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Dive into the research topics where Jeffery F. Latkowski is active.

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Featured researches published by Jeffery F. Latkowski.


Fusion Science and Technology | 2003

An Updated Point Design for Heavy Ion Fusion

S.S. Yu; Wayne R. Meier; R.P. Abbott; J. J. Barnard; T. Brown; D. A. Callahan; C. Debonnel; P. Heitzenroeder; Jeffery F. Latkowski; B.G. Logan; Steven J. Pemberton; P.F. Peterson; D. V. Rose; G. Sabbi; W. M. Sharp; D.R. Welch

Abstract An updated, self-consistent point design for a heavy ion fusion (HIF) power plant based on an induction linac driver, indirect-drive targets, and a thick liquid wall chamber has been completed. Conservative parameters were selected to allow each design area to meet its functional requirements in a robust manner, and thus this design is referred to as the Robust Point Design (RPD-2002). This paper provides a top-level summary of the major characteristics and design parameters for the target, driver, final focus magnet layout and shielding, chamber, beam propagation to the target, and overall power plant.


Fusion Science and Technology | 2011

Compact, Efficient Laser Systems Required for Laser Inertial Fusion Energy

A. Bayramian; S. Aceves; T. Anklam; K. Baker; E. Bliss; C. Boley; A. Bullington; John A. Caird; D. Chen; R. Deri; Mike Dunne; Alvin C. Erlandson; D. Flowers; Mark A. Henesian; Jeffery F. Latkowski; Kenneth R. Manes; William A. Molander; E. I. Moses; T. Piggott; S. Powers; S. Rana; S. Rodriguez; R. Sawicki; Kathleen I. Schaffers; L. Seppala; M. Spaeth; S. Sutton; S. Telford

Abstract This paper presents our conceptual design for laser drivers used in Laser Inertial Fusion Energy (LIFE) power plants. Although we have used only modest extensions of existing laser technology to ensure near-term feasibility, predicted performance meets or exceeds plant requirements: 2.2 MJ pulse energy produced by 384 beamlines at 16 Hz, with 18% wall-plug efficiency. High reliability and maintainability are achieved by mounting components in compact line-replaceable units that can be removed and replaced rapidly while other beamlines continue to operate, at up to ˜13% above normal energy, to compensate for neighboring beamlines that have failed. Statistical modeling predicts that laser-system availability can be greater than 99% provided that components meet reasonable mean-time-between-failure specifications.


Fusion Science and Technology | 2009

A SUSTAINABLE NUCLEAR FUEL CYCLE BASED ON LASER INERTIAL FUSION ENERGY

E. I. Moses; Tomas Diaz de la Rubia; E. Storm; Jeffery F. Latkowski; Joseph C. Farmer; Ryan P. Abbott; Kevin J. Kramer; Per F. Peterson; Henry F. Shaw; Ronald F. Lehman

Abstract The National Ignition Facility (NIF), a laser-based Inertial Confinement Fusion (ICF) experiment designed to achieve thermonuclear fusion ignition and burn in the laboratory, will soon be completed at the Lawrence Livermore National Laboratory. Experiments designed to accomplish the NIF’s goal will commence in 2010, using laser energies of 1 to 1.3 MJ. Fusion yields of the order of 10 to 35 MJ are expected soon thereafter. We propose that a laser system capable of generating fusion yields of 35 to 75 MJ at 10 to 15 Hz (i.e., ≈ 350- to 1000-MW fusion and ≈ 1.3 to 3.6 x 1020 n/s), coupled to a compact subcritical fission blanket, could be used to generate several GW of thermal power (GWth) while avoiding carbon dioxide emissions, mitigating nuclear proliferation concerns and minimizing the concerns associated with nuclear safety and long-term nuclