energy storage coils and homopolar development programs will be emphasized. Plans for tokamak ohmic-heating systems will be discussed briefly.

Rogers, J.D.

1976-01-01T23:59:59.000Z

133

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

E-Print Network (OSTI)

Williams. HYLIFE-II: A molten-salt inertial fusion energyelectricity. The binary molten salt ?ibe (LiF-BeF 2 ) andtarget and ablated molten salt. Her approach was essentially

Debonnel, Christophe Sylvain

2006-01-01T23:59:59.000Z

134

Magnetic and inertial CTR: present status and outlook  

SciTech Connect

Some of the successes of controlled fusion research in both inertial confinement and magnetic confinement are described. The possibilities of scaled- up experiments are also discussed with respect to cost and economics. (MOW)

Wood, L.

1975-01-20T23:59:59.000Z

135

Magnetic Confinement Fusion at the Crossroads  

E-Print Network (OSTI)

Atoll: 15MT yield References - "Dark Sun" by Richard Rhodes, 1995 "History of Soviet Fusion", V = 12m ­ Pfusion = 880 MW Ref: V.D. Shafranov, "History of Soviet Fusion" Physics-Uspekhi 4 835, culminating in TFTR (US), JET (EU), JT-60 (Japan) #12;MGB / UT / 070307 19 1973 Oil Embargo - Energy R

Princeton Plasma Physics Laboratory

136

Z-Pinch Driven Isentropic Compression for Inertial Fusion  

Science Conference Proceedings (OSTI)

The achievement of high gain with inertial fusion requires the compression of hydrogen isotopes to high density and temperatures. High densities can be achieved most efficiently by isentropic compression. This requires relatively slow pressure pulses on the order of 10-20 nanoseconds; however, the pressure profile must have the appropriate time. We present 1-D numerical simulations that indicate such a pressure profile can be generated by using pulsed power driven z pinches. Although high compression is calculated, the initial temperature is too low for ignition. Ignition could be achieved by heating a small portion of this compressed fuel with a short (-10 ps) high power laser pulse as previously described. Our 1-D calculations indicate that the existing Z-accelerator could provide the driving current (-20 MA) necessary to compress fuel to roughly 1500 times solid density. At this density the required laser energy is approximately 10 kJ. Multidimensional effects such as the Rayleigh-Taylor were not addressed in this brief numerical study. These effects will undoubtedly lower fuel compression for a given chive current. Therefore it is necessary to perform z-pinch driven compression experiments. Finally, we present preliminary experimental data from the Z-accelerator indicating that current can be efficiently delivered to appropriately small loads (- 5 mm radius) and that VISAR can be used measure high pressure during isentropic compression.

Asay, J.R.; Hall, C.A.; Holland, K.G.; Slutz, S.A.; Spielman, R.B.; Stygar, W.A.

1999-02-01T23:59:59.000Z

137

Concepts for fabrication of inertial fusion energy targets  

SciTech Connect

Future inertial fusion energy (IFE) power plants will have a Target Fabrication Facility (TFF) that must produce approximately 500,000 targets per day. To achieve a relatively low cost of electricity, the cost to produce these targets will need to be less than approximately $0.25 per target. In this paper the status on the development of concepts for a TFF to produce targets for a heavy ion fusion (HIF) reactor, such as HYLIFE II, and a laser direct drive fusion reactor such as Sombrero, is discussed. The baseline target that is produced in the HIF TFF is similar to the close-coupled indirect drive target designed by Callahan-Miller and Tabak at Lawrence Livermore Laboratory. This target consists of a cryogenic hohlraum that is made of a metal case and a variety of metal foams and metal-doped organic foams. The target contains a DT-filled CH capsule. The baseline direct drive target is the design developed by Bodner and coworkers at Naval Research Laboratory. HIF targets can be filled with DT before or after assembly of the capsule into the hohlraum. Assembly of targets before filling allows assembly operations to be done at room temperature, but tritium inventories are much larger due to the large volume that the hohlraum occupies in the fill system. Assembly of targets cold after filling allows substantial reduction in tritium inventory, but this requires assembly of targets at cryogenic temperature. A model being developed to evaluate the tritium inventories associated with each of the assembly and fill options indicates that filling targets before assembling the capsule into the hohlraum, filling at temperatures as high as possible, and reducing dead-volumes in the fill system as much as possible offers the potential to reduce tritium inventories to acceptable levels. Use of enhanced DT ice layering techniques, such as infrared layering can reduce tritium inventories significantly by reducing the layering time and therefore the number of capsules being layered. Current processes for fabrication of ICF capsules can most likely be easily scaled up to produce capsules at rates needed for an IFE plant.

Nobile, A. (Arthur), Jr.; Hoffer, J. K. (James K.); Gobby, P. L. (Peter L.); Steckle, W. P. (Warren P.), Jr.; Goodin, D. T. (Daniel T.); Besenbruch, G. E. (Gottfried E.); Schultz, K. R. (Kenneth R.)

2001-01-01T23:59:59.000Z

138

Demonstrating a Target Supply for Inertial Fusion Energy (A24816)  

E-Print Network (OSTI)

Fusion Science And Technology 47, 1131 (2005)16th Topical Meeting on Technology Fusion Energy Madison Wisconsin, US, 2004999609940

Goodin, D.T.

2004-11-05T23:59:59.000Z

139

Double-shell inertial confinement fusion target fabrication  

SciTech Connect

First generation hemishells, from which spherical shells are constructed, were fabricated by micromachining coated mandrels and by molding. The remachining of coated mandrels are described in detail. Techniques were developed for coating the microsized mandrels with polymeric and metallic materials by methods including conformal coating, vapor deposition, plasma polymerization and thermoforming. Micropositioning equipment and bonding techniques have also been developed to assemble the hemishells about a fuel pellet maintaining a spherical concentricity of better than 2 ..mu..m and voids in the hemishell bonding line of a few hundred angstroms or less.

Hatcher, C.W.; Lorensen, L.E.; Weinstein, B.W.

1980-08-26T23:59:59.000Z

140

ION ACCELERATORS AS DRIVERS FOR INERTIAL CONFINEMENT FUSION  

E-Print Network (OSTI)

S. Humphries, Jr. , Sandia Laboratories Report SANO 80-0402effort in this area is at Sandia Laboratories in Albuquerquebeing developed at Sandia Laboratories, Alburquerque,'

Faltens, A.

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "inertial confinement fusion" 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.


141

Inertial Confinement Fusion Ignition and High Yield Campaign  

E-Print Network (OSTI)

November 21, 2003 #12;2 Statements to FESAC IFE panel 10/28/03 · Ignition is a major goal for NNSA supports OFES's mission and OFES use of NNSA's ICF facilities is accepted · Defense Programs reserves right: Provide mission need report for the proposed OMEGA Extended Performance project. · October 2002: NNSA

142

Progress in Direct-Drive Inertial Confinement Fusion Research  

E-Print Network (OSTI)

Temperature Radius Massdensity Hot spot Burn wave Ablator DT ice #12;A-beam smoothing is critical to ICF ignition I1771 EO phase modulator Grating Amplifiers Grating Focusing optics Angular dispersion f Oscillator Phase Plates1 Measured far field of an OMEGA indirect-drive phase plate

143

Office of Inertial Confinement Fusion | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

required to support the nuclear weapon stockpile. ICF's experimental capabilities are an essential component of the overall NNSA plan to manage the assessment of nuclear...

144

INERTIAL FUSION DRIVEN BY INTENSE HEAVY-ION BEAMS  

E-Print Network (OSTI)

Tritium can be bred in a fusion reactor by capturing fusionchamber. Whereas magnetic-fusion reactors typically combineProjected MFE reactors have a toroidal fusion-power core

Sharp, W. M.

2011-01-01T23:59:59.000Z

145

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

146

(MSIB) Examination of Inertial Fusion Energy Candidate Materials  

Science Conference Proceedings (OSTI)

There is no source of fusion neutrons of adequate intensity currently available. Instead ... Evolution in High Purity Reference V-4Cr-4Ti Alloy for Fusion Reactor.

147

Exploring Plasma Science Advances from Fusion Findings to Astrophysica...  

NLE Websites -- All DOE Office Websites (Extended Search)

was shown for inertial confinement fusion experiments at the National Ignition Facility (NIF) at the DOE's Lawrence Livermore National Laboratory. Speakers noted that producing...

148

Final report of the Ad Hoc Experts Group on Fusion  

SciTech Connect

The objectives and strategy of the fusion program are reviewed. In particular, tokamaks, mirrors, alternate concepts, plasma physics, and inertial confinement options are reviewed. (MOW)

1978-06-01T23:59:59.000Z

149

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

SciTech Connect

The Laser Inertial Fusion Energy (LIFE) concept is being designed to operate as either a pure fusion or hybrid fusion-fission system. A key component of a LIFE engine is the fusion chamber subsystem. The present work details the chamber design for the pure fusion option. The fusion chamber consists of the first wall and blanket. This integrated system 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 LIFE design that meets all of these requirements is described herein.

Latkowski, J F; Kramer, K J; Abbott, R P; Morris, K R; DeMuth, J; Divol, L; El-Dasher, B; Lafuente, A; Loosmore, G; Reyes, S; Moses, G A; Fratoni, M; Flowers, D; Aceves, S; Rhodes, M; Kane, J; Scott, H; Kramer, R; Pantano, C; Scullard, C; Sawicki, R; Wilks, S; Mehl, M

2010-12-07T23:59:59.000Z

150

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

Science Conference Proceedings (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

151

Compact, Efficient Laser Systems Required for Laser Inertial Fusion Energy  

Science Conference Proceedings (OSTI)

IFE - NIF & LIFE / Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1)

A. Bayramian et al.

152

Timely Delivery of Laser Inertial Fusion Energy (LIFE)  

Science Conference Proceedings (OSTI)

IFE - NIF & LIFE / Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1)

M. Dunne et al.

153

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

Science Conference Proceedings (OSTI)

IFE - NIF & LIFE / Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1)

Jeffery F. Latkowski et al.

154

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

155

Summary talk to 21st IAEA FEC, Chendu, 2006 Inertial fusion advance  

E-Print Network (OSTI)

DT) will be demonstrated by using National Ignition Facility (NIF) in USA and Mega Joule Laser (LMJ is expected in the indirect-driver implosion on the NIF with the conventional scheme based on a central hot for inertial fusion Except for laser drivers such as NIF and LMJ etc., the Z- pinch drivers and the heavy ion

156

Measurements of neutron flux from an inertial-electrostatic confinement device  

SciTech Connect

A neutron-detection system was built for the purpose of measuring the neutron flux from an Inertial-Electrostatic Confinement Device located at Brigham Young University. A BF$sub 3$ proportional counter was used for absolute flux measurements and a pair of scintillation detectors was used to compare neutron output under different operating conditions. The detectors were designed to be compatible with the operating conditions of the device and to be able to measure small changes in neutron output. The detectors were calibrated using a Pu-Be source with corrections made for laboratory conditions. Performance of the counting system was checked and data were collected on the neutron flux from the device. (auth)

Westenskow, G.A.

1975-08-01T23:59:59.000Z

157

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

NLE Websites -- All DOE Office Websites (Extended Search)

content emergency.pppl.gov Join Our Mailing List A Collaborative National Center for Fusion & Plasma Research Search form Search Search Home About Overview Learn More Visiting...

158

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

SciTech Connect

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

159

Performance requirements of an inertial-fusion-energy source for hydrogen production  

DOE Green Energy (OSTI)

Performance of an inertial fusion system for the production of hydrogen is compared to a tandem-mirror-system hydrogen producer. Both systems use the General Atomic sulfur-iodine hydrogen-production cycle and produce no net electric power to the grid. An ICF-driven hydrogen producer will have higher system gains and lower electrical-consumption ratios than the design point for the tandem-mirror system if the inertial-fusion-energy gain eta Q > 8.8. For the ICF system to have a higher hydrogen production rate per unit fusion power than the tandem-mirror system requires that eta Q > 17. These can be achieved utilizing realistic laser and pellet performances.

Hovingh, J.

1983-01-01T23:59:59.000Z

160

Real-time Fusion Power Monitor via Neutron Activation of Circulating Fluid.  

E-Print Network (OSTI)

??Much effort has been devoted to the concept of fusion reactors, both magnetic and inertial confinement, in pursuit of an alternative source of energy. The (more)

Clark, Brandon

2007-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "inertial confinement fusion" 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

Open-ended magnetic confinement systems for fusion  

Science Conference Proceedings (OSTI)

Magnetic confinement systems that use externally generated magnetic fields can be divided topologically into two classes: ``closed`` and `open``. The tokamak, the stellarator, and the reversed-field-pinch approaches are representatives of the first category, while mirror-based systems and their variants are of the second category. While the recent thrust of magnetic fusion research, with its emphasis on the tokamak, has been concentrated on closed geometry, there are significant reasons for the continued pursuit of research into open-ended systems. The paper discusses these reasons, reviews the history and the present status of open-ended systems, and suggests some future directions for the research.

Post, R.F.; Ryutov, D.D.

1995-05-01T23:59:59.000Z

162

Timely Delivery of Laser Inertial Fusion Energy Presentation prepared for  

E-Print Network (OSTI)

acceptability Timely delivery NIF-1210-20673s2.ppt · Pinnacle West Capital Corp · PG&E Corporation · Mid Generation · Exelon Generation Company · Southern California Edison Electric Power Utility needs NIF-0611 on direct evidence of fusion performance (NIF). · Use of available technology and materials that can

163

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

DOE Green Energy (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

164

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

165

Inertial fusion program, January 1-June 30, 1979  

SciTech Connect

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

166

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

SciTech Connect

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

167

Mercury and Beyond: Diode-Pumped Solid-State Lasers for Inertial Fusion Energy  

SciTech Connect

We have begun building the ''Mercury'' laser system as the first in a series of new generation diode-pumped solid-state lasers for inertial fusion research. Mercury will integrate three key technologies: diodes, crystals, and gas cooling, within a unique laser architecture that is scalable to kilojoule energy levels for fusion energy applications. The primary performance goals include 10% electrical efficiencies at 10 Hz and 100 J with a 2-10 ns pulse length at 1.047 pm wavelength. When completed, Mercury will allow rep-rated target experiments with multiple target chambers for high energy density physics research.

Bibeau, C.; Beach, R.J.; Bayramian, A.; Chanteloup, J.C.; Ebbers, C.A.; Emanuel, M.A.; Orth, C.D.; Rothenberg, J.E.; Schaffers, K.I.; Skidmore, J.A.; Sutton, S.B.; Zapata, L.E.; Payne, S.A.; Powell, H.T.

1999-10-19T23:59:59.000Z

168

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

Science Conference Proceedings (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

169

Laser fusion overview. [Forecasting of laser fusion feasibility  

SciTech Connect

Because of recent breakthroughs in the target area, and in the glass laser area, the scientific feasibility of laser fusion--and of inertial fusion--may be demonstrated in the early 1980's. Then the development in that time period of a suitable laser (or storage ring or other driving source) would make possible an operational inertial fusion reactor in this century. These are roughly the same time scales as projected by the Tokamak magnetic confinement approach. It thus appears that the 15-20 year earlier start by magnetic confinement fusion may be overcome. Because inertial confinement has been demonstrated, and inertial fusion reactors may operate on smaller scales than Tokamaks, laser fusion may have important technical and economic advantages.

Nuckolls, J.

1976-05-17T23:59:59.000Z

170

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

SciTech Connect

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

171

Microwave measurements of electron density in a spherical inertial- electrostatic confinement system using six ion guns  

SciTech Connect

The electron density in a spherical inertial-electrostatic confinement device using six ion beams was studied with microwave techniques involving the fundamental and higher order cavity resonances. Thermal expansion problems were circumvented by switched operation of the device. The deuterium background pressure was found to be a dominant factor in determining n/sub e/ throughout the entire range of 0.4 to 10 milliTorr. With 1 m Torr pressure and 10 mA total ion current (at 20 to 40 keV) central electron densities of the order of 10$sup 9$ electrons/ cm$sup 3$ were estimated, with total population of approximately 10$sup 10$ electrons. No evidence of shell structure of the electron density was found, although the use of higher order modes to obtain better spatial resolution was precluded by the low magnitude of n/sub e/. Indirect indication of weak ion trapping was obtained by measurement of the enhancement of neutron flux that resulted when the guns were operated simultaneously. (auth)

Chan, A.I.Y.

1975-08-01T23:59:59.000Z

172

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

Science Conference Proceedings (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

173

Passive Spectroscopic Diagnostics for Magnetically-confined Fusion Plasmas  

SciTech Connect

Spectroscopy of radiation emitted by impurities and hydrogen isotopes plays an important role in the study of magnetically-confined fusion plasmas, both in determining the effects of impurities on plasma behavior and in measurements of plasma parameters such as electron and ion temperatures and densities, particle transport, and particle influx rates. This paper reviews spectroscopic diagnostics of plasma radiation that are excited by collisional processes in the plasma, which are termed 'passive' spectroscopic diagnostics to distinguish them from 'active' spectroscopic diagnostics involving injected particle and laser beams. A brief overview of the ionization balance in hot plasmas and the relevant line and continuum radiation excitation mechanisms is given. Instrumentation in the soft X-ray, vacuum ultraviolet, ultraviolet, visible, and near-infrared regions of the spectrum is described and examples of measurements are given. Paths for further development of these measurements and issues for their implementation in a burning plasma environment are discussed.

B.C. Stratton, M. Bitter, K.W. Hill, D.L. Hillis, and J.T. Hogan

2007-07-18T23:59:59.000Z

174

TIMELY DELIVERY OF LASER INERTIAL FUSION ENERGY (LIFE)  

SciTech Connect

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

175

Magnetic Probe to Study Plasma Jets for Magneto-Inertial Fusion  

SciTech Connect

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

176

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

Science Conference Proceedings (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

177

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

SciTech Connect

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

178

FusEdWeb | Fusion Education  

NLE Websites -- All DOE Office Websites (Extended Search)

Magnetic Confinement Fusion Magnetic Confinement Fusion FusEdWeb: Discover Fusion CPEP's Online Fusion Course Fusion FAQ Fusion and Plasma Glossary Plasma Dictionary Student and Teacher Resources Education and Outreach Ideas Other Fusion and Plasma Sites Great Sites Internet Plasma Physics EXperience GA's Fusion Energy Slide Show International Thermonuclear Experimental Reactor National Ignition Facility Search webby award honoree Webby Awards Honoree April 10, 2007 webby award honoree Links2Go - Fusion, November 9, 1998 FusEdWeb: Fusion Energy Education Our Sun | Other Stars and Galaxies | Inertial Confinement | Magnetic Confinement Fusion by Magnetic Confinement The image above is an artistic rendering of a tokamak, a donut-shaped magnetic vacuum chamber in which wispy vapors of fusion fuel are

179

Scenarios for multi-unit inertial fusion energy plants producing hydrogen fuel  

DOE Green Energy (OSTI)

This work describes: (a) the motivation for considering fusion in general, and Inertial Fusion Energy (IFE) in particular, to produce hydrogen fuel powering low-emission vehicles; (b) the general requirements for any fusion electric plant to produce hydrogen by water electrolysis at costs competitive with present consumer gasoline fuel costs per passenger mile, for advanced car architectures meeting President Clinton`s 80 mpg advanced car goal, and (c) a comparative economic analysis for the potential cost of electricity (CoE) and corresponding cost of hydrogen (CoH) from a variety of multi-unit IFE plants with one to eight target chambers sharing a common driver and target fab facility. Cases with either heavy-ion or diode-pumped, solid-state laser drivers are considered, with ``conventional`` indirect drive target gains versus ``advanced, e.g. Fast Ignitor`` direct drive gain assumptions, and with conventional steam balance-of-plant (BoP) versus advanced MHD plus steam combined cycle BoP, to contrast the potential economics under ``conventional`` and ``advanced`` IFE assumptions, respectively.

Logan, B.G.

1993-12-01T23:59:59.000Z

180

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

SciTech Connect

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

Note: This page contains sample records for the topic "inertial confinement fusion" from the National Library of EnergyBeta (NLEBeta).
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181

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

Science Conference Proceedings (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

182

The restructured fusion program and the role of alternative fusion concepts  

SciTech Connect

This testimony to the subcommittee on Energy and the Environment of the U.S. House of Representatives`s Committee on Science pushes for about 25% of the fusion budget to go to alternative fusion concepts. These concepts are: low density magnetic confinement, inertial confinement fusion, high density magnetic confinement, and non- thermonuclear and miscellaneous programs. Various aspects of each of these concepts are outlined.

Perkins, L.J.

1996-03-05T23:59:59.000Z

183

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

Science Conference Proceedings (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

184

FusEdWeb | Fusion Education  

NLE Websites -- All DOE Office Websites (Extended Search)

Achieving Fusion Conditions Achieving Fusion Conditions CPEP: Online Fusion Course Main Topics Energy Sources and Conversions Two Key Fusion Reactions How Fusion Reactions Work Creating the Conditions for Fusion Plasmas - the 4th State of Matter Achieving Fusion Conditions More Info About CPEP Fusion Chart Images: English + 6 More Languages Main CPEP Web Site Printed Charts in 3 Sizes Search webby award honoree Webby Awards Honoree April 10, 2007 webby award honoree Links2Go - Fusion, November 9, 1998 FusEdWeb: Fusion Energy Education Overview | The Guided Tour Achieving Fusion Conditions EXPERIMENTAL RESULTS IN FUSION RESEARCH Both inertial and magnetic confinement fusion research have focused on understanding plasma confinement and heating. This research has led to increases in plasma temperature, T, density, n, and energy confinement

185

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

Science Conference Proceedings (OSTI)

Laser Fusion-Fission Hybrid / Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2)

R. W. Moir; H. F. Shaw; A. Caro; Larry Kaufman; J. F. Latkowski; J. Powers; P. E. A. Turchi

186

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

E-Print Network (OSTI)

for magnetic fusion reactors and IFMIF. Journal of NuclearFusion reactors blanket nucleonics. In Progress in NuclearFusion-Fission hybrid reactors. In Advances in Nuclear

Kramer, Kevin James

2010-01-01T23:59:59.000Z

187

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

E-Print Network (OSTI)

32] E. Greenspan. Fusion reactors blanket nucleonics. Intemperature windows for fusion reactor structural materials.steels for magnetic fusion reactors and IFMIF. Journal of

Kramer, Kevin James

2010-01-01T23:59:59.000Z

188

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

SciTech Connect

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

189

Cryogenic DT and D2 targets for inertial confinement fusiona... T. C. Sangster,b  

E-Print Network (OSTI)

Facility NIF W. J. Hogan et al., Nucl. Fusion 41, 567 2001 are based on a spherical ablator containing most of the critical fabrication tolerances for ignition on the NIF. At the University of Rochester required for ignition on the NIF. At LLE, these cryogenic DT and D2 capsules are being imploded

190

Low Mass Transmission Lines for Z-Pinch Driven Inertial Fusion  

DOE Green Energy (OSTI)

Recyclable transmission lines (RTL) are studied as a means of repetitively driving z pinches. The lowest reprocessing costs should be obtained by minimizing the mass of the RTL. Low mass transmission lines (LMTL) could also help reduce the cost of a single shot facility such as the proposed X-1 accelerator and make z-pinch driven space propulsion feasible. We present calculations to determine the minimum LMTL electrode mass to provide sufficient inertia against the magnetic pressure produced by the large currents needed to drive the z pinches. The results indicate an electrode thickness which is much smaller than the resistive skin depth. We have performed experiments to determine if such thin electrodes can efficiently carry the required current. The tests were performed with various thickness of materials. The results indicate that LMTLs should efficiently carry the large z-pinch currents needed for inertial fusion. We also use our results to estimate of the performance of pulsed power driven pulsed nuclear rockets.

SLUTZ, STEPHEN A.; OLSON, CRAIG L.; PETERSON, PER

2002-01-01T23:59:59.000Z

191

Studies of fast electron transport in the problems of inertial fusion energy  

E-Print Network (OSTI)

In the existing natural fusion reactors, stars, the gravityto the construction of the fusion reactor. In the magneticwould be for real fusion reactor conditions. The analysis of

Frolov, Boris K.

2006-01-01T23:59:59.000Z

192

Initial confinement studies of ohmically heated plasmas in the tokamak fusion test reactor  

DOE Green Energy (OSTI)

Initial operation of the tokamak fusion test reactor has concentrated upon confinement studies of ohmically heated hydrogen and deuterium plasmas. Total energy confinement times (tau/sub E/) are 0.1--0.2 s for a line-average density range (n-bar/sub e/) of (1--2.5) x 10/sup 19/ m/sup -3/ with electron temperatures of T/sub e/(o)approx.1.2--2.2 keV, ion temperatures of T/sub i/(0)approx.0.9--1.5 keV, and Z/sub eff/approx.3. A comparison of Princeton large torus, poloidal divertor experiment, and tokamak fusion test reactor plasma confinement supports a dimension-cubed scaling law.

Efthimion, P.C.; Bell, M.; Blanchard, W.R.; Bretz, N.; Cecchi, J.L.; Coonrod, J.; Davis, S.; Dylla, H.F.; Fonck, R.; Furth, H.P.

1984-04-23T23:59:59.000Z

193

REP-Rated Target Injection for Inertial Fusion Energy (A24820)  

E-Print Network (OSTI)

Fusion Sci. And Technol. 47, 1143 (2005)16th Topical Meeting on Technology Fusion Energy Madison Wisconsin, US, 2004999609950

Frey, D.T.

2004-11-05T23:59:59.000Z

194

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

E-Print Network (OSTI)

4.3.3.4 Chamber Radius and Fusion Neutron Flux . . . . .1.1.3.2 Fusion Energy . . . . . . . . .1.1.3.3 Fission-Fusion Hybrids . . . . 1.2 Scope and Purpose

Kramer, Kevin James

2010-01-01T23:59:59.000Z

195

System and method for generating steady state confining current for a toroidal plasma fusion reactor  

SciTech Connect

A system for generating steady state confining current for a toroidal plasma fusion reactor providing steady-state generation of the thermonuclear power. A dense, hot toroidal plasma is initially prepared with a confining magnetic field with toroidal and poloidal components. Continuous wave RF energy is injected into said plasma to establish a spectrum of traveling waves in the plasma, where the traveling waves have momentum components substantially either all parallel, or all anti-parallel to the confining magnetic field. The injected RF energy is phased to couple to said traveling waves with both a phase velocity component and a wave momentum component in the direction of the plasma traveling wave components. The injected RF energy has a predetermined spectrum selected so that said traveling waves couple to plasma electrons having velocities in a predetermined range .DELTA.. The velocities in the range are substantially greater than the thermal electron velocity of the plasma. In addition, the range is sufficiently broad to produce a raised plateau having width .DELTA. in the plasma electron velocity distribution so that the plateau electrons provide steady-state current to generate a poloidal magnetic field component sufficient for confining the plasma. In steady state operation of the fusion reactor, the fusion power density in the plasma exceeds the power dissipated in the plasma.

Fisch, Nathaniel J. (Cambridge, MA)

1981-01-01T23:59:59.000Z

196

System and method for generating steady state confining current for a toroidal plasma fusion reactor  

SciTech Connect

A system for generating steady state confining current for a toroidal plasma fusion reactor providing steady-state generation of the thermonuclear power. A dense, hot toroidal plasma is initially prepared with a confining magnetic field with toroidal and poloidal components. Continuous wave RF energy is injected into said plasma to estalish a spectrum of traveling waves in the plasma, where the traveling waves have momentum components substantially either all parallel, or all anti-parallel to the confining magnetic field. The injected RF energy is phased to couple to said traveling waves with both a phase velocity component and a wave momentum component in the direction of the plasma traveling wave components. The injected RF energy has a predetermined spectrum selected so that said traveling waves couple to plasma electrons having velocities in a predetermined range .DELTA.. The velocities in the range are substantially greater than the thermal electron velocity of the plasma. In addition, the range is sufficiently broad to produce a raised plateau having width .DELTA. in the plasma electron velocity distribution so that the plateau electrons provide steady-state current to generate a poloidal magnetic field component sufficient for confining the plasma. In steady state operation of the fusion reactor, the fusion power density in the plasma exceeds the power dissipated inthe plasma.

Bers, Abraham (Arlington, MA)

1981-01-01T23:59:59.000Z

197

Flibe Coolant Cleanup and Processing in the HYLIFE-II Inertial Fusion Energy Power Plant  

SciTech Connect

In the HYLIFE-II chamber design, a thick flowing blanket of molten-salt (Li{sub 2}BeF{sub 4}) called flibe is used to protect structures from radiation damage. Since it is directly exposed to the fusion target, the flibe will absorb the target debris. Removing the materials left over from target explosions at the rate of {approx}6/s and then recycling some of these materials poses a challenge for the inertial fusion energy power plant. The choice of target materials derives from multi-disciplinary criteria such as target performance, fabricability, safety and environment, corrosion, and cost of recycle. Indirect-drive targets require high-2 materials for the hohlraum. Gold and gadolinium are favorite target materials for laboratory experiments but cost considerations may preclude their use in power plants or at least requires cost effective recycle because a year's supply of gold and gadolinium is estimated at 520 M$ and 40 M$. Environmental and waste considerations alone require recycle of this material. Separation by volatility appears to be the most attractive (e.g., Hg and Xe); centrifugation (e.g., Pb) is acceptable with some problems (e.g., materials compatibility) and chemical separation is the least attractive (e.g. Gd and Hf). Mercury, hafnium and xenon might be substituted with equal target performance and have advantages in removal and recycle due to their high volatility, except for hafnium. Alternatively, lead, tungsten and xenon might be used due to the ability to use centrifugation and gaseous separation. Hafnium or tantalum form fluorides, which will complicate materials compatibility, corrosion and require sufficient volatility of the fluoride for separation. Further complicating the coolant cleanup and processing is the formation of free fluorine due to nuclear transformation of lithium and beryllium in the flibe, which requires chemical control of the fluoride level to minimize corrosion. The study of the choice of target materials and the appropriate processing needs further study because we have not come up with choices which perform as well as gold and gadolinium and which have practical processes for recovery and recycle.

Moir, R W

2001-03-23T23:59:59.000Z

198

Developing a commercial production process for 500,000 targets per day: A key challenge for inertial fusion energy  

Science Conference Proceedings (OSTI)

As is true for current-day commercial power plants, a reliable and economic fuel supply is essential for the viability of future Inertial Fusion Energy (IFE) [Energy From Inertial Fusion, edited by W. J. Hogan (International Atomic Energy Agency, Vienna, 1995)] power plants. While IFE power plants will utilize deuterium-tritium (DT) bred in-house as the fusion fuel, the 'target' is the vehicle by which the fuel is delivered to the reaction chamber. Thus the cost of the target becomes a critical issue in regard to fuel cost. Typically six targets per second, or about 500 000/day are required for a nominal 1000 MW(e) power plant. The electricity value within a typical target is about $3, allocating 10% for fuel cost gives only 30 cents per target as-delivered to the chamber center. Complicating this economic goal, the target supply has many significant technical challenge - fabricating the precision fuel-containing capsule, filling it with DT, cooling it to cryogenic temperatures, layering the DT into a uniform layer, characterizing the finished product, accelerating it to high velocity for injection into the chamber, and tracking the target to steer the driver beams to meet it with micron-precision at the chamber center.

Goodin, D.T.; Alexander, N.B.; Besenbruch, G.E.; Bozek, A.S.; Brown, L.C.; Flint, G.W.; Kilkenny, J.D.; McQuillan, B.W.; Nikroo, A.; Paguio, R.R.; Petzoldt, R.W.; Schroen, D.G.; Sheliak, J.D.; Vermillion, B.A. [General Atomics, P.O. Box 85608, San Diego, California 92186-5608 (United States); Carlson, L.C.; Goodman, P.; Maksaereekul, W.; Raffray, R.; Spalding, J.; Tillack, M.S. [University of California at San Diego, 9500 Gilman Drive, La Jolla, California 92023 (United States)] (and others)

2006-05-15T23:59:59.000Z

199

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

200

Initial confinement studies of ohmically heated plasmas in the Tokamak Fusion Test Reactor  

DOE Green Energy (OSTI)

Initial operation of the Tokamak Fusion Test Reactor (TFTR) has concentrated upon confinement studies of ohmically heated hydrogen and deuterium plasmas. Total energy confinement times (tau/sub E/) are 0.1 to 0.2 s for a line-average density range (anti n/sub e/) of 1 to 2.5 x 10/sup 19/ m/sup -3/ with electron temperatures of T/sub e/(o) approx. 1.2 to 2.2 keV, ion temperatures of T/sub i/(o) approx. 0.9 to 1.5 keV, and Z/sub eff/ approx. 3. A comparison of PLT, PDX, and TFTR plasma confinement supports a dimension-cubed scaling law.

Efthimion, P.C.; Bell, M.; Blanchard, W.R.; Bretz, N.; Cecchi, J.L.; Coonrod, J.; Davis, S.; Dylla, H.F.; Fonck, R.; Furth, H.P.

1984-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "inertial confinement fusion" 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

Prospects for inertial fusion energy based on a diode-pumped solid-state laser (DPSSL) driver: Overview and development path  

SciTech Connect

It is now known with certainty that the type of fusion known as inertial fusion will work with sufficient energy input, so inertial fusion is really beyond the ``scientific breakeven`` point in many respects. The most important question that remains for inertial fusion energy (IFE) is whether this type of fusion can operate with sufficiently low input energy to make it economically feasible for energy production. The constraint for low input energy demands operation near the inertial fusion ignition threshold, and such operation creates enormous challenges to discover a target design that will produce sufficient energy gain. There are also multiple issues relating to the scientific feasibility of using a laboratory-type ``driver`` to energize a target, such as those concerning bandwidth and beam smoothing for ``direct drive,`` and extension of hohlraum plasma physics to the IFE scale for ``indirect drive.`` One driver that appears as though it will be able to meet the IFE requirements, assuming modest development and sufficient target gain, is a diode-pumped solid-state laser (DPSSL). We give an overview of this type of laser system, and explain what development remains for the economic production of electricity using this type of driver for IFE.

Orth, C.D.

1997-03-01T23:59:59.000Z

202

The National Ignition Facility and the Promise of Inertial Fusion Energy  

Science Conference Proceedings (OSTI)

Plenary / Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1)

E. I. Moses

203

Update on diode-pumped solid-state laser experiments for inertial fusion energy  

Science Conference Proceedings (OSTI)

The authors have completed the initial phase of the diode-pumped solid-state laser (DPSSL) experimental program to validate the expected pumping dynamics and extraction cross-sections of Yb{sup 3+}-doped Sr{sub 5}(PO{sub 4}){sub 3}F (Yb:S-FAP) crystals. Yb:S-FAP crystals up to 25 x 25 x 175 mm in size have been grown for this purpose which have acceptable loss characteristics (energy transmission properties of a Yb:S-FAP rod. The small signal gain under saturated pumping conditions was measured. These measurements imply an emission cross section of 6.0 x 10{sup {minus}20} cm{sup 2} that falls within error bars of the previously reported value of 7.3 x 10{sup {minus}20} cm{sup 2}, obtained from purely spectroscopic techniques. The effects of radiation trapping on the emission lifetime have been quantified. The long lifetime of Yb:S-FAP has beneficial effects for diode-pumped amplifier designs, relative to materials with equivalent cross sections but shorter lifetimes, in that less peak pump intensity is required (thus lower diode costs) and that lower spontaneous emission rates lead to a reduction in amplified spontaneous emission. Consequently, up to 1.7 J/cm{sup 3} of stored energy density was achieved in a 6x6x44 mm Yb:S-FAP amplifier rod; this stored energy density is large relative to typical flashlamp-pumped Nd:glass values of 0.3 to 0.5 J/cm{sup 3}. A 2.4 kW peak power InGaAs diode array has been fabricated by Beach, Emanuel, and co-workers which meets the central wavelength, bandwidth, and energy specifications for the author`s immediate experiments. These results further increase their optimism of being able to produce a {approximately} 10% efficient diode-pumped solid state laser for inertial fusion energy.

Marshall, C.; Smith, L.; Payne, S.

1994-08-15T23:59:59.000Z

204

Heavy Ion Fusion Systems Assessment study  

SciTech Connect

The Heavy Ion Fusion Systems Assessment (HIFSA) study was conducted with the specific objective of evaluating the prospects of using induction linac drivers to generate economical electrical power from inertial confinement fusion. The study used algorithmic models of representative components of a fusion system to identify favored areas in the multidimensional parameter space. The resulting cost-of-electricity (COE) projections are comparable to those from other (magnetic) fusion scenarios, at a plant size of 100 MWe.

Dudziak, D.J.; Herrmannsfeldt, W.B.

1986-07-01T23:59:59.000Z

205

Cost reduction possibilities for a heavy-ion accelerator for inertial confinement fusion  

SciTech Connect

A design was produced for a single module in a cost-optimized accelerator appropriate for a commercial heavy-ion power plant. The goal of the study was to determine if the cost of the accelerator module could be reduced through design options, selection of materials, and manufacturing techniques. Independent cost estimates were obtained for the three main components of the module, and cost reductions of 20% from the cost calculated by the heavy-ion accelerator design/cost-minimization computer code LIACEP were identified. 3 refs., 23 figs.

Thayer, G.R.; Sims, J.R.; Henke, M.D.; Harris, D.B.; Dudziak, D.J.; Phillips, N.R.

1987-10-01T23:59:59.000Z

206

Direct-Drive Inertial Confinement Fusion Research at the Laboratory for Laser Energetics  

E-Print Network (OSTI)

beams Relative size 240 ft National Ignition Facility (NIF) 1.8 MJ 192 beams NIF The National Ignition (NIF) is predicted to achieve high-gain (~40). · Direct drive targets are predicted to ignite on the NIF while it is in x-ray-drive configuration with polar direct drive (PDD). · Fully integrated fast

207

Target Fabrication in Support of Inertial Confinement Fusion and High Energy Density Physics Experiments  

E-Print Network (OSTI)

Bull. Am. Phys. Soc. 52, 354 (2007)49th American Physical Society Annual Meeting of Division of Plasma Physics Orlando Florida, US, 2007999614070

Back, C.A.

2007-07-18T23:59:59.000Z

208

Inertial confinement fusion quarterly report, January--March 1993. Volume 3, No. 2  

DOE Green Energy (OSTI)

This report discusses the following topics: High Fluence Third Harmonic Generation; Ultraviolet Induced Transient Absorption in KDP and Its Influence on Fourth Harmonic Frequency Conversion; Relativistic Semiclassical Atomic Transition Rates; Verification of OPAL Opacity Code Predictions for Conditions of Astrophysical Interest; Solid Hydrogen Surfaces; Large Aperture Sol-Gel Random Phase Plates for Beam Smoothing on Nova; and Neutron Time-of-Flight Ion Temperature Diagnostic for Nova.

Amendt, P.A. [ed.

1993-09-01T23:59:59.000Z

209

Prediction of inertial confinement fusion chamber gas evolution using multi-species computational fluid dynamics  

E-Print Network (OSTI)

18] Reactor Design, ChemKin r Software Theory Manual,Reactor Designs ChemKin software package. The ChemKin theory

Martin, Robert Scott

2007-01-01T23:59:59.000Z

210

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

E-Print Network (OSTI)

The f a s t breeder reactor should in theory solve the fuellight water reactors. The ICF driver could, in theory, serve

Herrmannsfeldt, W.b.

2010-01-01T23:59:59.000Z

211

Improved lifetimes and synchronization behavior in multi-grid inertial electrostatic confinement fusion devices  

E-Print Network (OSTI)

A high output power source is required for fast, manned exploration of the solar system, especially the outer planets. Travel times measured in months, not years, will require high power, lightweight nuclear systems. The ...

McGuire, Thomas John, 1977-

2007-01-01T23:59:59.000Z

212

Multifluid interpenetration mixing in directly driven inertial confinement fusion capsule implosionsa...  

E-Print Network (OSTI)

. An alternative to a Paper BI2 4, Bull. Am. Phys. Soc. 48, 21 2003 . b Invited speaker. Electronic mail: dcw

213

A new aperture for neutron and x-ray imaging of inertial confinement fusion experiments  

Science Conference Proceedings (OSTI)

Recent neutron imaging of experiments at the National Ignition Facility has provided useful information about the hotspot shape and cold-fuel distribution and has also given insight into avenues for improvement. Neutron image reconstruction depends on accurate pointing information because the point-spread function of the neutron aperture is not shift invariant. Current pointing techniques are limited in their accuracy and rely upon detailed information about the as-built structure of the array, which is difficult to determine. We present a technique for extracting high-precision pointing information from both neutron and x-ray images, and a new aperture design with features to facilitate this technique, and allow future co-registration of neutron and x-ray images.

Danly, C. R.; Grim, G. P.; Guler, N.; Intrator, M. H.; Merrill, F. E.; Volegov, P.; Wilde, C. H. [Los Alamos National Laboratory, PO Box 1663, Los Alamos, New Mexico 87545 (United States)

2012-10-15T23:59:59.000Z

214

Diagnosing inertial confinement fusion implosions at OMEGA and the NIF Using novel neutron spectrometry  

E-Print Network (OSTI)

A novel neutron spectrometer, called the Magnetic Recoil Spectrometer (MRS), was designed, built, and implemented on the OMEGA laser facility and the National Ignition Facility (NIF) to measure the neutron spectra from ...

Casey, Daniel Thomas

2012-01-01T23:59:59.000Z

215

Bayesian inference of inaccuracies in radiation transport physics from inertial confinement fusion experiments  

E-Print Network (OSTI)

First principles microphysics models are essential to the design and analysis of high energy density physics experiments. Using experimental data to investigate the underlying physics is also essential, particularly when simulations and experiments are not consistent with each other. This is a difficult task, due to the large number of physical models that play a role, and due to the complex (and as a result, noisy) nature of the experiments. This results in a large number of parameters that make any inference a daunting task; it is also very important to consistently treat both experimental and prior understanding of the problem. In this paper we present a Bayesian method that includes both these effects, and allows the inference of a set of modifiers which have been constructed to give information about microphysics models from experimental data. We pay particular attention to radiation transport models. The inference takes into account a large set of experimental parameters and an estimate of the prior kno...

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

2013-01-01T23:59:59.000Z

216

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

E-Print Network (OSTI)

it is unlikely that nuclear fission power plants willIn the case of nuclear fission reactions, the fundamentalaspects of nuclear fusion and fission. This approach, termed

Kramer, Kevin James

2010-01-01T23:59:59.000Z

217

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

218

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

E-Print Network (OSTI)

1.1.3.1 Fission Energy . . . . . . . . . 1.1.3.21.1.3.3 Fission-Fusion Hybrids . . . . 1.2 Scope and Purposei CONTENTS Fission Blanket . . . . . . . . . . . . . . . . .

Kramer, Kevin James

2010-01-01T23:59:59.000Z

219

FusEdWeb | Fusion Education  

NLE Websites -- All DOE Office Websites (Extended Search)

FAQ FAQ FusEdWeb: Discover Fusion CPEP's Online Fusion Course Fusion FAQ Fusion and Plasma Glossary Plasma Dictionary Student and Teacher Resources Education and Outreach Ideas Other Fusion and Plasma Sites Great Sites Internet Plasma Physics EXperience GA's Fusion Energy Slide Show International Thermonuclear Experimental Reactor National Ignition Facility Search webby award honoree Webby Awards Honoree April 10, 2007 webby award honoree Links2Go - Fusion, November 9, 1998 FusEdWeb: Fusion Energy Education Our Sun | Other Stars and Galaxies | Inertial Confinement | Magnetic Confinement Answers to Frequently Asked Questions about Fusion Research An updated, searchable Fusion FAQ is being prepared. In the meantime, the incomplete public-domain Fusion FAQ from 1994-1995 is still available

220

Apparatus and method for removing particle species from fusion-plasma-confinement devices  

DOE Patents (OSTI)

In a mirror fusion plasma confinement apparatus, method and apparatus are provided for selectively removing (pumping) trapped low energy (thermal) particle species from the end cell region, without removing the still useful high energy particle species, and without requiring large power input to accomplish the pumping. Perturbation magnets are placed in the thermal barrier region of the end cell region at the turning point characteristic of trapped thermal particles, thus deflecting the thermal particles from their closed trajectory, causing them to drift sufficiently to exit the thermal barrier.

Hamilton, G.W.

1981-10-26T23:59:59.000Z

Note: This page contains sample records for the topic "inertial confinement fusion" 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

Use of Clearance Indexes to Assess Waste Disposal Issues for the HYLIFE-II Inertial Fusion Energy Power Plant Design  

SciTech Connect

Traditionally, waste management studies for fusion energy have used the Waste Disposal Rating (WDR) to evaluate if radioactive material from irradiated structures could qualify for shallow land burial. However, given the space limitations and the negative public perception of large volumes of waste, there is a growing international motivation to develop a fusion waste management system that maximizes the amount of material that can be cleared or recycled. In this work, we present an updated assessment of the waste management options for the HYLIFE-II inertial fusion energy (IFE) power plant, using the concept of Clearance Index (CI) for radioactive waste disposal. With that purpose, we have performed a detailed neutronics analysis of the HYLIFE-II design, using the TART and ACAB computer codes for neutron transport and activation, respectively. Whereas the traditional version of ACAB only provided the user with the WDR as an index for waste considerations, here we have modified the code to calculate Clearance Indexes using the current International Atomic Energy Agency (IAEA) clearance limits for radiological waste disposal. The results from the analysis are used to perform an assessment of the waste management options for the HYLIFE-II IFE design.

Reyes, S; Latkowski, J F; Sanz, J

2002-01-17T23:59:59.000Z

222

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

223

Krypton Fluoride (KrF) Laser Driver for Inertial Fusion Energy  

Science Conference Proceedings (OSTI)

IFE / Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 1), Nashville, Tennessee, August 27-31, 2012

Matthew F. Wolford; John D. Sethian; Matthew C. Myers; Frank Hegeler; John L. Giuliani; Stephen P. Obenschain

224

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

E-Print Network (OSTI)

Code MFE Magnetic Fusion Energy MOX Mixed Oxide NES Nuclearreprocessing mixed oxide (MOX) fuels, as will be discussedbegun using Mixed ox- ide or MOX fuel as a means of both

Kramer, Kevin James

2010-01-01T23:59:59.000Z

225

FusEdWeb | Fusion Education  

NLE Websites -- All DOE Office Websites (Extended Search)

Our Sun Our Sun FusEdWeb: Discover Fusion CPEP's Online Fusion Course Fusion FAQ Fusion and Plasma Glossary Plasma Dictionary Student and Teacher Resources Education and Outreach Ideas Other Fusion and Plasma Sites Great Sites Internet Plasma Physics EXperience GA's Fusion Energy Slide Show International Thermonuclear Experimental Reactor National Ignition Facility Search webby award honoree Webby Awards Honoree April 10, 2007 webby award honoree Links2Go - Fusion, November 9, 1998 FusEdWeb: Fusion Energy Education Our Sun | Other Stars and Galaxies | Inertial Confinement | Magnetic Confinement The Sun Runs on Fusion Energy How the sun looks through x-ray eyes! Like all stars, the sun is a huge fusion reactor, pumping out 100 million times as much energy in a single second as the entire population of Earth

226

Accelerators for heavy ion fusion  

SciTech Connect

Large fusion devices will almost certainly produce net energy. However, a successful commercial fusion energy system must also satisfy important engineering and economic constraints. Inertial confinement fusion power plants driven by multi-stage, heavy-ion accelerators appear capable of meeting these constraints. The reasons behind this promising outlook for heavy-ion fusion are given in this report. This report is based on the transcript of a talk presented at the Symposium on Lasers and Particle Beams for Fusion and Strategic Defense at the University of Rochester on April 17-19, 1985.

Bangerter, R.O.

1985-10-01T23:59:59.000Z

227

Magnetized target fusion and fusion propulsion.  

DOE Green Energy (OSTI)

Magnetized target fusion (MTF) is a thermonuclear fusion concept that is intermediate between the two mainline approaches, magnetic confinement and inertial confinement fusion (MCF and ICF). MTF incorporates some aspects of each and offers advantages over each of the mainline approaches. First, it provides a means of reducing the driver power requirements, thereby admitting a wider range of drivers than ICF. Second, the magnetic field is only used for insulation, not confinement, and the plasma is wall confined, so that plasma instabilities are traded in for hydrodynamic instabilities. However, the degree of compression required to reach fusion conditions is lower than for ICF, so that hydrodynamic instabilities are much less threatening. The standoff driver innovation proposes to dynamically form the target plasma and a gaseous shell that compresses and confines the target plasma. Therefore, fusion target fabrication is traded in for a multiplicity of plasma guns, which must work in synchrony. The standoff driver embodiment of MTF leads to a fusion propulsion system concept that is potentially compact and lightweight. We will discuss the underlying physics of MTF and some of the details of the fusion propulsion concept using the standoff driver approach. We discuss here the optimization of an MTF target design for space propulsion.

Kirkpatrick, R. C. (Ronald C.)

2001-01-01T23:59:59.000Z

228

Magneized target fusion: An overview of the concept  

SciTech Connect

Magnetized target fusion (MTF) seeks to take advantage of the reduction of thermal conductivity through the application of a strong magneticfield and thereby ease the requirements for reaching fusion conditions in a thermonuclear (TN) fusion fuel. A potentially important benefit of the strong field in the partial trapping of energetic charged particles to enhance energy deposition by the TN fusion reaction products. The essential physics is described. MTF appears to lead to fusion targets that require orders of magnitude less power and intensity for fusion ignition than currently proposed (unmagnetized) inertial confinement fusion (ICF) targets do, making some very energetic pulsed power drivers attractive for realizing controlled fusion.

Kirkpatrick, R.C.

1994-12-31T23:59:59.000Z

229

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

230

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

231

FusEdWeb | Fusion Education  

NLE Websites -- All DOE Office Websites (Extended Search)

About Us About Us FusEdWeb: Discover Fusion CPEP's Online Fusion Course Fusion FAQ Fusion and Plasma Glossary Plasma Dictionary Student and Teacher Resources Education and Outreach Ideas Other Fusion and Plasma Sites Great Sites Internet Plasma Physics EXperience GA's Fusion Energy Slide Show International Thermonuclear Experimental Reactor National Ignition Facility Search webby award honoree Webby Awards Honoree April 10, 2007 webby award honoree Links2Go - Fusion, November 9, 1998 FusEdWeb: Fusion Energy Education Our Sun | Other Stars and Galaxies | Inertial Confinement | Magnetic Confinement Webby Honoree graphic graphic Key Resource Snap editors choice new scientist DrMatrix Webby Awards Honoree, April 10, 2007 The Alchemist - WebPick, January 29, 1999 Links2Go - Fusion, November 9, 1998 October 19, 1998 - October 19, 1999 Site of the Day, September 24, 1998. Hot spot. Student Science Resource, April 16, 1997

232

FusEdWeb | Fusion Education  

NLE Websites -- All DOE Office Websites (Extended Search)

Glossary Glossary FusEdWeb: Discover Fusion CPEP's Online Fusion Course Fusion FAQ Fusion and Plasma Glossary Plasma Dictionary Student and Teacher Resources Education and Outreach Ideas Other Fusion and Plasma Sites Great Sites Internet Plasma Physics EXperience GA's Fusion Energy Slide Show International Thermonuclear Experimental Reactor National Ignition Facility Search webby award honoree Webby Awards Honoree April 10, 2007 webby award honoree Links2Go - Fusion, November 9, 1998 FusEdWeb: Fusion Energy Education Our Sun | Other Stars and Galaxies | Inertial Confinement | Magnetic Confinement The Glossary of Plasma Physics and Fusion Energy Research Browse | Search | Submit an Entry Introduction, Sources and Contributors This Glossary seeks to provide plain-language definitions of over 3600

233

FusEdWeb | Fusion Education  

NLE Websites -- All DOE Office Websites (Extended Search)

Home> Student and Teacher Resources > For Introductory Students Home> Student and Teacher Resources > For Introductory Students FusEdWeb: Discover Fusion CPEP's Online Fusion Course Fusion FAQ Fusion and Plasma Glossary Plasma Dictionary Student and Teacher Resources Education and Outreach Ideas Other Fusion and Plasma Sites Great Sites Internet Plasma Physics EXperience GA's Fusion Energy Slide Show International Thermonuclear Experimental Reactor National Ignition Facility Search webby award honoree Webby Awards Honoree April 10, 2007 webby award honoree Links2Go - Fusion, November 9, 1998 FusEdWeb: Fusion Energy Education Our Sun | Other Stars and Galaxies | Inertial Confinement | Magnetic Confinement Guide to Fusion Education Resources for Introductory Physics Students This is a compilation of online and offline education resources for

234

The Production and Delivery of an Inertial Fusion Energy Power Plant Fuel - The Cryogenic Target (A25529)  

E-Print Network (OSTI)

Proc. Of 24th Symposium On Fusion Technology, Warsaw, Poland (2006), To Be Published In Fusion Eng, And Design24th Symposium on Fusion Technology Warsaw, pl, 2006999612525

Bozek, A.S.

2006-09-01T23:59:59.000Z

235

DEMONSTRATING A TARGET SUPPLY FOR INERTIAL FUSION ENERGY D.T. Goodin,1 N.B. Alexander,1 L.C. Brown,1 D.A. Callahan,2 P. Ebey,3 D.T. Frey,1 R. Gallix,1 D. Geller,3  

E-Print Network (OSTI)

DEMONSTRATING A TARGET SUPPLY FOR INERTIAL FUSION ENERGY D.T. Goodin,1 N.B. Alexander,1 L.C. Brown-5608 A central feature of an Inertial Fusion Energy (IFE) power plant is a target that has been compressed and heated to fusion conditions by the energy input of the driver. The technology to economically manufacture

Raffray, A. René

236

Automated laser fusion target production concept  

SciTech Connect

A target production concept is described for the production of multilayered cryogenic spherical inertial confinement fusion targets. The facility is to deliver targets to the reactor chamber at rates up to 10 per second and at costs consistent with economic production of power.

Hendricks, C.D.

1977-10-04T23:59:59.000Z

237

Integrated process modeling for the laser inertial fusion Energy (LIFE) generation system  

Science Conference Proceedings (OSTI)

A concept for a new fusion-fission hybrid technology is being developed at Lawrence Livermore National Laboratory. The primary application of this technology is base-load electrical power generation. However, variants of the baseline technology can be used to 'burn' spent nuclear fuel from light water reactors or to perform selective transmutation of problematic fission products. The use of a fusion driver allows very high burn-up of the fission fuel, limited only by the radiation resistance of the fuel form and system structures. As a part of this process, integrated process models have been developed to aid in concept definition. Several models have been developed. A cost scaling model allows quick assessment of design changes or technology improvements on cost of electricity. System design models are being used to better understand system interactions and to do design trade-off and optimization studies. Here we describe the different systems models and present systems analysis results. Different market entry strategies are discussed along with potential benefits to US energy security and nuclear waste disposal. Advanced technology options are evaluated and potential benefits from additional R&D targeted at the different options is quantified.

Meier, W R; Anklam, T M; Erlandson, A C; Miles, R R; Simon, A J; Sawicki, R; Storm, E

2009-10-22T23:59:59.000Z

238

University of California, San Diego UCSD-ENG-090 Fusion Division  

E-Print Network (OSTI)

: A Stationary Inertial-Confinement Fusion Reactor with Non- vaporizing Walls," 13th IEEE Symposium on Fusion) compressible response to impulsive loading on wavy free surfaces, and (3) energy deposition, phase change energy density 200 kJ/m3 Laser propagation limits laser intensity compression beam 1014~1015 W/cm2

Krstic, Miroslav

239

MIT Plasma Fusion Sciences Center IAP Seminar! Jan 10th, 2012!  

E-Print Network (OSTI)

MIT Plasma Fusion Sciences Center IAP Seminar! Jan 10th, 2012! ! ! ! ! ! Otto Landen! Associate-07NA27344 Inertial Confinement Fusion Physics and Challenges*! #12;The NIF ignition experiments-degenerate fuel Spherical collapse of the shell produces a central hot spot surrounded by cold, dense main fuel

240

Program on Technology Innovation: Assessment of Fusion Energy Options for Commercial Electricity Production  

Science Conference Proceedings (OSTI)

Fusion energy options were reviewed to assess technical readiness levels for commercial electricity production for the power industry. Magnetic and inertial confinement systems, in addition to nontraditional fusion concepts, were reviewed by a technical panel of experts, based on workshop presentations by the proponents of each technology. The results are summarized in this ...

2012-10-15T23:59:59.000Z

Note: This page contains sample records for the topic "inertial confinement fusion" 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

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

DOE Green Energy (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

242

U.S. Heavy Ion Beam Science towards inertial fusion energy  

DOE Green Energy (OSTI)

Significant experimental and theoretical progress in the U.S heavy-ion fusion (HIF) program is reported in modeling and measurements of intense space-charge-dominated heavy ion and electron beams. Measurements of the transport of a well-matched and aligned high current (0.2A) 1.0 MeV potassium ion beam through 10 electric quadrupoles, with a fill factor of 60%, shows no emittance growth within experimental measurement uncertainty, as expected from the simulations. Another experiment shows that passing a beam through an aperture can reduce emittance to near the theoretical limits, and that plasma neutralization of the beam's space-charge can greatly reduce the focal spot radius. Measurements of intense beamlet current density, emittance, charge-state purity, and energy spread from a new, high-brightness, Argon plasma source for HIF experiments are described. New theory and simulations of neutralization of intense beam space charge with plasma in various focusing chamber configurations indicate that near-emittance-limited beam focal spot sizes can be obtained even with beam perveance an order of magnitude higher than in earlier HIF focusing experiments.

Logan, B.G.; Baca, D.; Barnard, J.J.; Bieniosek, F.M.; Burkhart, C.; Celata, C.M.; Chacon-Golcher, E.; Cohen, R.H.; Davidson, R.C.; Efthimion P.; Faltens, A.; Friedman, A.; Grisham, L.; Grote, D.P.; Haber, I.; Henestroza, E.; Kaganovich, I.; Kishek, R.A.; Kwan, J.W.; Lee, E.P.; Lee, W.W.; Leitner, M.; Lund, S.M.; Meier, W.R.; Molvik, A.W.; O'Shea, P.G.; Olson, C.; Olson, R.E.; Prost, L.R.; Qin, H.; Reiser, M.; Rose, D.; Sabbi, G.; Seidl, P.A.; Sharp, W.M.; Shuman, D.B.; Vay, J-L.; Waldron, W.L.; Welch, D.; Westenskow, G.A.; Yu, S.S.

2002-10-01T23:59:59.000Z

243

Radiological design criteria for fusion power test facilities  

Science Conference Proceedings (OSTI)

The quest for fusion power and understanding of plasma physics has resulted in planning, design, and construction of several major fusion power test facilities, based largely on magnetic and inertial confinement concepts. We have considered radiological design aspects of the Joint European Torus (JET), Livermore Mirror and Inertial Fusion projects, and Princeton Tokamak. Our analyses on radiological design criteria cover acceptable exposure levels at the site boundary, man-rem doses for plant personnel and population at large, based upon experience gained for the fission reactors, and on considerations of cost-benefit analyses.

Singh, M.S.; Campbell, G.W.

1982-02-12T23:59:59.000Z

244

A Continuous, In-Chamber Target Tracking and Engagement Approach for Laser Fusion  

Science Conference Proceedings (OSTI)

Technical Paper / The Technology of Fusion Energy - Inertial Fusion Technology: Targets and Chambers

Ron Petzoldt; Neil Alexander; Lane Carlson; Graham Flint; Dan Goodin; Jon Spalding; Mark Tillack

245

Controlled thermonuclear fusion reactors  

SciTech Connect

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

Walstrom, P.L.

1976-01-01T23:59:59.000Z

246

Inertial confinement fusion target component fabrication and technology development support. Annual report, October 1, 1996--September 30, 1997  

Science Conference Proceedings (OSTI)

This report documents the technical activities of the period October 1, 1996 through September 30, 1997. During this period, GA and their partner Schafer Corporation were assigned 13 formal tasks in support of the ICF program and its five laboratories. A portion of the effort on these tasks included providing direct {open_quotes}Onsite Support{close_quotes} at Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), and Sandia National Laboratory Albuquerque (SNLA). Over 700 gold-plated hohlraum mandrels were fabricated and delivered to LLNL, LANL and SNLA. More than 1600 glass and plastic target capsules were produced for LLNL, LANL, SNLA and University of Rochester/Laboratory for Laser Energetics (UR/LLE). Nearly 2000 various target foils and films were delivered for Naval Research Lab (NRL) and UR/LLE in FY97. This report describes these target fabrication activities and the target fabrication and characterization development activities that made the deliveries possible. The ICF program is anticipating experiments at the OMEGA laser and the National Ignition Facility (NIF) which will require targets containing cryogenic layered D{sub 2} or deuterium-tritium (DT) fuel. This project is part of the National Cryogenic Target Program and support experiments at LLNL and LANL to generate and characterize cryogenic layers for these targets. During FY97, significant progress was made in the design and component testing of the OMEGA Cryogenic Target System that will field cryogenic targets on OMEGA. This included major design changes, reduction in equipment, and process simplifications. This report summarizes and documents the technical progress made on these tasks.

Gibson, J. [ed.

1998-03-01T23:59:59.000Z

247

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

SciTech Connect

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

248

Electra: An Electron Beam Pumped KrF Rep-Rate Laser System for Inertial Fusion Energy  

Science Conference Proceedings (OSTI)

High Average Power Laser and Other IFE R&D / Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1)

P. M. Burns et al.

249

Solenoid transport for heavy ion fusion  

E-Print Network (OSTI)

Transport for Heavy Ion Fusion* Edward Lee** LawrenceHm Heavy Ion Inertial Fusion Abstract Solenoid transport ofseveral stages of a heavy ion fusion driver. In general this

Lee, Edward

2004-01-01T23:59:59.000Z

250

An important challenge in magnetic fusion research is to obtain high energy confinement in a stationary plasma that will be co  

NLE Websites -- All DOE Office Websites (Extended Search)

Ways to reduce your tokamak heating bill: Gaining control of edge transport Ways to reduce your tokamak heating bill: Gaining control of edge transport barriers on Alcator C-Mod A crucial challenge in magnetic fusion is to obtain high energy confinement in a stationary plasma that is compatible with the engineering requirements of a fusion reactor. The triggering of edge transport barriers at the boundary of confined plasma is a common approach to obtaining high energy confinement, in a regime known as H-mode, which extrapolates to high performance in ITER and other burning plasma devices. However, barriers to energy transport can sometimes be self-defeating, since they also provide a strong barrier to particle transport. This can lead to enhanced confinement of impurities in the plasma core, excessive radiated power and deterioration of performance for a given

251

American Fusion News | Princeton Plasma Physics Lab  

NLE Websites -- All DOE Office Websites (Extended Search)

American Fusion News American Fusion News General Atomics (GA) December 4, 2012 The Scorpion's Strategy: "Catch and Subdue" December 4, 2012 Frozen Bullets Tame Unruly Edge Plasmas in Fusion Experiment February 15, 2012 General Atomics (GA) Fusion News: A New Spin on Understanding Plasma Confinement See All Massachusetts Institute of Technology (MIT) April 5, 2013 Applying physics, teamwork to fusion energy science February 22, 2013 A Tour of Plasma Physics in Downtown Cambridge December 4, 2012 Placing Fusion Power on a Pedestal September 21, 2012 MASSACHUSETTS INSTITUTUE OF TECHNOLOGY See All National Ignition Facility February 22, 2013 Summary of Assessment of Prospects for Inertial Fusion Energy February 16, 2012 National Ignition Facility (NIF): Under Pressure: Ramp-Compression Smashes

252

Particle-beam fusion research facilities at Sandia National Laboratories  

SciTech Connect

Sandia research in inertial-confinement fusion (ICF) is based on pulse-power capabilities that grew out of earlier developments of intense relativistic electron-beam (e-beam) radiation sources for weapon effects studies. ICF involves irradiating a deuterium-tritium pellet with either laser light or particle beams until the center of the pellet is compressed and heated to the point of nuclear fusion. This publication focuses on the use of particle beams to achieve fusion, and on the various facilities that are used in support of the particle-beam fusion (PBF) program.

1980-12-31T23:59:59.000Z

253

Advanced fission and fossil plant economics-implications for fusion  

Science Conference Proceedings (OSTI)

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

Delene, J.G.

1994-09-01T23:59:59.000Z

254

Fudge: a high-bandwidth fusion diagnostic of the NIF  

SciTech Connect

Diagnostics for the National Ignition Facility (NIF)/Inertial Confinement Fusion (ICF) program must include good characterization of the fusion source. Ideally, diagnostics would measure the spatially-resolved history of the fusion reaction rate and temperature. Existing diagnostics can satisfy this goal only partially. One class of new techniques that could play a major role in high-yield diagnostics is measurements based on fusion {gamma} rays. The Fusion Diagnostic Gamma Experiment (FUDGE) can be used to perform energy-resolved measurements of (D,T) fusion reaction rates This diagnostic is based on the 16 7-MeV {gamma} rays that are produced by (D,T) fusion. The {gamma} rays are free of spectral dispersion and can be detected with a high bandwidth Cherenkov detector. A simple magnetic monochromator selects signals from the 16 7-MeV {gamma} rays and reduces background signals from non-fusion {gamma} rays.

Moran, M. J., LLNL

1998-06-02T23:59:59.000Z

255

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

256

Method and system to directly produce electrical power within the lithium blanket region of a magnetically confined, deuterium-tritium (DT) fueled, thermonuclear fusion reactor  

DOE Patents (OSTI)

A method for integrating liquid metal magnetohydrodynamic power generation with fusion blanket technology to produce electrical power from a thermonuclear fusion reactor located within a confining magnetic field and within a toroidal structure. A hot liquid metal flows from a liquid metal blanket region into a pump duct of an electromagnetic pump which moves the liquid metal to a mixer where a gas of predetermined pressure is mixed with the pressurized liquid metal to form a Froth mixture. Electrical power is generated by flowing the Froth mixture between electrodes in a generator duct. When the Froth mixture exits the generator the gas is separated from the liquid metal and both are recycled.

Woolley, Robert D. (Belle Mead, NJ)

1999-01-01T23:59:59.000Z

257

Method and System to Directly Produce Electrical Power within the Lithium Blanket Region of a Magnetically Confined, Deuterium-Tritium (DT) Fueled, Thermonuclear Fusion Reactor  

DOE Patents (OSTI)

A method for integrating liquid metal magnetohydrodynamic power generation with fusion blanket technology to produce electrical power from a thermonuclear fusion reactor located within a confining magnetic field and within a toroidal structure. A hot liquid metal flows from a liquid metal blanket region into a pump duct of an electromagnetic pump which moves the liquid metal to a mixer where a gas of predetermined pressure is mixed with the pressurized liquid metal to form a Froth mixture. Electrical power is generated by flowing the Froth mixture between electrodes in a generator duct. When the Froth mixture exits the generator the gas is separated from the liquid metal and both are recycled.

Woolley, Robert D.

1998-09-22T23:59:59.000Z

258

LDRD final report on confinement of cluster fusion plasmas with magnetic fields.  

Science Conference Proceedings (OSTI)

Two versions of a current driver for single-turn, single-use 1-cm diameter magnetic field coils have been built and tested at the Sandia National Laboratories for use with cluster fusion experiments at the University of Texas in Austin. These coils are used to provide axial magnetic fields to slow radial loss of electrons from laser-produced deuterium plasmas. Typical peak field strength achievable for the two-capacitor system is 50 T, and 200 T for the ten-capacitor system. Current rise time for both systems is about 1.7 {mu}s, with peak current of 500 kA and 2 MA, respectively. Because the coil must be brought to the laser, the driver needs to be portable and drive currents in vacuum. The drivers are complete but laser-plasma experiments are still in progress. Therefore, in this report, we focus on system design, initial tests, and performance characteristics of the two-capacitor and ten-capacitors systems. The questions of whether a 200 T magnetic field can retard the breakup of a cluster-fusion plasma, and whether this field can enhance neutron production have not yet been answered. However, tools have been developed that will enable producing the magnetic fields needed to answer these questions. These are a two-capacitor, 400-kA system that was delivered to the University of Texas in 2010, and a 2-MA ten-capacitor system delivered this year. The first system allowed initial testing, and the second system will be able to produce the 200 T magnetic fields needed for cluster fusion experiments with a petawatt laser. The prototype 400-kA magnetic field driver system was designed and built to test the design concept for the system, and to verify that a portable driver system could be built that delivers current to a magnetic field coil in vacuum. This system was built copying a design from a fixed-facility, high-field machine at LANL, but made to be portable and to use a Z-machine-like vacuum insulator and vacuum transmission line. This system was sent to the University of Texas in Austin where magnetic fields up to 50 T have been produced in vacuum. Peak charge voltage and current for this system have been 100 kV and 490 kA. It was used this last year to verify injection of deuterium and surrogate clusters into these small, single-turn coils without shorting the coil. Initial test confirmed the need to insulate the inner surface of the coil, which requires that the clusters must be injected through small holes in an insulator. Tests with a low power laser confirmed that it is possible to inject clusters into the magnetic field coils through these holes without destroying the clusters. The university team also learned the necessity of maintaining good vacuum to avoid insulator, transmission line, and coil shorting. A 200-T, 2 MA system was also constructed using the experience from the first design to make the pulsed-power system more robust. This machine is a copy of the prototype design, but with ten 100-kV capacitors versus the two used in the prototype. It has additional inductance in the switch/capacitor unit to avoid breakdown seen in the prototype design. It also has slightly more inductance at the cable connection to the vacuum chamber. With this design we have been able to demonstrate 1 MA current into a 1 cm diameter coil with the vacuum chamber at air pressure. Circuit code simulations, including the additional inductance with the new design, agree well with the measured current at a charge voltage of 40 kV with a short circuit load, and at 50 kV with a coil. The code also predicts that with a charge voltage of 97 kV we will be able to get 2 MA into a 1 cm diameter coil, which will be sufficient for 200 T fields. Smaller diameter or multiple-turn coils will be able to achieve even higher fields, or be able to achieve 200-T fields with lower charge voltage. Work is now proceeding at the university under separate funding to verify operation at the 2-MA level, and to address issues of debris mitigation, measurement of the magnetic field, and operation in vacuum. We anticipate operation at full current with single

Argo, Jeffrey W.; Kellogg, Jeffrey W.; Headley, Daniel Ignacio; Stoltzfus, Brian Scott; Waugh, Caleb J.; Lewis, Sean M.; Porter, John Larry, Jr.; Wisher, Matthew; Struve, Kenneth William; Savage, Mark Edward; Quevedo, Hernan J.; Bengtson, Roger

2011-11-01T23:59:59.000Z

259

FusEdWeb | Fusion Education  

NLE Websites -- All DOE Office Websites (Extended Search)

- Fusion, November 9, 1998 FusEdWeb: Fusion Energy Education Overview | The Guided Tour Creating the Conditions for Fusion PLASMA CONFINEMENT AND HEATING Fusion requires high...

260

Technological implications of fusion power: requirements and status  

SciTech Connect

The major technological requirements for fusion power, as implied by current conceptual designs of fusion power plants, are identified and assessed relative to the goals of existing technology programs. The focus of the discussion is on the tokamak magnetic confinement concept; however, key technological requirements of mirror magnetic confinement systems and of inertial confinement concepts will also be addressed. The required technology is examined on the basis of three general areas of concern: (a) the power balance, that is, the unique power handling requirements associated with the production of electrical power by fusion; (b) reactor design, focusing primarily on the requirements imposed by a tritium-based fuel cycle, thermal hydraulic considerations, and magnet systems; and (c) materials considerations, including radiation damage effects, neutron-induced activation, and resource limitations.

Steiner, D.

1978-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "inertial confinement fusion" from the National Library of EnergyBeta (NLEBeta).
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261

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

DOE Green Energy (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

262

Controlled thermonuclear fusion research in Europe -- Competence in advanced physics and technologies  

SciTech Connect

Development of Fusion power is being pursued in all major industrial countries. The European Union, together with countries associated to the EURATOM-Framework Program undertakes an integrated RTD program for the development of magnetic fusion. The Key Action Controlled Thermonuclear Fusion has the objectives to develop the capacity to construct and operated a Next Step device for which the design is being pursued in international collaboration (ITER EDA, International Thermonuclear Experimental Reactor Engineering Design Activities); to undertake structured activities for concept improvements for a fusion power station; to develop technologies needed in the longer term for a prototype fusion reactor. Work on the socio-economic aspects of fusion and a keep in touch activity coordinating national civil research activities in inertial confinement fusion complement the program.

Bruhns, H.

2000-03-01T23:59:59.000Z

263

Materials for Inertial Fusion Energy  

Science Conference Proceedings (OSTI)

A3: Investigation on Co-combustion Kinetics of Anthracite Coal and Biomass Char by Thermogravimetric Analysis A4: Analysis of Micro-compositional and...

264

Realizing Technologies for Magnetized Target Fusion  

SciTech Connect

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

265

A 3 MEGAJOULE HEAVY ION FUSION DRIVER  

E-Print Network (OSTI)

Research, Office of Inertia! Fusion, Research Division ofA 3 MEGAJOULE HEAVY ION FUSION DRIVER* A. Faltens, E. Hoyer,Research, Office of Inertial Fusion, Research Division of

Faltens, A.

2010-01-01T23:59:59.000Z

266

NUCLEAR FUSION doi:10.1088/0029-5515/50/1/014004  

E-Print Network (OSTI)

Fusion energy research began in the early 1950s as scientists worked to harness the awesome power of the atom for peaceful purposes. There was early optimism for a quick solution for fusion energy as there had been for fission. However, this was soon tempered by reality as the difficulty of producing and confining fusion fuel at temperatures of 100 million ? C in the laboratory was appreciated. Fusion research has followed two main paths inertial confinement fusion and magnetic confinement fusion. Over the past 50 years, there has been remarkable progress with both approaches, and now each has a solid technical foundation that has led to the construction of major facilities that are aimed at demonstrating fusion energy producing plasmas. PACS numbers: 52.55.?s, 52.57.?z, 28.52.?s, 89.30.Jj (Some figures in this article are in colour only in the electronic version) 1. Introductionfusion energy prior to 1958 The 1950s were a period of rapid progress and high expectations in science and technology. Nuclear weapons were advanced with the first fusion assisted nuclear weapons being tested in 1952. Peaceful uses of nuclear energy in

Dale Meade

2009-01-01T23:59:59.000Z

267

Low-density hydrocarbon foams for laser fusion targets: Progress report, 1987  

SciTech Connect

This report describes progress made in the development of direct-drive hydrocarbon foam targets for laser inertial confinement fusion during 1987. The foam materials are polystyrene, resorcinol-formaldehyde, carbonized resorcinol-formaldehyde, and cellulose acetate. The processes for making the foams, their properties, characterization techniques, and the relationship of their properties to target specifications are presented. Progress in the creation and testing of prototype targets is also described.

Haendler, B.L.; Buckley, S.R.; Chen, C.; Cook, A.R.; Cook, R.C.; Hair, L.M.; Kong, F.M.; Kramer, H.D.; Letts, S.A.; Overturf, G.E. III

1988-06-01T23:59:59.000Z

268

Reviewers Comments on the 5th Symposium and the Status of Fusion Research 2003  

DOE Green Energy (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

269

Method and apparatus to produce and maintain a thick, flowing, liquid lithium first wall for toroidal magnetic confinement DT fusion reactors  

DOE Patents (OSTI)

A system for forming a thick flowing liquid metal, in this case lithium, layer on the inside wall of a toroid containing the plasma of a deuterium-tritium fusion reactor. The presence of the liquid metal layer or first wall serves to prevent neutron damage to the walls of the toroid. A poloidal current in the liquid metal layer is oriented so that it flows in the same direction as the current in a series of external magnets used to confine the plasma. This current alignment results in the liquid metal being forced against the wall of the toroid. After the liquid metal exits the toroid it is pumped to a heat extraction and power conversion device prior to being reentering the toroid.

Woolley, Robert D. (Hillsborough, NJ)

2002-01-01T23:59:59.000Z

270

Comparison of electric and magnetic quadrupole focusing for the low energy end of an induction-linac-ICF (Inertial-Confinement-Fusion) driver  

SciTech Connect

This report compares two physics designs of the low energy end of an induction linac-ICF driver: one using electric quadrupole focusing of many parallel beams followed by transverse combining; the other using magnetic quadrupole focusing of fewer beams without beam combining. Because of larger head-to-tail velocity spread and a consequent rapid current amplification in a magnetic focusing channel, the overall accelerator size of the design using magnetic focusing is comparable to that using electric focusing.

Kim, C.H.

1987-04-01T23:59:59.000Z

271

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

Science Conference Proceedings (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

272

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

SciTech Connect

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

273

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)

+ cannels, K(Ca), and has a single-channel conductance of an intermediate size. Later studies showed Department of Biological Science; 3 Department of Mathematics and Programs in Molecular Biophysics+ concentration is determined by Ca2+ influx and pumping through the plasma membrane, and cycling of Ca2

274

TWO IMPORTANT FUSION PROCESSES CREATING THE CONDITIONS FOR FUSION  

NLE Websites -- All DOE Office Websites (Extended Search)

IMPORTANT FUSION PROCESSES CREATING THE CONDITIONS FOR FUSION F u s i o n Physics of a Fundamental Energy Source C o n f i n e m e n t Q u a l i t y , n τ ( m - 3 s ) 1970-75 1990s 1975-80 1980s Ion Temperature (K) 10 21 10 20 10 19 10 18 10 17 10 6 10 7 10 8 10 9 Inertial Magnetic Expected reactor regime Expected reactor regime Useful Nuclear Masses (The electron's mass is 0.000549 u.) Label Species Mass (u*) n ( 1 n) neutron 1.008665 p ( 1 H) proton 1.007276 D ( 2 H) deuteron 2.013553 T ( 3 H) triton 3.015500 3 He helium-3 3.014932 α ( 4 He) helium-4 4.001505 * 1 u = 1.66054 x 10 -27 kg = 931.466 MeV/c 2 Nuclear Mass (u) B i n d i n g E n e r g y P e r N u c l e o n ( M e V ) 1 200 150 100 50 10 0 5 62 Ni Fusion Reactions Release Energy Fission Reactions Release Energy EXPERIMENTAL RESULTS IN FUSION RESEARCH Fusion requires high tempera- ture plasmas confined long enough at high density

275

How much laser power can propagate through fusion plasma?  

E-Print Network (OSTI)

Propagation of intense laser beams is crucial for inertial confinement fusion, which requires precise beam control to achieve the compression and heating necessary to ignite the fusion reaction. The National Ignition Facility (NIF), where fusion will be attempted, is now under construction. Control of intense beam propagation may be ruined by laser beam self-focusing. We have identified the maximum laser beam power that can propagate through fusion plasma without significant self-focusing and have found excellent agreement with recent experimental data, and suggest a way to increase that maximum by appropriate choice of plasma composition with implication for NIF designs. Our theory also leads to the prediction of anti-correlation between beam spray and backscatter and suggests the indirect control of backscatter through manipulation of plasma ionization state or acoustic damping.

Pavel M. Lushnikov; Harvey A. Rose

2005-12-30T23:59:59.000Z

276

Initiation of long, free-standing Z-discharges by CO2 laser gas heating  

E-Print Network (OSTI)

inertial confine- ment fusion reactor was impossible due toa repetitively operated fusion reactor guiding struc- tures

2004-01-01T23:59:59.000Z

277

Multiple excitation regenerative amplifier inertial confinement system  

DOE Patents (OSTI)

The invention relates to apparatus and methods for producing high intensity laser radiation generation which is achieved through an optical amplifier-storage ring design. One or two synchronized, counterpropagating laser pulses are injected into a regenerative amplifier cavity and amplified by gain media which are pumped repetitively by electrical or optical means. The gain media excitation pulses are tailored to efficiently amplify the laser pulses during each transit. After the laser pulses have been amplified to the desired intensity level, they are either switched out of the cavity by some switch means, as for example an electro-optical device, for any well known laser end uses, or a target means may be injected into the regenerative amplifier cavity in such a way as to intercept simultaneously the counterpropagating laser pulses. One such well known end uses to which this invention is intended is for production of high density and temperature plasmas suitable for generating neutrons, ions and x-rays and for studying matter heated by high intensity laser radiation. 11 figs.

George, V.E.; Haas, R.A.; Krupke, W.F.; Schlitt, L.G.

1980-05-27T23:59:59.000Z

278

Multiple excitation regenerative amplifier inertial confinement system  

DOE Patents (OSTI)

The invention relates to apparatus and methods for producing high intensity laser radiation generation which is achieved through an optical amplifier-storage ring design. One or two synchronized, counterpropagating laser pulses are injected into a regenerative amplifier cavity and amplified by gain media which are pumped repetitively by electrical or optical means. The gain media excitation pulses are tailored to efficiently amplify the laser pulses during each transit. After the laser pulses have been amplified to the desired intensity level, they are either switched out of the cavity by some switch means, as for example an electro-optical device, for any well known laser end uses, or a target means may be injected into the regenerative amplifier cavity in such a way as to intercept simultaneously the counterpropagating laser pulses. One such well known end uses to which this invention is intended is for production of high density and temperature plasmas suitable for generating neutrons, ions and x-rays and for studying matter heated by high intensity laser radiation.

George, Victor E. (Livermore, CA); Haas, Roger A. (Pleasanton, CA); Krupke, William F. (Pleasanton, CA); Schlitt, Leland G. (Livermore, CA)

1980-01-01T23:59:59.000Z

279

Engineering Challenges in Antiproton Triggered Fusion Propulsion  

SciTech Connect

During the last decade antiproton triggered fusion propulsion has been investigated as a method for achieving high specific impulse, high thrust in a nuclear pulse propulsion system. In general the antiprotons are injected into a pellet containing fusion fuel with a small amount of fissionable material (i.e., an amount less than the critical mass) where the products from the fission are then used to trigger a fusion reaction. Initial calculations and simulations indicate that if magnetically insulated inertial confinement fusion is used that the pellets should result in a specific impulse of between 100,000 and 300,000 seconds at high thrust. The engineering challenges associated with this propulsion system are significant. For example, the antiprotons must be precisely focused. The pellet must be designed to contain the fission and initial fusion products and this will require strong magnetic fields. The fusion fuel must be contained for a sufficiently long time to effectively release the fusion energy, and the payload must be shielded from the radiation, especially the excess neutrons emitted, in addition to many other particles. We will review the recent progress, possible engineering solutions and the potential performance of these systems.

Cassenti, Brice [Department. of Engineering and Science, Rensselaer Polytechnic Institute, 275 Windsor Avenue, Hattford, CT 06120 (United States); Kammash, Terry [Nuclear Engineering Department, University of Michigan, Ann Arbor, MI 48109 (United States)

2008-01-21T23:59:59.000Z

280

: Fusion Wall Development Research by Neutron Depth ...  

Science Conference Proceedings (OSTI)

... nano-sized cavities with the theory that the ... Formation, Transaction of America Nuclear Society Summer ... in an Inertial Fusion Energy Reactor, Nucl. ...

2012-11-16T23:59:59.000Z

Note: This page contains sample records for the topic "inertial confinement fusion" 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

Negative Halogen Ions for Fusion Applications  

DOE Green Energy (OSTI)

Over the past quarter century, advances in hydrogen negative ion sources have extended the usable range of hydrogen isotope neutral beams to energies suitable for large magnetically confined fusion devices. Recently, drawing upon this experience, negative halogen ions have been proposed as an alternative to positive ions for heavy ion fusion drivers in inertial confinement fusion, because electron accumulation would be prevented in negative ion beams, and if desired, the beams could be photo-detached to neutrals. This paper reports the results of an experiment comparing the current density and beam emittance of Cl+ and Cl- extracted from substantially ion-ion plasmas with that of Ar+ extracted from an ordinary electron-ion plasma, all using the same source, extractor, and emittance scanner. At similar discharge conditions, the Cl- current was typically 85 90% of the positive chlorine current, with an e-/ Cl- ratio as low as seven without grid magnets. The Cl- was as much as 76% of the Ar+ current from a discharge with the same RF drive. The minimum normalized beam emittance and inferred ion temperatures of Cl+, Cl-, and Ar+ were all similar, so the current density and optical quality of Cl- appear as suitable for heavy ion fusion driver applications as a positive noble gas ion of similar mass. Since F, I, and Br should all behave similarly in an ion source, they should also be suitable as driver beams.

Grisham, L.R.; Kwan, J.W.; Hahto, S.K.; Hahto, S.T.; Leung, K.N.; Westenskow, G.

2006-01-01T23:59:59.000Z

282

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

NLE Websites -- All DOE Office Websites (Extended Search)

General Atomics (GA) Fusion News: A New Spin on Understanding Plasma Confinement American Fusion News Category: General Atomics (GA) Link: General Atomics (GA) Fusion News: A New...

283

High Current Ion Sources and Injectors for Heavy Ion Fusion  

E-Print Network (OSTI)

2001). [40] L.R. Grisham, Fusion Sci. & Tech. 43, 191, (Symp. on Heavy Ion Inertial Fusion, Princeton, New Jersey,Sept. 6-9, 1995; in Fusion Engineering and Design, 32-33,

Kwan, Joe W.

2005-01-01T23:59:59.000Z

284

Heavy ion fusion--Using heavy ions to make electricity  

E-Print Network (OSTI)

in Proc. of the Inertial Fusion Science and ApplicationsP. Abbott, P. F. Peterson, Fusion Science and Technology 44March 1520, 2004 Heavy Ion Fusion Using Heavy Ions to Make

Celata, C.M.

2004-01-01T23:59:59.000Z

285

Nuclear fusion advances  

Science Conference Proceedings (OSTI)

The last decade has seen advances in the shaping and confinement of plasmas, and in approaches to noninductive current drive. Here, the author presents an overview of nuclear fusion advances between 1983-93 examining: fusion milestones; plasma shaping; ...

W. Sweet

1994-02-01T23:59:59.000Z

286

Spherical torus fusion reactor  

DOE Patents (OSTI)

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

Martin Peng, Y.K.M.

1985-10-03T23:59:59.000Z

287

Induction Linac Systems Experiments for heavy ion fusion  

Science Conference Proceedings (OSTI)

The Lawrence Berkeley Laboratory and the Lawrence Livermore National Laboratory propose to build at LBL the Induction Linac Systems Experiments (ILSE), the next logical step toward the eventual goal of a heavy ion induction accelerator powerful enough to implode or drive inertial confinement fusion targets. Though much smaller than a driver, ILSE will be at full driver scale in several important parameters. Nearly all accelerator components and beam manipulations required for a driver will be tested. It is expected that ILSE will be built in stages as funds and technical progress allow. The first stage, called Elise will include all of the electrostatic quadrupole focused parts of ILSE.

Herrmannsfeldt, W.B. [Stanford Linear Accelerator Center, Menlo Park, CA (United States); Bangerter, R.O. [Lawrence Berkeley Lab., CA (United States). Accelerator and Fusion Research Div.

1994-06-01T23:59:59.000Z

288

Laboratory for Laser Energetics annual report, 1 October 1991--30 September 1992. Inertial Fusion Program and National Laser Users Facility Program  

Science Conference Proceedings (OSTI)

This is an annual report covering research progress on laser fusion and the OMEGA Upgrade design and development. In laser fusion, line-spectroscopy methods were demonstrated to be useful in diagnosing the core temperature and densities of polymer-shell targets; a theoretical analysis of nonlocal heat transport effects on filamentation of light in plasmas confirms that the principle mechanism driving filamentation is kinetic thermal rather than ponderomotive; a new method (spatial beam deflection) to produce laser pulses of arbitrary shape was developed; laser-plasma x-ray emission was measured using photodiode arrays; experiments on long-scale-length plasmas have shown that smoothing by spectral dispersion has proven effective in reducing Raman scattering; a method for increasing the gas-retention time of polymer shell targets was developed by overcoating them with aluminum. Experiments relating to the OMEGA Upgrade are described.

Not Available

1993-01-01T23:59:59.000Z

289

Laser fusion driven breeder design study. Final report  

Science Conference Proceedings (OSTI)

The results of the Laser Fusion Breeder Design Study are given. This information primarily relates to the conceptual design of an inertial confinement fusion (ICF) breeder reactor (or fusion-fission hybrid) based upon the HYLIFE liquid metal wall protection concept developed at Lawrence Livermore National Laboratory. The blanket design for this breeder is optimized to both reduce fissions and maximize the production of fissile fuel for subsequent use in conventional light water reactors (LWRs). When the suppressed fission blanket is compared with its fast fission counterparts, a minimal fission rate in the blanket results in a unique reactor safety advantage for this concept with respect to reduced radioactive inventory and reduced fission product decay afterheat in the event of a loss-of-coolant-accident.

Berwald, D.H.; Massey, J.V.

1980-12-01T23:59:59.000Z

290

Role of atomic collisions in fusion  

SciTech Connect

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

291

AFRD - Fusion Energy Science  

NLE Websites -- All DOE Office Websites (Extended Search)

Heavy Ion Fusion Virtual National Laboratory Heavy Ion Fusion Virtual National Laboratory AFRD - Fusion Energy Sciences AFRD - Home Fusion - Home HIF-VNL Website Ion Beam Technology Group website Artist's conception of a heavy ion fusion power plant Artist's conception of an IFE powerplant We further inertial fusion energy as a future power source, primarily through R&D on heavy-ion induction accelerators. Our program is part of a "Virtual National Laboratory," headquartered in AFRD, that joins us with Lawrence Livermore National Laboratory and the Princeton Plasma Physics Laboratory in close collaboration on inertial fusion driven by beams of heavy ions. The related emergent science of high-energy-density physics (HEDP) has become a major focus. For further synergy, we have combined forces with the former Ion Beam

292

Argonne Accelerator Institute  

NLE Websites -- All DOE Office Websites (Extended Search)

HEARTHFIRE - Inertial Confinement Fusion (1974 - 1980 at Argonne) At Argonne, the concept of using intense pulsed proton or deuteron beams for inertial confinement fusion (ICF) of...

293

Snowmass 2002: The Fusion Energy Sciences Summer Study  

SciTech Connect

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

294

Scientific problems of fusion, solved and to be solved  

SciTech Connect

A good comprehensive review of research progress and the present status of research on inertial confinement, tokamak device, and magnetic mirror technology is given. (MOW)

Post, R.F.

1977-11-04T23:59:59.000Z

295

IFE thick liquid wall chamber dynamics: Governing mechanisms and modeling and experimental capabilities  

E-Print Network (OSTI)

Metal-Wall Inertial Fusion Reactors " Nuclear Eng. andI A n Inertial Confinement Fusion Reactor," Ph.D. thesis,in Inertial Confinement Fusion Reactors," Ph.D. thesis,

2005-01-01T23:59:59.000Z

296

Slow liner fusion  

SciTech Connect

{open_quotes}Slow{close_quotes} liner fusion ({approximately}10 ms compression time) implosions are nondestructive and make repetitive ({approximately} 1 Hz) pulsed liner fusion reactors possible. This paper summarizes a General Atomics physics-based fusion reactor study that showed slow liner feasibility, even with conservative open-line axial magnetic field confinement and Bohm radial transport.

Shaffer, M.J.

1997-08-01T23:59:59.000Z

297

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

E-Print Network (OSTI)

W. M. Sharp, and D. R. Welch, Fusion Sci. Technol. 44, 266implosion in heavy ion fusion,"Laser Part. Beam 24, 359-Heavy-Ion-Beam Inertial Fusion at High Coupling Efficiency.

Seidl, P.A.

2013-01-01T23:59:59.000Z

298

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 net electric efficiency, and low neutron-induced radioactivity. The invention includes a compact blanket design and method and apparatus for obtaining energy utilizing the compact blanket.

Lasche, G.P.

1983-09-29T23:59:59.000Z

299

Inertial Fusion Energy and its Materials Challenges  

Science Conference Proceedings (OSTI)

Symposium, IOMMMS Global Materials Forum: Materials in a Green Economy: An International ... Recent Development of Materials for Green Energy in Korea.

300

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

E-Print Network (OSTI)

Fusion Engineering and Design 81 (2006) 1639­1645 Thermo-mechanical analysis of a micro laser (HAPL) program goal is to develop a laser inertial fusion reactor using a solid first wall (FW). The FW of the inertial fusion energy (IFE) chamber is exposed to high energy photon, particle

Ghoniem, Nasr M.

Note: This page contains sample records for the topic "inertial confinement fusion" 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

Hot electron confinement in a microwave heated spindle cusp  

SciTech Connect

The Plasma Research Laboratory at the University of Missouri-Columbia was established with awards from the McDonnel Douglas Foundation, ARMCO, Union Electric, Black and Vetch, Kansas City Power and Light, the National Science Foundation, and DOE. The Plasma Research Lab's major effort is the Missouri Magnetic Mirror (MMM or M{sup 3}) Project. The technical goals of MMM have been (1) Diagnostic Development, (2) Plasma Physics in the Cusp geometry, (3) plasma-wall interactions, (4) impurity effects in a steady-state plasma, and (5) Development of Diagnostics for use in harsh plasma processing environments. The other major goal of MMM has remained providing a facility for hands-on training in experimental plasma physics. The major experimental facility of MMM is the MMM Modified Experiment (M4X). Other research efforts in the Plasma Research Laboratory include small efforts in cold fusion, toroidal magnetic confinement, and inertial confinement and a potentially major effort in direct conversion of nuclear energy.

Prelas, M.A.

1991-08-01T23:59:59.000Z

302

Reviewers Comments on the 5th Symposium and the Status of Fusion Research 2003  

SciTech Connect

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

303

Contact Us | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Inertial Confinement Fusion Contact Us Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Inertial Confinement...

304

Facilities | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Inertial Confinement Fusion Facilities Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Inertial Confinement...

305

Mirror Confinement Systems: project summaries  

SciTech Connect

This report contains descriptions of the projects supported by the Mirror Confinement Systems (MCS) Division of the Office of Fusion Energy. The individual project summaries were prepared by the principal investigators, in collaboration with MCS staff office, and include objectives and milestones for each project. In addition to project summaries, statements of Division objectives and budget summaries are also provided.

1980-07-01T23:59:59.000Z

306

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

307

Computational and experimental investigation of magnetized target fusion  

SciTech Connect

In Magnetized Target Fusion (MTF), a preheated and magnetized target plasma is hydrodynamically compressed to fusion conditions. Because the magnetic field suppresses losses by electron thermal conduction in the fuel during the target implosion heating process, the compression may be over a much longer time scale than in traditional inertial confinement fusion (ICF). Bigger targets and much lower initial target densities than in ICF can be used, reducing radiative energy losses. Therefore, ``liner-on-plasma`` compressions, driven by relatively inexpensive electrical pulsed power, may be practical. Potential MTF target plasmas must meet minimum temperature, density, and magnetic field starting conditions, and must remain relatively free of high-Z radiation-cooling-enhancing contaminants. At Los Alamos National Laboratory, computational and experimental research is being pursued into MTF target plasmas, such as deuterium-fiber-initiated Z-pinches, and the Russian-originated MAGO plasma. In addition, liner-on-plasma compressions of such target plasmas to fusion conditions are being computationally modeled, and experimental investigation of such heavy liner implosions has begun. The status of the research will be presented.

Sheehey, P.T.; Guzik, J.A.; Kirkpatrick, R.C.; Lindemuth, I.R.; Scudder, D.W.; Shlachter, J.S.; Wysocki, F.J.

1996-07-01T23:59:59.000Z

308

Component framework for coupled integrated fusion plasma simulation  

Science Conference Proceedings (OSTI)

Successful simulation of the complex physics that affect magnetically confined fusion plasma remains an important target milestone towards the development of viable fusion energy. Major advances in the underlying physics formulations, mathematical modeling, ... Keywords: components, coupled simulation, framework, fusion

Wael R. Elwasif; David E. Bernholdt; Lee A. Berry; Donald B. Batchelor

2007-10-01T23:59:59.000Z

309

Method and Apparatus to Produce and Maintain a thick, flowing, Liquid Lithium first wall for Toroidal Magnetic Confinement DT Fusion Reactors  

DOE Patents (OSTI)

A system for forming a thick flowing liquid metal, in this case lithium, layer on the inside wall of a toroid containing the plasma of a deuterium-tritium fission reactor. The presence of the liquid metal layer or first wall serves to prevent neutron damage to the walls of the toroid. A poloidal current in the liquid metal layer is oriented so that it flows in the same direction as the current in a series of external magnets used to confine the plasma. This current alignment results in the liquid metal being forced against the wall of the toroid. After the liquid metal exits the toroid it is pumped to a heat extraction and power conversion device prior to being reentering the toroid.

Woolley, Robert D.

1998-10-21T23:59:59.000Z

310

Parametic Study of the current limit within a single driver-scale transport beam line of an induction Linac for Heavy Ion Fusion  

E-Print Network (OSTI)

illumination geometry, Nuclear Fusion [25] M. Tabak and D.radiator target for inertial fusion driven from two sidesPlasma Phys. Control. Fusion [27] D. A. Callahan-Miller and

Prost, Lionel Robert

2007-01-01T23:59:59.000Z

311

Fusion reactor design | Princeton Plasma Physics Lab  

NLE Websites -- All DOE Office Websites (Extended Search)

used magnetic confinement device is the tokamak, followed by the stellarator. PPPL and ITER: Lab teams support the world's largest fusion experiment with leading-edge ideas and...

312

The National Ignition Facility and the Path to Fusion Energy  

SciTech Connect

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

313

Particle beam fusion research at Sandia National Laboratories  

SciTech Connect

Sandia`s Particle Beam Fusion Program is investigating several driver options, based on pulsed power technology, with the goal of demonstrating a practical ignitor for Inertial Confinement Fusion (ICF) Reactors. The interrelated aspects of power conditioning and compression, beam-target interaction, and target ignition are being studied. The issues of efficiency, reliability and multiple pulse capability are being integrated into the program to provide a viable approach to an experimental power reactor. On a shorter time scale the authors expect to derive important military-related benefits from attendant research and facility development. The two most important advantages of pulsed power driven fusion are the inherent low cost and high efficiency of high current particle accelerators. However, comparison of the relative merits of particle beams and focused laser beams must include many other factors such as beam transport, and target coupling, as well as target design and fabrication. These issues are being investigated to determine if the perceived practical benefits of particle beam fusion can indeed be realized. The practical considerations are exemplified in a comparison of the leading ICF drivers. The plan being followed by Sandia involves using the Electron Beam Fusion Accelerator (EBFA) to meet three objectives by 1985: significant burn using EBFA 1, net energy gain based on an upgrade of EBFA to the 2 megajoule (MJ) level (EBFA 2), and demonstration of a single module of EBFA 2 operated in the repetitive pulse mode. These goals are dependent, of course, on success in solving several key technical problems under investigation. If these technical problems can be solved, then practical applications to fusion power could be considered. The potential for these applications has been studied using economic models that allow one to derive the cost of power based on various assumptions.

1978-12-31T23:59:59.000Z

314

Development and characterization of an inertial electrostatic confinement thruster.  

E-Print Network (OSTI)

??This present work is focused on the development of an IEC thruster based on the jet mode of operation. Discharge characteristics of the IEC jet (more)

Krishnamurthy, Akshata

2012-01-01T23:59:59.000Z

315

Particle beam fusion progress report for 1989  

Science Conference Proceedings (OSTI)

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

Sweeney, M.A. [ed.] [Sandia National Labs., Albuquerque, NM (United States). Pulsed Power Sciences Center

1994-08-01T23:59:59.000Z

316

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

317

Neutron detectors for fusion reaction-rate measurements  

SciTech Connect

Fusion reactions in an inertial-confinement fusion (ICF) target filled with deuterium or a deuterium/tritium fuel release nearly monoenergetic neutrons. Because most the neutrons leave the compressed target without collision, they preserve reaction-rate information as they travel radially outward from their point of origin. Three fast, neutron detector techniques, each capable of measuring the fusion reaction-rate of ICF targets, have been demonstrated. The most advanced detector is based on the fast rise-time of a commercial plastic scintillator material (BC-422) which acts as a neutron-to-light converter. Signals, which are recorded with a fast optical streak camera, have a resolution of 25 ps. Good signals can be recorded for targets producing only 5 x 10{sup 7} DT neutrons. Two other detectors use knock-on collisions between neutrons and protons in a thin polyethylene (CH{sub 2}) converter. In one, the converter is placed in front of the photocathode of an x-ray streak camera. Recoil protons pass through the photocathode and knock out electrons which are accelerated and deflected to produce a signal. Resolutions < 25 ps are possible. In the other, the converter is placed in front of a microchannel plate (MCP) with a gated microstrip. Recoil protons eject electrons from the gold layer forming the microstrip. If a gate pulse is present, the signal is amplified. Present gate times are about 80 ps.

Lerche, R.A.; Phillion, D.W.; Landen, O.L.; Murphy, T.J. [Lawrence Livermore National Lab., CA (United States); Jaanimagi, P.A. [Univ. of Rochester, NY (United States). Laboratory for Laser Energetics

1994-02-10T23:59:59.000Z

318

Some applications of mirror-generated electric potentials to alternative fusion concepts  

Science Conference Proceedings (OSTI)

Transient electrical potentials can be generated in plasmas by utilizing impulsive mirror-generated forces acting on the plasma electrons together with ion inertia to cause momentary charge imbalance. In the Mirrortron such potentials are generated by applying a rapidly rising (tens of nanoseconds) localized mirror field to the central region of a hot-electron plasma confined between static mirrors. Because of the loss-cone nature of the electron distribution the sudden appearance of the pulsed mirror tends to expel electrons, whereas the ion density remains nearly constant. The quasi-neutrality condition then operates to create an electrical potential the equipotential surfaces of which can be shown theoretically to be congruent with surfaces of constant B. An alternative way of generating transient potentials is to apply a pulse of high-power microwaves to a plasma residing on a magnetic field with a longitudinal gradient. This technique resembles one employed in the Pleiade experiments. At gigawatt power levels, such as those produced by a Free Electron Laser, the production of very high transient potentials is predicted. Fusion-relevant applications of these ideas include heavy-ion drivers for inertial fusion, and the possibility of employing these techniques to enhance the longitudinal confinement of fusion plasmas in multiple-mirror systems. 23 refs., 3 figs.

Post, R.F.

1990-09-24T23:59:59.000Z

319

An updated point design for heavy ion fusion  

E-Print Network (OSTI)

et al. , HYLIFE-II: A Molten-Salt Inertial Fusion Energybeen selected to be the molten salt flinabe (LiNaBeF 4 ),the target and the molten-salt jets. However, simulations

2002-01-01T23:59:59.000Z

320

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

Note: This page contains sample records for the topic "inertial confinement fusion" from the National Library of EnergyBeta (NLEBeta).
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321

Inertial energy storage device  

DOE Patents (OSTI)

The inertial energy storage device of the present invention comprises a composite ring formed of circumferentially wound resin-impregnated filament material, a flanged hollow metal hub concentrically disposed in the ring, and a plurality of discrete filament bandsets coupling the hub to the ring. Each bandset is formed of a pair of parallel bands affixed to the hub in a spaced apart relationship with the axis of rotation of the hub being disposed between the bands and with each band being in the configuration of a hoop extending about the ring along a chordal plane thereof. The bandsets are disposed in an angular relationship with one another so as to encircle the ring at spaced-apart circumferential locations while being disposed in an overlapping relationship on the flanges of the hub. The energy storage device of the present invention has the capability of substantial energy storage due to the relationship of the filament bands to the ring and the flanged hub.

Knight, Jr., Charles E. (Knoxville, TN); Kelly, James J. (Oak Ridge, TN); Pollard, Roy E. (Powell, TN)

1978-01-01T23:59:59.000Z

322

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

SciTech Connect

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

323

Self-sustained Inertial Oscillations  

Science Conference Proceedings (OSTI)

The authors describe a self-sustaining baroclinic inertial oscillation whose energy source rests in a uniform horizontal temperature gradient. This energy is released through the agency of a stratification-dependent mixing law that is meant to ...

Joseph Pedlosky; Henry Stommel

1993-08-01T23:59:59.000Z

324

Magnetic Confinement Fusion Science Status and Challenges  

E-Print Network (OSTI)

by centrifugal force of particles moving along curved magnetic field plasma magnetic field Centrifugal force #12;Centrifugal force in a torus centrifugal force magnetic field #12;Stability theory is highly developed disruption to occur, Control its behavior by rapid injection of jet of neutral gas Causes energy

325

Analytic criteria for shock ignition of fusion reactions in a central hot spot  

Science Conference Proceedings (OSTI)

Shock ignition is an inertial confinement fusion scheme where the ignition conditions are achieved in two steps. First, the DT shell is compressed at a low implosion velocity creating a central core at a low temperature and a high density. Then, a strong spherical converging shock is launched before the fuel stagnation time. It increases the central pressure and ignites the core. It is shown in this paper that this latter phase can be described analytically by using a self-similar solution to the equations of ideal hydrodynamics. A high and uniformly distributed pressure in the hot spot can be created thus providing favorable conditions for ignition. Analytic ignition criteria are obtained that relate the areal density of the compressed core with the shock velocity. The conclusions of the analytical model are confirmed in full hydrodynamic simulations.

Ribeyre, X.; Tikhonchuk, V. T.; Breil, J.; Lafon, M.; Le Bel, E. [Centre Lasers Intenses et Applications, Universite Bordeaux 1-CEA-CNRS, Talence 33405 (France)

2011-10-15T23:59:59.000Z

326

An important challenge in magnetic fusion research is to obtain...  

NLE Websites -- All DOE Office Websites (Extended Search)

in a stationary plasma that is compatible with the engineering requirements of a fusion reactor. The triggering of edge transport barriers at the boundary of confined...

327

Magnetic fusion reactor economics  

SciTech Connect

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

Krakowski, R.A.

1995-12-01T23:59:59.000Z

328

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

329

Confinement Of Pure Ion Plasma In A Cylindrical Current Sheet  

E-Print Network (OSTI)

j ?B force. An equilibrium calculation using a relativistic, 1-D, cold-fluid model shows: the confine- ment of non-neutral ion plasmas that are adequately dense for controlled thermonu- clear fusion limit? Conventional magnetic fusion devices contain quasi-neutral plasmas in a toroidal or linear

330

Visit the National Academies Press online and register for... Instant access to free PDF downloads of titles from the  

E-Print Network (OSTI)

(2013) Assessment of Inertial Confinement Fusion Targets Panel on the Assessment of Inertial Confinement Fusion Targets; Board on Physics and Astronomy; Board on Energy and Environmental Systems; Division rights reserved. Assessment of Inertial Confinement Fusion Targets 1 2 3 4 5 6 7 8 9 10 11 12

331

Inertial Particle Dynamics in a Hurricane  

E-Print Network (OSTI)

The motion of inertial (i.e., finite-size) particles is analyzed in a three-dimensional unsteady simulation of Hurricane Isabel. As established recently, the long-term dynamics of inertial particles in a fluid is governed ...

Sapsis, Themistoklis

332

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

333

Fusion Policy Advisory Committee (FPAC)  

Science Conference Proceedings (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

334

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

E-Print Network (OSTI)

et al. , "HYLIFE-II: A Molten-Salt Inertial Fusion EnergyL. Vay 3 Vallecitos Molten Salt Research Princeton PlasmaPower Corp. , Vallecitos Molten Salt Research, and Voss

Seidl, P.A.

2013-01-01T23:59:59.000Z

335

Ion Rings for Magnetic Fusion  

Science Conference Proceedings (OSTI)

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

Greenly, John, B.

2005-07-31T23:59:59.000Z

336

Estimated radiactive and shock loading of fusion reactor armor  

SciTech Connect

Inertial confinement fusion (ICF) is of interest as a source of neutrons for proliferation-resistant and high burn-up fission reactor designs. ICF is a transient process, each implosion leading to energy release over a short period, with a continuous series of ICF operations needed to drive the fission reactor. ICF yields energy in the form of MeV-range neutrons and ions, and thermal x-rays. These radiations, particularly the thermal x-rays, can deposit a pulse of energy in the wall of the ICF chamber, inducing loading by isochoric heating (i.e. at constant volume before the material can expand) or by ablation of material from the surface. The explosion of the hot ICF system, and the compression of any fill material in the chamber, may also result in direct mechanical loading by a blast wave (decaying shock) reaching the chamber wall. The chamber wall must be able to survive the repetitive loading events for long enough for the reactor to operate economically. It is thus necessary to understand the loading induced by ICF systems in possible chamber wall designs, and to predict the response and life time of the wall. Estimates are given for the loading induced in the wall armor of the fusion chamber caused by ablative thermal radiation from the fusion plasma and by the hydrodynamic shock. Taking a version of the LIFE design as an example, the ablation pressure was estimated to be {approx}0.6 GPa with an approximately exponential decay with time constant {approx}0.6 ns. Radiation hydrodynamics simulations suggested that ablation of the W armor should be negligible.

Swift, D C

2008-11-25T23:59:59.000Z

337

Fusion power production in TFTR  

SciTech Connect

Up to 9.3 MW of fusion power has been produced from deuterium-tritium (DT) fusion reactions in the Tokamak Fusion Test Reactor (TFTR). The total fusion yield from a single plasma pulse has reached 6.5 MJ. The experiments in TFTR with deuterium-tritium plasmas fueled and heated by neutral beam injection span wide ranges in plasma and operating conditions. Through the use of lithium pellet conditioning to control the edge recycling, the plasma confinement in TFTR has been improved to the point where the stability of the plasma to pressure driven modes is limiting the fusion power for plasma currents up to 2.5 MA. The central energy and fusion power densities in these plasmas are comparable to those expected in a thermalized DT reactor, such as ITER.

Bell, M.G.; Budny, R.V. [Princeton Univ., NJ (United States). Plasma Physics Lab.; Barnes, C.W. [Los Alamos National Lab., NM (United States)] [and others

1994-11-01T23:59:59.000Z

338

Status of Safety and Environmental Activities in the US Fusion Program  

Science Conference Proceedings (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

339

Status of Safety and Environmental Activities in the US Fusion Program  

SciTech Connect

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

340

Method of controlling fusion reaction rates  

DOE Patents (OSTI)

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

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

1988-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "inertial confinement fusion" 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

Comments on open-ended magnetic systems for fusion  

SciTech Connect

Differentiating characteristics of magnetic confinement systems having externally generated magnetic fields that are open'' are listed and discussed in the light of their several potential advantages for fusion power systems. It is pointed out that at this stage of fusion research high-Q'' (as deduced from long energy confinement times) is not necessarily the most relevant criterion by which to judge the potential of alternate fusion approaches for the economic generation of fusion power. An example is given of a hypothetical open-geometry fusion power system where low-Q operation is essential to meeting one of its main objectives (low neutron power flux).

Post, R.F.

1990-09-24T23:59:59.000Z

342

Spherical torus fusion reactor  

DOE Patents (OSTI)

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

Peng, Yueng-Kay M. (Oak Ridge, TN)

1989-01-01T23:59:59.000Z

343

Massachusetts Institute of Technology, Plasma Fusion Center, Technical Research Programs  

SciTech Connect

A review is given of the technical programs carried out by the Plasma Fusion Center. The major divisions of work areas are applied plasma research, confinement experiments, fusion technology and engineering, and fusion systems. Some objectives and results of each program are described. (MOW)

1980-08-01T23:59:59.000Z

344

INERTIAL FUSION DRIVEN BY INTENSE HEAVY-ION BEAMS  

E-Print Network (OSTI)

National Ignition Facility (NIF) is beginning to testdriver, like that used in NIF, is well- suited. However,use in power plants. The NIF neodymium-glass lasers are less

Sharp, W. M.

2011-01-01T23:59:59.000Z

345

Peter A. Norreys Professor of Inertial Fusion Science,  

E-Print Network (OSTI)

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 (CH or Be) NIF 1MJ Indirect Drive Design Laser energy = 1MJ Fuel kinetic energy = 10kJ Total

346

The high current transport experiment for heavy ion inertial fusion  

E-Print Network (OSTI)

accelconf/l02/PAPERS/TU483.PDF SNS parameters list, ReportScience, November 2003, SNS-100000000- PL0001-R10, http://the Spallation Neutron Source (SNS) Front End [29,30,31] and

2004-01-01T23:59:59.000Z

347

INERTIAL FUSION DRIVEN BY INTENSE HEAVY-ION BEAMS  

E-Print Network (OSTI)

inner wall instead of molten-salt walls [10], necessitatingof molten Li 2 BeF 4 (FLiBe) or other lithium salt to

Sharp, W. M.

2011-01-01T23:59:59.000Z

348

ARIES INERTIAL FUSION CHAMBER ASSESSMENT M. S. Tillack, F. Najmabadi  

E-Print Network (OSTI)

Washington, DC 20375 L. M. Waganer Boeing Company P.O. Box 516 St Louis, MO 63166-0516 and the ARIES Team to define design windows and explore in detail the tradeoffs for various chamber concepts. The work to better understand fundamental tradeoffs, characterize design windows and offer additional guidance to R

California at San Diego, University of

349

Homodyne target tracking for direct drive laser inertial fusion  

E-Print Network (OSTI)

systems use a single frequency of light in both reference and measurement legs of the interferometer and can operate independent of laserLasers Office: 408-546-4546 Mobile: 408-506-7504 Email correspondence with Hovemere Ltd, makers of precise wavelength measurement systems

Spalding, Jon David

2009-01-01T23:59:59.000Z

350

Inertial fusion energy target injection, tracking, and beam pointing  

Science Conference Proceedings (OSTI)

Several cryogenic targets must be injected each second into a reaction chamber. Required target speed is about 100 m/s. Required accuracy of the driver beams on target is a few hundred micrometers. Fuel strength is calculated to allow acceleration in excess of 10,000 m/s{sup 2} if the fuel temperature is less than 17 K. A 0.1 {mu}m thick dual membrane will allow nearly 2,000 m/s{sup 2} acceleration. Acceleration is gradually increased and decreased over a few membrane oscillation periods (a few ms), to avoid added stress from vibrations which could otherwise cause a factor of two decrease in allowed acceleration. Movable shielding allows multiple targets to be in flight toward the reaction chamber at once while minimizing neutron heating of subsequent targets. The use of multiple injectors is recommended for redundancy which increases availability and allows a higher pulse rate. Gas gun, rail gun, induction accelerator, and electrostatic accelerator target injection devices are studied, and compared. A gas gun is the preferred device for indirect-drive targets due to its simplicity and proven reliability. With the gas gun, the amount of gas required for each target (about 10 to 100 mg) is acceptable. A revolver loading mechanism is recommended with a cam operated poppet valve to control the gas flow. Cutting vents near the muzzle of the gas gun barrel is recommended to improve accuracy and aid gas pumping. If a railgun is used, we recommend an externally applied magnetic field to reduce required current by an order of magnitude. Optical target tracking is recommended. Up/down counters are suggested to predict target arrival time. Target steering is shown to be feasible and would avoid the need to actively point the beams. Calculations show that induced tumble from electrostatically steering the target is not excessive.

Petzoldt, R.W.

1995-03-07T23:59:59.000Z

351

Apparatus for producing cryogenic inertially driven fusion targets  

SciTech Connect

A new technique for producing uniform layers of solid DT on microballoon surfaces. Local heating of the target, typically by means of a focused laser, within an isothermal freezing cell containing a low pressure cryogenic exchange gas such as helium, vaporizes the DT fuel contained within the microballoon. Removal of the laser heating source causes the DT gas to rapidly condense and freeze in a layer which exhibits a good degree of uniformity.

Miller, John R. (Los Alamos, NM)

1981-01-01T23:59:59.000Z

352

Methods and apparatus for producing cryogenic inertially driven fusion targets  

SciTech Connect

A new technique for producing uniform layers of solid DT on microballoon surfaces. Local heating of the target, typically by means of a focused laser, within an isothermal freezing cell containing a low pressure cryogenic exchange gas such as helium, vaporizes the DT fuel. Removal of the laser heating source causes the DT gas to rapidly condense and freeze in a layer which exhibits a good degree of uniformity.

Miller, John R. (Los Alamos, NM)

1981-01-01T23:59:59.000Z

353

Laser fusion experiments at LLL  

Science Conference Proceedings (OSTI)

These notes present the experimental basis and status for laser fusion as developed at LLL. Two other chapters, one authored by K.A. Brueckner and the other by C. Max, present the theoretical implosion physics and laser plasma interaction physics. The notes consist of six sections. The first is an introductory section which provides some of the history of inertial fusion and a simple explanation of the concepts involved. The second section presents an extensive discussion of diagnostic instrumentation used in the LLL Laser Fusion Program. The third section is a presentation of laser facilities and capabilities at LLL. The purpose here is to define capability, not to derive how it was obtained. The fourth and fifth sections present the experimental data on laser-plasma interaction and implosion physics. The last chapter is a short projection of the future.

Ahlstrom, H.G.

1980-06-16T23:59:59.000Z

354

Is the Coriolis Force Really Responsible for the Inertial Oscillation?  

Science Conference Proceedings (OSTI)

It is demonstrated that the inertial oscillation is not produced exclusively by inertial forces, and that the inertial oscillation appears as oscillatory motion even when viewed from a nonrotating frame of reference. The component of true ...

Dale R. Durran

1993-11-01T23:59:59.000Z

355

Fusion Simulation Project Workshop Report  

E-Print Network (OSTI)

for tokamak operation, disruptions, energetic particle stability and confinement, turbulent transport to performance projections and operational limits. The Fusion Simulation Project, which will focus on tokamak and transient heat loads on the divertor . . . . . 17 2.1.3 Tritium migration and impurity transport

Gropp, Bill

356

Midterm Summary of Japan-US Fusion Cooperation Program TITAN  

SciTech Connect

Japan-US cooperation program TITAN (Tritium, Irradiation and Thermofluid for America and Nippon) started in April 2007 as 6-year project. This is the summary report at the midterm of the project. Historical overview of the Japan-US cooperation programs and direction of the TITAN project in its second half are presented in addition to the technical highlights. Blankets are component systems whose principal functions are extraction of heat and tritium. Thus it is crucial to clarify the potentiality for controlling heat and tritium flow throughout the first wall, blanket and out-of-vessel recovery systems. The TITAN project continues the JUPITER-II activity but extends its scope including the first wall and the recovery systems with the title of 'Tritium and thermofluid control for magnetic and inertial confinement systems'. The objective of the program is to clarify the mechanisms of tritium and heat transfer throughout the first-wall, the blanket and the heat/tritium recovery systems under specific conditions to fusion such as irradiation, high heat flux, circulation and high magnetic fields. Based on integrated models, the breeding, transfer, inventory of tritium and heat extraction properties will be evaluated for some representative liquid breeder blankets and the necessary database will be obtained for focused research in the future.

Muroga, Takeo [National Institute for Fusion Science, Toki, Japan; Sze, Dai-Kai [University of California, San Diego; Sokolov, Mikhail [ORNL; Katoh, Yutai [ORNL; Stoller, Roger E [ORNL

2011-01-01T23:59:59.000Z

357

Pinch-based thermonuclear D{sup 3}He fusion driven by a femtosecond laser  

Science Conference Proceedings (OSTI)

A new thermonuclear-fusion concept involving inertial-magnetic confinement on the basis of a high-current Z pinch and employing a powerful femtosecond laser is proposed. The possibility of implementing this scheme for the production of energy in a compressed liner consisting of a D{sup 3}He fuel contained inside a {sup 9}Be shell is considered. It is shown that the concerted effect of the electric discharge along the liner and an ultrashort laser shot at one of the liner endfaces provides preconditions for an ultrafast ignition of a small portion of the fuel and for the onset of the propagation of a burn wave along a plasma filament. Under favorable conditions, this system provides an energy gain of about 50, the contribution of the neutron component here being only a few percent. Basic mechanisms of the heating and confinement of the D{sup 3}He fuel are discussed along with the problem of convenient gamma-ray plasma diagnostics.

Kukulin, V. I.; Voronchev, V. T. [Moscow State University, Skobeltsyn Institute of Nuclear Physics (Russian Federation)

2010-08-15T23:59:59.000Z

358

Decay of a Near-Inertial Wave  

Science Conference Proceedings (OSTI)

The decay of a downward propagating near-inertial wave was observed over four days. During this short period, the energy of the near-inertial wave decreased by 70%. The shear layers produced by the wave were regions of enhanced turbulent ...

Dave Hebert; J. N. Moum

1994-11-01T23:59:59.000Z

359

Confinement and heating of a deuterium-tritium plasma  

Science Conference Proceedings (OSTI)

The Tomamak Fusion Test reactor has performed initial high-power experiments with the plasma fueled with nominally equal densities of deuterium and tritium. Compared to pure deuterium plasmas, the energy stored in the electron and ions increased by [similar to]20%. These increases indicate improvements in confinement associated with the use of tritium and possibly heating of electrons by [alpha] particles created by the D-T fusion reactions.

Hawryluk, R.J.; Adler, H.; Alling, P.; Ancher, C.; Anderson, H.; Anderson, J.L.; Ashcroft, D.; Barnes, C.W.; Barnes, G.; Batha, S.; Bell, M.G.; Bell, R.; Bitter, M.; Blanchard, W.; Bretz, N.L.; Budny, R.; Bush, C.E.; Camp, R.; Caorlin, M.; Cauffman, S.; Chang, Z.; Cheng, C.Z.; Collins, J.; Coward, G.; Darrow, D.S.; DeLooper, J.; Duong, H.; Dudek, L.; Durst, R.; Efthimion, P.C.; Ernst, D.; Fisher, R.; Fonck, R.J.; Fredrickson, E.; Fromm, N.; Fu, G.Y.; Furth, H.P.; Gentile, C.; Gorelenkov, N.; Grek, B.; Grisham, L.R.; Hammett, G.; Hanson, G.R.; Heidbrink, W.; Herrmann, H.W.; Hill, K.W.; Hosea, J.; Hsuan, H.; Janos, A.; Jassby, D.L.; Jobes, F.C.; Johnson, D.W.; Johnson, L.C.; Kamperschroer, J.; Kugel, H.; Lam, N.T.; LaMarche, P.H.; Loughlin, M.J.; LeBlanc, B.; Leonard, M.; Levinton, F.M.; Machuzak, J.; Mansfield, D.K.; Martin, A.; Mazzucato, E.; Majeski, R.; Marmar, E.; McChesney, J.; McCormack, B.; McCune, D.C.; McGuire, K.M.; McKee, G.; Meade, D.M.; Medley, S.S.; Mikkelsen, D.R.; Muelle

1994-05-30T23:59:59.000Z

360

Regarding Confinement Resonances  

NLE Websites -- All DOE Office Websites (Extended Search)

Regarding Confinement Resonances Regarding Confinement Resonances Regarding Confinement Resonances Print Wednesday, 27 July 2011 00:00 When an atom is encapsulated inside a hollow spherical carbon buckyball, the complex is called an "endofullerene." Theoretically, if the atom is an unreactive noble gas like xenon, it should be centered within the cage. If one or more of the atom's electrons are boosted out of the cage by an x-ray photon, the electron waves may be transmitted through or reflected off the carbon cage, giving rise to an interference effect similar to waves in a water tank. These so-called "confinement resonances" were predicted theoretically a decade ago but have never been observed. In the first experimental test of this theory, members of an international team led by Ronald Phaneuf, University of Nevada, and working at ALS Beamline 10.0.1 produced and isolated xenon endofullerenes and observed confinement resonances.

Note: This page contains sample records for the topic "inertial confinement fusion" 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

Regarding Confinement Resonances  

NLE Websites -- All DOE Office Websites (Extended Search)

Regarding Confinement Resonances Print Regarding Confinement Resonances Print When an atom is encapsulated inside a hollow spherical carbon buckyball, the complex is called an "endofullerene." Theoretically, if the atom is an unreactive noble gas like xenon, it should be centered within the cage. If one or more of the atom's electrons are boosted out of the cage by an x-ray photon, the electron waves may be transmitted through or reflected off the carbon cage, giving rise to an interference effect similar to waves in a water tank. These so-called "confinement resonances" were predicted theoretically a decade ago but have never been observed. In the first experimental test of this theory, members of an international team led by Ronald Phaneuf, University of Nevada, and working at ALS Beamline 10.0.1 produced and isolated xenon endofullerenes and observed confinement resonances.

362

Regarding Confinement Resonances  

NLE Websites -- All DOE Office Websites (Extended Search)

Regarding Confinement Resonances Print Regarding Confinement Resonances Print When an atom is encapsulated inside a hollow spherical carbon buckyball, the complex is called an "endofullerene." Theoretically, if the atom is an unreactive noble gas like xenon, it should be centered within the cage. If one or more of the atom's electrons are boosted out of the cage by an x-ray photon, the electron waves may be transmitted through or reflected off the carbon cage, giving rise to an interference effect similar to waves in a water tank. These so-called "confinement resonances" were predicted theoretically a decade ago but have never been observed. In the first experimental test of this theory, members of an international team led by Ronald Phaneuf, University of Nevada, and working at ALS Beamline 10.0.1 produced and isolated xenon endofullerenes and observed confinement resonances.

363

Regarding Confinement Resonances  

NLE Websites -- All DOE Office Websites (Extended Search)

Regarding Confinement Resonances Print Regarding Confinement Resonances Print When an atom is encapsulated inside a hollow spherical carbon buckyball, the complex is called an "endofullerene." Theoretically, if the atom is an unreactive noble gas like xenon, it should be centered within the cage. If one or more of the atom's electrons are boosted out of the cage by an x-ray photon, the electron waves may be transmitted through or reflected off the carbon cage, giving rise to an interference effect similar to waves in a water tank. These so-called "confinement resonances" were predicted theoretically a decade ago but have never been observed. In the first experimental test of this theory, members of an international team led by Ronald Phaneuf, University of Nevada, and working at ALS Beamline 10.0.1 produced and isolated xenon endofullerenes and observed confinement resonances.

364

Regarding Confinement Resonances  

NLE Websites -- All DOE Office Websites (Extended Search)

off the carbon cage, giving rise to an interference effect similar to waves in a water tank. These so-called "confinement resonances" were predicted theoretically a decade ago but...

365

A Stratified Model of the Inertial Recirculation  

Science Conference Proceedings (OSTI)

An inertial gyre with characteristics very similar to the recirculation observed in eddy-resolving general circulation models is obtained with a simple, analytically tractable, two-layer model. The recirculating gyre is contained in a box of ...

Paola Cessi

1988-04-01T23:59:59.000Z

366

Inertial measurement via dynamics of trapped particles  

E-Print Network (OSTI)

We describe theoretical and practical aspects of the particle trap as an inertial sensor. The insight motivating this approach is that a trapped particle acts like a mass on a spring, but the restoring forces are provided ...

Post, E. Rehmi, 1966-

2003-01-01T23:59:59.000Z

367

Apparatus for magnetic and electrostatic confinement of plasma  

DOE Patents (OSTI)

An apparatus and method for containing plasma and forming a Field Reversed Configuration (FRC) magnetic topology are described in which plasma ions are contained magnetically in stable, non-adiabatic orbits in the FRC. Further, the electrons are contained electrostatically in a deep energy well, created by tuning an externally applied magnetic field. The simultaneous electrostatic confinement of electrons and magnetic confinement of ions avoids anomalous transport and facilitates classical containment of both electrons and ions. In this configuration, ions and electrons may have adequate density and temperature so that upon collisions ions are fused together by nuclear force, thus releasing fusion energy. Moreover, the fusion fuel plasmas that can be used with the present confinement system and method are not limited to neutronic fuels only, but also advantageously include advanced fuels.

Rostoker, Norman; Binderbauer, Michl

2013-06-11T23:59:59.000Z

368

23rd IAEA Fusion Energy Conference: Summary Of Sessions EX/C and ICC  

Science Conference Proceedings (OSTI)

An overview is given of recent experimental results in the areas of innovative confinement concepts, operational scenarios and confinement experiments as presented at the 2010 IAEA Fusion Energy Conference. Important new findings are presented from fusion devices worldwide, with a strong focus towards the scientific and technical issues associated with ITER and W7-X devices, presently under construction.

Richard J. Hawryluk

2011-01-05T23:59:59.000Z

369

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

SciTech Connect

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

370

Wellbore inertial directional surveying system  

DOE Patents (OSTI)

A wellbore inertial directional surveying system for providing a complete directional survey of an oil or gas well borehole to determine the displacement in all three directions of the borehole path relative to the well head at the surface. The information generated by the present invention is especially useful when numerous wells are drilled to different geographical targets from a single offshore platform. Accurate knowledge of the path of the borehole allows proper well spacing and provides assurance that target formations are reached. The tool is lowered down into a borehole on an electrical cable. A computer positioned on the surface communicates with the tool via the cable. The tool contains a sensor block which is supported on a single gimbal, the rotation axis of which is aligned with the cylinder axis of the tool and, correspondingly, the borehole. The gyroscope measurement of the sensor block rotation is used in a null-seeking servo loop which essentially prevents rotation of the sensor block about the gimbal axis. Angular rates of the sensor block about axes which are perpendicular to te gimbal axis are measured by gyroscopes in a manner similar to a strapped-down arrangement. Three accelerometers provide acceleration information as the tool is lowered within the borehole. The uphole computer derives position information based upon acceleration information and angular rate information. Kalman estimation techniques are used to compensate for system errors. 25 figures.

Andreas, R.D.; Heck, G.M.; Kohler, S.M.; Watts, A.C.

1982-09-08T23:59:59.000Z

371

Wellbore inertial directional surveying system  

DOE Patents (OSTI)

A wellbore inertial directional surveying system for providing a complete directional survey of an oil or gas well borehole to determine the displacement in all three directions of the borehole path relative to the well head at the surface. The information generated by the present invention is especially useful when numerous wells are drilled to different geographical targets from a single off-shore platform. Accurate knowledge of the path of the borehole allows proper well spacing and provides assurance that target formations are reached. The tool is lowered down into a borehole on the electrical cable. A computer positioned on the surface communicates with the tool via the cable. The tool contains a sensor block which is supported on a single gimbal, the rotation axis of which is aligned with the cylinder axis of the tool and, correspondingly, the borehole. The gyroscope measurement of the sensor block rotation is used in a null-seeking servo loop which essentially prevents rotation of the sensor block aboutthe gimbal axis. Angular rates of the sensor block about axes which are perpendicular to the gimbal axis are measured by gyroscopes in a manner similar to a strapped-down arrangement. Three accelerometers provide acceleration information as the tool is lowered within the borehole. The uphole computer derives position information based upon acceleration information and anular rate information. Kalman estimation techniques are used to compensate for system errors.

Andreas, Ronald D. (Albuquerque, NM); Heck, G. Michael (Albuquerque, NM); Kohler, Stewart M. (Albuquerque, NM); Watts, Alfred C. (Albuquerque, NM)

1991-01-01T23:59:59.000Z

372

Core transport studies in fusion devices  

E-Print Network (OSTI)

The turbulence in magnetically confined fusion plasmas has important and non-trivial effects on the quality of the energy confinement. These effects are hard to make a quantitative assessment of analytically. The problem investigated in this article is the transport of energy and particles, in particular impurities, in a Tokamak plasma. Impurities from the walls of the plasma vessel cause energy losses if they reach the plasma core. It is therefore important to understand the transport mechanisms to prevent impurity accumulation and minimize losses. This is an area of research where turbulence plays a major role and is intimately associated with the performance of future fusion reactors, such as ITER.

Strand, Pr; Nordman, Hans

2010-01-01T23:59:59.000Z

373

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

374

ITER: The International Thermonuclear Experimental Reactor and the Nuclear Weapons Proliferation Implications of Thermonuclear-Fusion Energy Systems  

E-Print Network (OSTI)

This paper contains two parts: (I) A list of points highlighting the strategic-political and militarytechnical 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 foster further nuclear proliferation throughout the world. The safety and environmental problems related to the operation of largescale fusion facilities such as ITER (which contain massive amounts of hazardous and/or radioactive materials such as tritium, lithium, and beryllium, as well as neutron-activated structural materials) are not addressed in this paper.

Andr Gsponer; Jean-pierre Hurni

2004-01-01T23:59:59.000Z

375

2011 Confined Space Program Update  

NLE Websites -- All DOE Office Websites (Extended Search)

Confined Space Entry Program Update Confined Space Entry Program Update IMPORTANT: After reading this document, click the "Get Course Credit" link at the bottom of the page. You will then log in to the EHS training system using your LDAP to get course credit. LBNL's confined space entry program was substantially improved this year. Several new features have been included which improve overall safety for Confined Space Entrants and better align the confined space entry program with the OSHA requirements. As an Activity Lead, Confined Space Entrant or Entry Supervisor, you should be aware of the following: We improved the procedures for safely working in confined spaces. Please review the new Chapter 34 in Publication 3000. Additionally, we have a new planning tool known as the confined space inventory which is a registry of LBNL's confined spaces, their potential hazards and safe work procedures unique to a particular confined space.

376

Fusion breeder  

SciTech Connect

The fusion breeder is a fusion reactor designed with special blankets to maximize the transmutation by 14 MeV neutrons of uranium-238 to plutonium or thorium to uranium-233 for use as a fuel for fission reactors. Breeding fissile fuels has not been a goal of the US fusion energy program. This paper suggests it is time for a policy change to make the fusion breeder a goal of the US fusion program and the US nuclear energy program. The purpose of this paper is to suggest this policy change be made and tell why it should be made, and to outline specific research and development goals so that the fusion breeder will be developed in time to meet fissile fuel needs.

Moir, R.W.

1982-02-22T23:59:59.000Z

377

Fusion Website  

NLE Websites -- All DOE Office Websites (Extended Search)

Fusion Basics Fusion Intro Fusion Education Research DIII-D Internal Site Opportunities Virtual DIII-D Collaborators Countries Physics Eng Physics Operations Diagnostics Computing IFT IFT Site ITER ITER Site FDF Theory Collaborators Conferences GA-Hosted Room Reservations Fusion Meetings Plasma Publications Presentations Images Brochures Posters Movies Corporate General Atomics Products Visitor GA Fusion Hotels Internal Users GA Internal Site DIII-D General Experimental Science Experimental Science Home 2013 Experimental Campaign Burning Plasma Physics Dynamics & Control Boundary and Pedestal ELM Control Operations Diagnostics Computing Support Visitors DIII-D Web Access Help IFT ITER-GA Theory Research Highlights Personnel Links Policies Safety Comp Support Trouble Ticket Eng/Design Fusion Webmail Phone Book

378

Fusion breeder  

SciTech Connect

The fusion breeder is a fusion reactor designed with special blankets to maximize the transmutation by 14 MeV neutrons of uranium-238 to plutonium or thorium to uranium-233 for use as a fuel for fission reactors. Breeding fissile fuels has not been a goal of the US fusion energy program. This paper suggests it is time for a policy change to make the fusion breeder a goal of the US fusion program and the US nuclear energy program. The purpose of this paper is to suggest this policy change be made and tell why it should be made, and to outline specific research and development goals so that the fusion breeder will be developed in time to meet fissile fuel needs.

Moir, R.W.

1982-04-20T23:59:59.000Z

379

Fusion Implementation  

SciTech Connect

If a fusion DEMO reactor can be brought into operation during the first half of this century, fusion power production can have a significant impact on carbon dioxide production during the latter half of the century. An assessment of fusion implementation scenarios shows that the resource demands and waste production associated with these scenarios are manageable factors. If fusion is implemented during the latter half of this century it will be one element of a portfolio of (hopefully) carbon dioxide limiting sources of electrical power. It is time to assess the regional implications of fusion power implementation. An important attribute of fusion power is the wide range of possible regions of the country, or countries in the world, where power plants can be located. Unlike most renewable energy options, fusion energy will function within a local distribution system and not require costly, and difficult, long distance transmission systems. For example, the East Coast of the United States is a prime candidate for fusion power deployment by virtue of its distance from renewable energy sources. As fossil fuels become less and less available as an energy option, the transmission of energy across bodies of water will become very expensive. On a global scale, fusion power will be particularly attractive for regions separated from sources of renewable energy by oceans.

J.A. Schmidt

2002-02-20T23:59:59.000Z

380

Bold Step by the World to Fusion Energy: ITER  

E-Print Network (OSTI)

HISTORY OF INT'L COLLABORATION · 1958: WORLD-WIDE DECLASSIFICATION OF MAGNETICALLY CONFINED FUSIONV TEMPERATURES [20 MILLION DEGREES F] · 1970'S: OIL CRISIS PROPELS MAJOR INVESTMENT IN FUSION RESEARCH FACILITIES HISTORY AND KEY FUSION SCIENCE ADVANCES 85 90 95 00 05 85 90 95 00 05 CDA EDA EDA -ext US out AT

Note: This page contains sample records for the topic "inertial confinement fusion" 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

Assisted fusion  

E-Print Network (OSTI)

A model of nuclear fusion consisting of a wave packet impinging into a well located between square one dimensional barriers is treated analytically. The wave function inside the well is calculated exactly for the assisted tunneling induced by a perturbation mimicking a constant electric field with arbitrary time dependence. Conditions are found for the enhancement of fusion.

German Klbermann

2009-10-19T23:59:59.000Z

382

Fusion devices  

SciTech Connect

Three types of thermonuclear fusion devices currently under development are reviewed for an electric utilities management audience. Overall design features of laser fusion, tokamak, and magnetic mirror type reactors are described and illustrated. Thrusts and trends in current research on these devices that promise to improve performance are briefly reviewed. Twenty photographs and drawings are included. (RME)

Fowler, T.K.

1977-10-11T23:59:59.000Z

383

On the Inertial Stability f the Equatorial Middle Atmosphere  

Science Conference Proceedings (OSTI)

A theory of inertial instability on the equatorial beta-plane is developed with application to the inertial stability of the equatorial middle atmosphere at the solstices. It is shown that the stability of this region depends primarily on two ...

Timothy J. Dunkerton

1981-11-01T23:59:59.000Z

384

Fusion power and the environment  

SciTech Connect

Environmental characteristics of conceptual fusion-reactor systems based on magnetic confinement are examined quantitatively, and some comparisons with fission systems are made. Fusion, like all other energy sources, will not be completely free of environmental liabilities, but the most obvious of these-- tritium leakage and activation of structural materials by neutron bombardment-- are susceptible to significant reduction by ingenuity in choice of materials and design. Large fusion reactors can probably be designed so that worst-case releases of radioactivity owing to accident or sabotage would produce no prompt fatalities in the public. A world energy economy relying heavily on fusion could make heavy demands on scarce nonfuel materials, a topic deserving further attention. Fusion's potential environmental advantages are not entirely ''automatic'', converting them into practical reality will require emphasis on environmental characteristics throughout the process of reactor design and engineering. The central role of environmental impact in the long-term energy dilemma of civilization justifies the highest priority on this aspect of fusion. (auth)

Holdren, J.P.; Fowler, T.K.; Post, R.F.

1975-06-01T23:59:59.000Z

385

COLLABORATIVE: FUSION SIMULATION PROGRAM  

SciTech Connect

New York University, Courant Institute of Mathematical Sciences, participated in the ???¢????????Fusion Simulation Program (FSP) Planning Activities???¢??????? [http://www.pppl.gov/fsp], with C.S. Chang as the institutional PI. FSP???¢????????s mission was to enable scientific discovery of important new plasma phenomena with associated understanding that emerges only upon integration. This requires developing a predictive integrated simulation capability for magnetically-confined fusion plasmas that are properly validated against experiments in regimes relevant for producing practical fusion energy. Specific institutional goal of the New York University was to participate in the planning of the edge integrated simulation, with emphasis on the usage of large scale HPCs, in connection with the SciDAC CPES project which the PI was leading. New York University successfully completed its mission by participating in the various planning activities, including the edge physics integration, the edge science drivers, and the mathematical verification. The activity resulted in the combined report that can be found in http://www.pppl.gov/fsp/Overview.html. Participation and presentations as part of this project are listed in a separation file.

Chang, Choong Seock

2012-06-05T23:59:59.000Z

386

Fusion research: the past is prologue  

SciTech Connect

At this juncture fusion research can be viewed as being at a turning point, a time to review its past and to imagine its future. Today, almost 50 years since the first serious attempts to address the daunting problem of achieving controlled fusion, we have both an opportunity and a challenge. Some predictions place fusion research today at a point midway between its first inception and its eventual maturation - in the middle of the 21st century - when fusion would become a major source of energy. Our opportunity therefore is to assess what we have learned from 50 years of hard work and use that knowledge as a starting point for new and better approaches to solving the fusion problem. Our challenge is to prove the "50 more years" prophesy wrong, by finding ways to shorten the time when fusion power becomes a reality. The thesis will be advanced that in the magnetic confinement approach to fusion open-ended magnetic confinement geometries offer much in responding to the challenge. A major advantage of open systems is that, owing to their theoretically and experimentally demonstrated ability to suppress plasma instabilities of both the MHD and the high-frequency wave-particle variety, the confinement becomes predictable from "classical," i.e., Fokker-Planck-type analysis. In a time of straitened budgetary circumstances for magnetic fusion research now being faced in the United States, the theoretical tractability of mirror-based systems is a substantial asset. In pursuing this avenue it is also necessary to keep an open mind as to the forms that mirror-based fusion power plants might take. For example, one can look to the high-energy physics community for a possible model: This community has shown the feasibility of constructing large and complex particle accelerators using superconducting magnets, vacuum chambers and complicated particle-handling technology, housed in underground tunnels that are 20 or more kilometers long. In the paper examples of mirror-based fusion power systems resembling long "linear colliders" will be discussed. It is not the intent of this paper to present detailed proposals for next-generation experiments in magnetic fusion research, but rather to encourage a return to the ambiance of an earlier era of fusion research, when innovative thinking and a spirit of scientific adventure prevailed. In that way we can realistically build a new era of fusion research, an era that would be firmly undergirded by the scientific and technological foundation that was laid in fusion's first half-century.

Post, R F

1998-10-14T23:59:59.000Z

387

Fusion Energy Division annual progress report, period ending December 31, 1988  

Science Conference Proceedings (OSTI)

This report discusses the following topics on fusion research: toroidal confinement activities; atomic physics and plasma diagnostics development; fusion theory and computation; plasma technology; superconducting magnet development; advanced systems program; fusion materials research; neutron transport; and management services, quality assurance, and safety.

Sheffield, J.; Berry, L.A.; Saltmarsh, M.J.

1990-02-01T23:59:59.000Z

388

Simulation of Geomagnetic/Inertial Integrated Navigation System  

Science Conference Proceedings (OSTI)

In order to optimize the algorithm of geomagnetic/inertial integrated navigation, we establish platform of geomagnetic/inertial integrated navigation System, and study the geomagnetic matching location approach based on ICCP algorithm and MSD algorithm, ... Keywords: Geomagnetic/Inertial Integrated Navigation, Geomagnetic Matching, ICCP algorithm, MSD algorithm, Kalman filter

Zhou Yingying; Zhang Yanshun; Guo Lei

2011-01-01T23:59:59.000Z

389

Reconfigurable Assembly Station for Precision Manufacture of Nuclear Fusion Ignition Targets  

SciTech Connect

This paper explores the design and testing of a reconfigurable assembly station developed for assembling the inertial confinement nuclear fusion ignition targets that will be fielded in the National Ignition Facility (NIF) laser [1]. The assembly station, referred to as the Flexible Final Assembly Machine (FlexFAM) and shown in Figure 1, is a companion system to the earlier Final Assembly Machine (FAM) [2]. Both machines consist of a manipulator system integrated with an optical coordinate measuring machine (OCMM). The manipulator system has six groups of stacked axis used to manipulate the millimeter-sized target components with submicron precision, and utilizes the same force and torque feedback sensing as the FAM. Real-time dimensional metrology is provided by the OCMM's vision system and through-the-lens (TTL) laser-based height measuring probe. The manually actuated manipulator system of the FlexFAM provides a total of thirty degrees-of-freedom to the target components being assembled predominantly in a cubic centimeter work zone.

Castro, C; Montesanti, R C; Taylor, J S; Hamza, A V; Dzenitis, E G

2009-08-11T23:59:59.000Z

390

Nonlinear inertial Alfven wave in dusty plasmas  

SciTech Connect

Solitary inertial Alfven wave in the presence of positively and negatively charged dust particles is studied. It is found that electron density dips are formed in the super Alfvenic region and wave amplitude is increased for the case of negatively charged dust particles in comparison with positively charged dust particles in electron-ion plasmas.

Mahmood, S. [Theoretical Plasma Physics Division, P.O. Nilore Islamabad 44000 (Pakistan); National Center for Physics, Shadra Valley, Quaid-i-Azam University Islamabad 44000 (Pakistan); Saleem, H. [National Center for Physics, Shadra Valley, Quaid-i-Azam University Islamabad 44000 (Pakistan)

2011-11-29T23:59:59.000Z

391

LIFE: The Case for Early Commercialization of Fusion Energy  

SciTech Connect

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

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

2010-11-30T23:59:59.000Z

392

Facilities | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Inertial Confinement Fusion Inertial Confinement Fusion Facilities Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test, and Evaluation > Office of Inertial Confinement Fusion > Facilities Facilities Office of Inertial Confinement Fusion, Facilities ICF operates a set of world-class experimental facilities to create HEDP conditions and to obtain quantitative data in support of its numerous stockpile stewardship-related activities. To learn about three high energy experimental facilities and two small lasers that provide ICF capabilities, select the links below. National Ignition Facility, Lawrence Livermore National Laboratory OMEGA and OMEGA EP, University of Rochester Laboratory for Laser Energetics Z Machine, Sandia National Laboratories

393

Basic ReseaRch DiRections  

National Nuclear Security Administration (NNSA)

Beams FRM Faraday Rotation Measure GA General Atomics GRB Gamma Ray Burst HED High Energy Density IAW Ion Acoustic Wave ICF Inertial Confinement Fusion ISAC Isotope...

394

STATEMENT OF CONSIDERATIONS REQUEST BY CORNING INCORPORATED FOR...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

fused silica transmissive optics utilized in advanced Inertial Confinement Fusion (ICF) laser systems. The present cost of laser optics used in the ICF laser system is between...

395

Z Machine | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test Capabilities and Evaluation > Office of Inertial Confinement Fusion > Facilities > Z...

396

Nike | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test Capabilities and Evaluation > Office of Inertial Confinement Fusion > Facilities > Nike...

397

National Ignition Facility | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test Capabilities and Evaluation > Office of Inertial Confinement Fusion > Facilities >...

398

Target Fabrication Industry Day - September 11, 2013 | National...  

National Nuclear Security Administration (NNSA)

Home > About Us > Our Programs > Defense Programs > Office of Research, Development, Test Capabilities and Evaluation > Office of Inertial Confinement Fusion > Target...

399

John Lindl and Bruce Hammel Lawrence Livermore National Laboratory  

E-Print Network (OSTI)

Advances in Indirect Drive ICF Target Physics Presentation to 20th IAEA Fusion Energy Conference #12;NIF in Inertial Confinement Fusion Inertial Confinement Fusion uses direct or indirect drive to couple driver by cold, dense main fuel Direct Drive Hot spot (10 keV) Cold, dense main fuel (200-1000 g/cm3) Indirect

400

Causality detection and turbulence in fusion plasmas  

E-Print Network (OSTI)

This work explores the potential of an information-theoretical causality detection method for unraveling the relation between fluctuating variables in complex nonlinear systems. The method is tested on some simple though nonlinear models, and guidelines for the choice of analysis parameters are established. Then, measurements from magnetically confined fusion plasmas are analyzed. The selected data bear relevance to the all-important spontaneous confinement transitions often observed in fusion plasmas, fundamental for the design of an economically attractive fusion reactor. It is shown how the present method is capable of clarifying the interaction between fluctuating quantities such as the turbulence amplitude, turbulent flux, and Zonal Flow amplitude, and uncovers several interactions that were missed by traditional methods.

van Milligen, B Ph; Ramisch, M; Estrada, T; Hidalgo, C; Alonso, A

2013-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "inertial confinement fusion" 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

PHYSICS, COMPUTER SCIENCE AND MATHEMATICS DIVISION. ANNUAL REPORT, 1 JAN. - 31 DEC. 1976  

E-Print Network (OSTI)

Ion Beams of a Pellet Fusion Reactor by Quadrupole Doublets.for an inertially confined fusion reactor, work was begun toand A. Paul) TOKAMAK FUSION TEST REACTOR (TFTR) TFTR studies

Authors, Various

2010-01-01T23:59:59.000Z

402

A Pilot Plant: The Fastest Path to Commercial Fusion Energy  

SciTech Connect

Considerable effort has been dedicated to determining the possible properties of a magneticconfinement fusion power plant, particularly in the U.S.1, Europe2 and Japan3. There has also been some effort to detail the development path to fusion energy, particularly in the U.S.4 Only limited attention has been given, in Japan5 and in China6, to the options for a specific device to form the bridge from the International Thermonuclear Experimental Reactor, ITER, to commercial fusion energy. Nor has much attention been paid, since 2003, to the synergies between magnetic and inertial fusion energy development. Here we consider, at a very high level, the possibility of a Qeng ? 1 Pilot Plant, with linear dimensions ~ 2/3 the linear dimensions of a commercial fusion power plant, as the needed bridge. As we examine the R&D needs for such a system we find significant synergies between the needs for the development of magnetic and inertial fusion energy.

Robert J. Goldston

2010-03-03T23:59:59.000Z

403

Dynamic Instruction Fusion  

E-Print Network (OSTI)

SANTA CRUZ DYNAMIC INSTRUCTION FUSION A thesis submitted in4 2.2 Instruction Fusion & Complex10 3.1 Fusion Selection

Lee, Ian

2012-01-01T23:59:59.000Z

404

Minimal fusion systems.  

E-Print Network (OSTI)

??We define minimal fusion systems in a way that every non-solvable fusion system has a section which is minimal. Minimal fusion systems can also be (more)

Henke, Ellen

2010-01-01T23:59:59.000Z

405

Confinement and Stability of Alternate Fusion Concepts Varenna, Italy  

E-Print Network (OSTI)

¥ Axisymmetric ideal MHD ¥ Accurate geometry ¥ Fit to experiment yields magnetic fields, currents, etc. NIMROD o Flux from injector coils Injector flux (private) Divertor Injector flux = 14 mWb Toroidal current The vacuum (bias) field allows operation at l(y) = j||/B ~ lFC (Flux conserver eigenmode). Vacuum Field

406

Optimizing and validating the magnetic confinement approach to fusion  

E-Print Network (OSTI)

opportunities for "Exploratory Plasma Research" (EPR) in the U.S. #12;What is EPR? · "EPR" a recently

407

Universities and the UK Magnetic Confinement Fusion Programme  

E-Print Network (OSTI)

as for DTN, plus a choice of three other modules (eg High Performance Computing; Statistical Data Analysis

408

Challenges Surrounding the Injection and Arrival of Targets at LIFE Fusion Chamber Center  

SciTech Connect

IFE target designers must consider several engineering requirements in addition to the physics requirements for successful target implosion. These considerations include low target cost, high manufacturing throughput, the ability of the target to survive the injection into the fusion chamber and arrive in a condition and physical position consistent with proper laser-target interaction and ease of post-implosion debris removal. This article briefly describes these considerations for the Laser Inertial Fusion-based Energy (LIFE) targets currently being designed.

Miles, R; Spaeth, M; Manes, K; Amendt, P; Tabak, M; Bond, T; Kucheyev, S; Latkowski, J; Loosmore, G; Bliss, E; Baker, K; Bhandarkar, S; Petzoldt, R; Alexander, N; Tillack, M; Holdener, D

2010-12-01T23:59:59.000Z

409

Accelerator & Fusion Research Division: 1993 Summary of activities  

SciTech Connect

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

410

Charge exchange recombination spectroscopy on fusion devices  

Science Conference Proceedings (OSTI)

For fusion, obtaining reliable measurements of basic plasma parameters like ion and electron densities and temperatures is a primary goal. For theory, measurements are needed as a function of time and space to understand plasma transport and confinement with the ultimate goal of achieving economic nuclear fusion power. Electron profile measurements and plasma spectroscopy for the plasma ions are introduced. With the advent of Neutral Beam auxiliary plasma heating, Charge Exchange Recombination Spectroscopy provides accurate and time resolved measurements of the ions in large volume fusion devices. In acknowledgement of Nicol Peacock's role in the development of these techniques, still at the forefront of plasma fusion research, this paper describes the evolution of this diagnostic method.

Duval, B. P. [Centre de Recherches en Physique des Plasmas, EPFL, Lausanne (Switzerland)

2012-05-25T23:59:59.000Z

411

Heating, Confinement and Extrapolation to Reactors  

Science Conference Proceedings (OSTI)

Status of Fusion / Proceedings of the Tenth Carolus Magnus Summer School on Plasma and Fusion Energy Physics

J. Ongena; A. M. Messiaen

412

Rotation studies in fusion plasmas via imaging X-ray crystal spectroscopy  

E-Print Network (OSTI)

The increase in plasma performance associated with turbulence suppression via flow shear in magnetically confined fusion plasmas has been well documented. Currently, the standard methods for both generating and measuring ...

Ince-Cushman, Alexander Charles

2008-01-01T23:59:59.000Z

413

Cold fusion, Alchemist's dream  

SciTech Connect

In this report the following topics relating to cold fusion are discussed: muon catalysed cold fusion; piezonuclear fusion; sundry explanations pertaining to cold fusion; cosmic ray muon catalysed cold fusion; vibrational mechanisms in excited states of D{sub 2} molecules; barrier penetration probabilities within the hydrogenated metal lattice/piezonuclear fusion; branching ratios of D{sub 2} fusion at low energies; fusion of deuterons into {sup 4}He; secondary D+T fusion within the hydrogenated metal lattice; {sup 3}He to {sup 4}He ratio within the metal lattice; shock induced fusion; and anomalously high isotopic ratios of {sup 3}He/{sup 4}He.

Clayton, E.D.

1989-09-01T23:59:59.000Z

414

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

SciTech Connect

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

415

Inertial navigation system for directional surveying  

DOE Green Energy (OSTI)

A Wellbore Inertial Navigation System (WINS) was developed and tested. Developed for directional surveying of geothermal, oil, and gas wells, the system uses gyros and accelerometers to obtain survey errors of less than 10 ft (approx. 3 m) in a 10,000-ft (approx. 300-m) well. The tool, which communicates with a computer at the surface, is 4 in. (approx. 10 cm) in diameter and 20 ft (approx. 6.1 m) long. The concept and hardware is based on a system developed by Sandia for flight vehicles.

Kohler, S.M.

1982-09-01T23:59:59.000Z

416

The Structure of Near-Inertial Waves during Ocean Storms  

Science Conference Proceedings (OSTI)

Current meter data from two sites were analyzed for near-inertial motions generated by storm during the ten-month period of the Ocean Storms Experiment in the northeast Pacific Ocean. The most striking feature of the inertial wave response to ...

Hongbo Qi; Roland A. De Szoeke; Clayton A. Paulson; Charles C. Eriksen

1995-11-01T23:59:59.000Z

417

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 ther...

Howes, G G

2007-01-01T23:59:59.000Z

418

Safeguard Requirements for Fusion Power Plants  

Science Conference Proceedings (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

419

EBT electron energy confinement experiments  

SciTech Connect

Plasma parameters as measured in the EBT-S device are presented together with a description of ECH power modulation techniques applied to investigate the confinement properties of the EBT plasma.

Wilgen, J.B.; Richards, R.K.; Hillis, D.L.; Swain, D.W.; White, T.L.; Peterson, B.G.; Baity, F.W.; Berry, L.A.; Casson, W.H.; Cobble, J.A.

1984-01-01T23:59:59.000Z

420

Tandem mirror plasma confinement apparatus  

DOE Patents (OSTI)

Apparatus and method for confining a plasma in a center mirror cell by use of two end mirror cells as positively charged end stoppers to minimize leakage of positive particles from the ends of the center mirror cell.

Fowler, T. Kenneth (Walnut Creek, CA)

1978-11-14T23:59:59.000Z

Note: This page contains sample records for the topic "inertial confinement fusion" 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.


421

GRAVITATIONAL INSTABILITY OF ROTATING, PRESSURE-CONFINED, POLYTROPIC GAS DISKS WITH VERTICAL STRATIFICATION  

SciTech Connect

We investigate the gravitational instability (GI) of rotating, vertically stratified, pressure-confined, polytropic gas disks using a linear stability analysis as well as analytic approximations. The disks are initially in vertical hydrostatic equilibrium and bounded by a constant external pressure. We find that the GI of a pressure-confined disk is in general a mixed mode of the conventional Jeans and distortional instabilities, and is thus an unstable version of acoustic-surface-gravity waves. The Jeans mode dominates in weakly confined disks or disks with rigid boundaries. On the other hand, when the disk has free boundaries and is strongly pressure confined, the mixed GI is dominated by the distortional mode that is surface-gravity waves driven unstable under their own gravity and thus incompressible. We demonstrate that the Jeans mode is gravity-modified acoustic waves rather than inertial waves and that inertial waves are almost unaffected by self-gravity. We derive an analytic expression for the effective sound speed c{sub eff} of acoustic-surface-gravity waves. We also find expressions for the gravity reduction factors relative to a razor-thin counterpart that are appropriate for the Jeans and distortional modes. The usual razor-thin dispersion relation, after correcting for c{sub eff} and the reduction factors, closely matches the numerical results obtained by solving a full set of linearized equations. The effective sound speed generalizes the Toomre stability parameter of the Jeans mode to allow for the mixed GI of vertically stratified, pressure-confined disks.

Kim, Jeong-Gyu; Kim, Woong-Tae [Center for the Exploration of the Origin of the Universe (CEOU), Astronomy Program, Department of Physics and Astronomy, Seoul National University, Seoul 151-742 (Korea, Republic of); Seo, Young Min; Hong, Seung Soo, E-mail: jgkim@astro.snu.ac.kr, E-mail: wkim@astro.snu.ac.kr, E-mail: seo3919@email.arizona.edu, E-mail: sshong@astro.snu.ac.kr [FPRD, Department of Physics and Astronomy, Seoul National University, Seoul 151-742 (Korea, Republic of)

2012-12-20T23:59:59.000Z

422

Expert Topics | Princeton Plasma Physics Lab  

NLE Websites -- All DOE Office Websites (Extended Search)

AC power Education Emergency planning Engineering Fusion energy Fusion reactor design Fusion roadmapping ITER Inertial confinement fusion International collaborations Laser diagnostics Lithium Magnetic reconnection Nuclear energy Nuclear safety Particle beam dynamics Plasma astrophysics Plasma diagnostics Plasma physics Power system design Power systems Quality assurance STEM Science literacy Stellarators Surface science Sustainability Tokamaks Visiting PPPL History Fusion Basics DOE and Fusion Links Contract Documents Speakers Bureau Tours News Events Research Education Organization Contact Us Overview Learn More AC power Education Emergency planning Engineering Fusion energy Fusion reactor design Fusion roadmapping ITER Inertial confinement fusion International collaborations Laser diagnostics

423

Magnetic and electrostatic confinement of plasma with tuning of electrostatic field  

DOE Patents (OSTI)

A system and method for containing plasma and forming a Field Reversed Configuration (FRC) magnetic topology are described in which plasma ions are contained magnetically in stable, non-adiabatic orbits in the FRC. Further, the electrons are contained electrostatically in a deep energy well, created by tuning an externally applied magnetic field. The simultaneous electrostatic confinement of electrons and magnetic confinement of ions avoids anomalous transport and facilitates classical containment of both electrons and ions. In this configuration, ions and electrons may have adequate density and temperature so that upon collisions they are fused together by nuclear force, thus releasing fusion energy. Moreover, the fusion fuel plasmas that can be used with the present confinement system and method are not limited to neutronic fuels only, but also advantageously include advanced fuels.

Rostoker, Norman (Irvine, CA); Binderbauer, Michl (Irvine, CA); Qerushi, Artan (Irvine, CA); Tahsiri, Hooshang (Irvine, CA)

2008-10-21T23:59:59.000Z

424

Fusion Energy Division annual progress report period ending December 31, 1986  

SciTech Connect

This annual report on fusion energy discusses the progress on work in the following main topics: toroidal confinement experiments; atomic physics and plasma diagnostics development; plasma theory and computing; plasma-materials interactions; plasma technology; superconducting magnet development; fusion engineering design center; materials research and development; and neutron transport. (LSP)

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

1987-10-01T23:59:59.000Z

425

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

SciTech Connect

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

426

Latent Matcher Fusion  

Science Conference Proceedings (OSTI)

Page 1. Latent Matcher Fusion -- Lessons Learned IAI ... 14 Page 15. The Fusion was in Two Steps Step 1 a reduced working candidate list was ...

2012-08-07T23:59:59.000Z

427

Model Comparison in Plasma Energy Confinement Scaling revisited  

SciTech Connect

Already in 1998 we presented on a MaxEnt conference a Bayesian model comparison for the confinement scaling of fusion devices. The reason to visit this field again is an over the years enlarged data basis facilitating new physical insights. We compare up to ten physical models on the basis of the old (low-{beta}) data of the 1998 approach and newly acquired high-{beta} data. This work serves as an example where the prior odds cannot be set constant (as would be the normal procedure) but has to be furnished with physics information.

Preuss, R.; Dinklage, A. [Max-Planck-Institut fuer Plasmaphysik, EURATOM Association, D-85748 Garching (Germany)

2006-11-29T23:59:59.000Z

428

Implicit Methods for the Magnetohydrodynamic Description of Magnetically Confined Plasmas  

SciTech Connect

Implicit algorithms are essential for predicting the slow growth and saturation of global instabilities in todays magnetically confined fusion plasma experiments. Present day algorithms for obtaining implicit solutions to the magnetohydrodynamic (MHD) equations for highly magnetized plasma have their roots in algorithms used in the 1960s and 1970s. However, todays computers and modern linear and non?linear solver techniques make practical much more comprehensive implicit algorithms than were previously possible. Combining these advanced implicit algorithms with highly accurate spatial representations of the vector fields describing the plasma flow and magnetic fields and with improved methods of calculating anisotropic thermal conduction now makes possible simulations of fusion experiments using realistic values of plasma parameters and actual configuration geometry.

S.C. Jardin

2010-09-28T23:59:59.000Z

429

Life Pure Fusion Target Designs: Status and Prospects  

Science Conference Proceedings (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

430

Characterization of the deuteron beam current in a linear accelerator for nuclear-diagnostic calibrations  

E-Print Network (OSTI)

In Inertial Confinement Fusion (ICF) research, passive detection systems are often required in several applications for observing fusion-product spectra from an ICF-capsule implosion. These detection devices can be calibrated ...

Denis, Daniel (Daniel B.)

2009-01-01T23:59:59.000Z

431

CORRELATIONS IN CONFINED QUANTUM PLASMAS  

Science Conference Proceedings (OSTI)

This is the final report for the project 'Correlations in Confined Quantum Plasmas', NSF-DOE Partnership Grant DE FG02 07ER54946, 8/1/2007 - 7/30/2010. The research was performed in collaboration with a group at Christian Albrechts University (CAU), Kiel, Germany. That collaboration, almost 15 years old, was formalized during the past four years under this NSF-DOE Partnership Grant to support graduate students at the two institutions and to facilitate frequent exchange visits. The research was focused on exploring the frontiers of charged particle physics evolving from new experimental access to unusual states associated with confinement. Particular attention was paid to combined effects of quantum mechanics and confinement. A suite of analytical and numerical tools tailored to the specific inquiry has been developed and employed

DUFTY J W

2012-01-11T23:59:59.000Z

432

CONFINEMENT OF HIGH TEMPERATURE PLASMA  

DOE Patents (OSTI)

The confinement of a high temperature plasma in a stellarator in which the magnetic confinement has tended to shift the plasma from the center of the curved, U-shaped end loops is described. Magnetic means are provided for counteracting this tendency of the plasma to be shifted away from the center of the end loops, and in one embodiment this magnetic means is a longitudinally extending magnetic field such as is provided by two sets of parallel conductors bent to follow the U-shaped curvature of the end loops and energized oppositely on the inside and outside of this curvature. (AEC)

Koenig, H.R.

1963-05-01T23:59:59.000Z

433

Observations of Persistent Mixing and Near-Inertial Internal Waves  

Science Conference Proceedings (OSTI)

Repeated profiles of microstructure and shear alongside a drogued buoy show a 10 m thick mixing zone at the same depth as a near-inertial feature. Because the profile was diffusively stable and free of thermohaline intrusions, internal wave ...

M. C. Gregg; E. A. D'Asaro; T. J. Shay; N. Larson

1986-05-01T23:59:59.000Z

434

Near-Inertial Motion on the South Australian Shelf  

Science Conference Proceedings (OSTI)

Inertial oscillations in current and temperature records collected at two moorings on the South Australian continental shelf during February to May 1983 have been examined. A strong response to the eastward passage of cold fronts was observed at ...

Richard B. Schahinger

1988-03-01T23:59:59.000Z

435

Internal-Inertial Waves in a Surgasso Sea Front  

Science Conference Proceedings (OSTI)

This work examines the presence of internal-inertial waves in a front in the North Atlantic subtropical convergence zone. Results of Doppler shear profiler and towed thermistor chain surveys are displayed to document the position and magnitude of ...

Richard P. Mied; Colin Y. Shen; Clifford L. Trump; Gloria J. Lindemann

1986-11-01T23:59:59.000Z

436

Observations of Near-Inertial Waves in a Front  

Science Conference Proceedings (OSTI)

Near-inertial with horizontal scales O(10 km) dominate profiles of velocity finestructure collected in the North Pacific Subtropical Front during January 1980. Considerable spatial variability is observed. Two features in particular contain most ...

Eric Kunze; Thomas B. Sanford

1984-03-01T23:59:59.000Z

437

Mesoscale Circulation Growth under Conditions of Weak Inertial Instability  

Science Conference Proceedings (OSTI)

The hypothesis that inertial instability plays a role in the upscale development of mesoscale convective systems (MCSs) is explored by sampling environments that supported the growth of MCSs in the Preliminary Regional Experiment for STORM (...

David O. Blanchard; William R. Cotton; John M. Brown

1998-01-01T23:59:59.000Z

438

Low-Pass Filters to Suppress Inertial and Tidal Frequencies  

Science Conference Proceedings (OSTI)

A systematic way is given to design digital filters which allow clear separation of signals with periods of a few days from noise of higher frequency, particularly tidal and inertial. Several examples are given which pass little high-frequency ...

Rory O. R. Y. Thompson

1983-06-01T23:59:59.000Z

439

Intermittent and Elliptical Inertial Oscillations in the Atmospheric Boundary Layer  

Science Conference Proceedings (OSTI)

As a convective boundary layer over land decays in the late afternoon, the atmosphere responds to the release of turbulent stresses. For many years, this response has been presumed to take the form of an inertial oscillation, a horizontal ...

Julie K. Lundquist

2003-11-01T23:59:59.000Z

440

Current ShearInertial Wave Interaction in the Sargasso Sea  

Science Conference Proceedings (OSTI)

Acoustic Doppler profiler measurements of inertial waves embedded within the high shell region of a cold core ring in the Sargasso Sea are described. By repeatedly traversing the same point from different directions, a sampling pattern resembling ...

Richard P. Mied; Colin Y. Shen; Matthew J. Kidd

1990-01-01T23:59:59.000Z

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441

Energy and particle confinement in ITER (International Thermonuclear Experimental Reactor)  

SciTech Connect

ITER will require a level of energy ({tau}{sub E}) and particle ({tau}{sub p}) confinement sufficient for reaching ignition and extended burn of DT plasmas, with steady-state, high-Q (Q = P{sub fusion}/P{sub aux} = 5P{sub {alpha}}/P{sub aux}) operation as an ultimate goal. This translates into a required confinement capability of T{sub i}(0)n{sub DT}(0){tau}{sub E} {approximately}4--8 {times} 10{sup 21} keV{center dot}s/m{sup 3} for Q {approximately}5--{infinity} (where T{sub i}(0) is the central ion temperature, n{sub DT}(0) is the central DT fuel ion density, {tau}{sub E} is the global energy confinement time). In addition, {tau}{sub p} {sup He}/{tau}{sub E} < 10 is required to ensure that the thermal {alpha}-particle (He) accumulation (n{sub He}/n{sub e}) is less than 10% (where {tau}{sub p}{sup He} is the global thermal alpha particle containment time). Furthermore, the tritium fuel burnup fraction under nominal burn conditions must be greater than 1.5%. While the ITER Tn{tau}{sub E} requirement is about ten times the highest value achieved in JET (3), the extrapolation in plasma physics parameters is less. If {beta} (ratio of plasma kinetic pressure to magnetic pressure), {nu}* (collisionality), and {rho}/a (ratio of the ion gyroradius to the plasma minor radius) are taken as the relevant dimensionless parameters to characterize the plasma, the extrapolation from present JET performance to ITER is a factor {le}2. The ITER concept is based on the expectation that H-mode confinement can be achieved for long pulse. This paper covers the energy and particle confinement issues for ITER. 15 refs.

Uckan, N.A. (Oak Ridge National Lab., TN (USA)); Yushmanov, P.N.; Mukhovatov, V.S.; Parail, V.V.; Putvinskii, S. (Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow (USSR). Inst. Atomnoj Ehnergii); Takizuka, T.; Tsunematsu, T.; Yoshino, R. (Japan Atomic Energy Research Inst., Tokyo (Japan)); Borrass, K.; Engelmann, F.; Kardaun, O.; Lackner, K. (Max-Planck-Institut fuer Plasmaphysik,

1990-01-01T23:59:59.000Z

442

A probabilistic model for the identification of confinement regimes and edge localized mode behavior, with implications to scaling laws  

Science Conference Proceedings (OSTI)

Pattern recognition is becoming an important tool in fusion data analysis. However, fusion diagnostic measurements are often affected by considerable statistical uncertainties, rendering the extraction of useful patterns a significant challenge. Therefore, we assume a probabilistic model for the data and perform pattern recognition in the space of probability distributions. We show the considerable advantage of our method for identifying confinement regimes and edge localized mode behavior, and we discuss the potential for scaling laws.

Verdoolaege, Geert; Van Oost, Guido [Department of Applied Physics, Ghent University, 9000 Gent (Belgium)

2012-10-15T23:59:59.000Z

443

Quark confinement and hadronic interactions  

SciTech Connect

A study of quark models for many-hadron systems is presented. The starting point in the construction of these nonrelativistic models is a proper formal definition of the concept of color singlet and nonsinglet clusters in a multiquark system which respects the exchange symmetry of the quarks. This definition provides a natural way to impose saturation of the confining forces.

Lenz, F.; Londergan, J.T.; Moniz, E.J.; Rosenfelder, R.; Stingl, M.; Yazaki, K.

1986-08-01T23:59:59.000Z

444

Fusion energy  

Science Conference Proceedings (OSTI)

The main purpose of the International Thermonuclear Experimental Reactor (ITER) is to develop an experimental fusion reactor through the united efforts of many technologically advanced countries. The ITER terms of reference, issued jointly by the European Community, Japan, the USSR, and the United States, call for an integrated international design activity and constitute the basis of current activities. Joint work on ITER is carried out under the auspices of the International Atomic Energy Agency (IAEA), according to the terms of quadripartite agreement reached between the European Community, Japan, the USSR, and the United States. The site for joint technical work sessions is at the MaxPlanck Institute of Plasma Physics. Garching, Federal Republic of Germany. The ITER activities have two phases: a definition phase performed in 1988 and the present design phase (1989--1990). During the definition phase, a set of ITER technical characteristics and supporting research and development (R D) activities were developed and reported. The present conceptual design phase of ITER lasts until the end of 1990. The objectives of this phase are to develop the design of ITER, perform a safety and environmental analysis, develop site requirements, define future R D needs, and estimate cost, manpower, and schedule for construction and operation. A final report will be submitted at the end of 1990. This paper summarizes progress in the ITER program during the 1989 design phase.

Not Available

1990-09-01T23:59:59.000Z

445

Low-cost inertial measurement unit.  

Science Conference Proceedings (OSTI)

Sandia National Laboratories performs many expensive tests using inertial measurement units (IMUs)--systems that use accelerometers, gyroscopes, and other sensors to measure flight dynamics in three dimensions. For the purpose of this report, the metrics used to evaluate an IMU are cost, size, performance, resolution, upgradeability and testing. The cost of a precision IMU is very high and can cost hundreds of thousands of dollars. Thus the goals and results of this project are as follows: (1) Examine the data flow in an IMU and determine a generic IMU design. (2) Discuss a high cost IMU implementation and its theoretically achievable results. (3) Discuss design modifications that would save money for suited applications. (4) Design and implement a low cost IMU and discuss its theoretically achievable results. (5) Test the low cost IMU and compare theoretical results with empirical results. (6) Construct a more streamlined printed circuit board design reducing noise, increasing capabilities, and constructing a self-contained unit. Using these results, we can compare a high cost IMU versus a low cost IMU using the metrics from above. Further, we can examine and suggest situations where a low cost IMU could be used instead of a high cost IMU for saving cost, size, or both.

Deyle, Travis Jay

2005-03-01T23:59:59.000Z

446

Bemerkungen zur "kalten Fusion"  

E-Print Network (OSTI)

Steven Jones et al. reported to have observed nuclear fusion at room temperature. They observed this "cold fusion" by electrolyzing heavy water. Later experiments confirmed these observations. These experiments confirmed the generation of strong electric fields within the deuterided metals. These electric fields accelerate the deuterons to keV energies and allow the observed nuclear fusion. Roman Sioda and I suggested a theoretical description of this nuclear fusion. Our "extended micro hot fusion" scenario explains how nuclear fusion can be generated over a long time within deuterided metals. Moreover we predicted the explosion of large pieces of deuterided metals. This article reviews the "cold fusion" work of Steven Jones et al. and discusses the fracto-fusion scenario. I show that the extended micro hot fusion scenario can explain the observed neutron emissions, neutron bursts, and heat bursts.

Rainer W. Kuehne

2006-04-14T23:59:59.000Z

447

Bemerkungen zur "kalten Fusion"  

E-Print Network (OSTI)

Steven Jones et al. reported to have observed nuclear fusion at room temperature. They observed this "cold fusion" by electrolyzing heavy water. Later experiments confirmed these observations. These experiments confirmed the generation of strong electric fields within the deuterided metals. These electric fields accelerate the deuterons to keV energies and allow the observed nuclear fusion. Roman Sioda and I suggested a theoretical description of this nuclear fusion. Our "extended micro hot fusion" scenario explains how nuclear fusion can be generated over a long time within deuterided metals. Moreover we predicted the explosion of large pieces of deuterided metals. This article reviews the "cold fusion" work of Steven Jones et al. and discusses the fracto-fusion scenario. I show that the extended micro hot fusion scenario can explain the observed neutron emissions, neutron bursts, and heat bursts.

Kuehne, R W

2006-01-01T23:59:59.000Z

448

Review of fusion synfuels  

DOE Green Energy (OSTI)

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 65% are projected for fusion reactors using high-temperatures 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.

1980-01-01T23:59:59.000Z

449

Photo of the Week: The Mirror Fusion Test Facility | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

The Mirror Fusion Test Facility The Mirror Fusion Test Facility Photo of the Week: The Mirror Fusion Test Facility July 19, 2013 - 4:17pm Addthis This 1981 photo shows the Mirror Fusion Test Facility (MFTF), an experimental magnetic confinement fusion device built using a magnetic mirror at Lawrence Livermore National Laboratory (LLNL). The MFTF functioned as the primary research center for mirror fusion devices. The design consisted of a 64-meter-long vacuum vessel fitted with 26 coil magnets bonding the center of the vessel and two 400-ton yin-yang magnet mirrors at either end. The first magnet produced a magnetic field force equal to the weight of 30 jumbo jets hanging from the magnet coil. | Photo courtesy of Lawrence Livermore National Laboratory. This 1981 photo shows the Mirror Fusion Test Facility (MFTF), an

450

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

Science Conference Proceedings (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

451

Innovative Confinement Concepts Workshop 2000 (Book of Abstracts)  

E-Print Network (OSTI)

Torus Nuclear Fusion Reactor Space Propulsion VehicleTorus Nuclear Fusion Reactor Space Propulsion Vehicle

Celata, Christine; Accelerator and Fusion Research Staff

2000-01-01T23:59:59.000Z

452

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

453

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

454

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

E-Print Network (OSTI)

need to produce uranium enrichment plants and potentiallyjustified use of uranium enrichment and reprocessing plants,uranium reactor, or a clandestine centrifuge enrichment

Kramer, Kevin James

2010-01-01T23:59:59.000Z

455

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

E-Print Network (OSTI)

outlook, October 2007. 1.1 [3] Peak oil wikipedia, the freeen.wikipedia.org/wiki/Peak_oil#cite_note-mkinghubbert1956-0.

Kramer, Kevin James

2010-01-01T23:59:59.000Z

456

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

E-Print Network (OSTI)

surrounding nuclear non-proliferation are contin- uouslyfrom associated non-proliferation treaties and operating thethe LFFH engine design, non-proliferation aspects and code

Kramer, Kevin James

2010-01-01T23:59:59.000Z

457

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

E-Print Network (OSTI)

Nonproliferation Aspects 5.1 Proliferation Resistance ofstudy focuses on the nonproliferation aspects of the LFFH5 focuses on the nonproliferation aspects of the LFFH

Kramer, Kevin James

2010-01-01T23:59:59.000Z

458

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

E-Print Network (OSTI)

for anything but remote handling under controlledhandling, and inspection systems must be designed with remote

Kramer, Kevin James

2010-01-01T23:59:59.000Z

459

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

E-Print Network (OSTI)

of the available energy is wasted and how that energy couldof the available energy is wasted and how that energy could

Kramer, Kevin James

2010-01-01T23:59:59.000Z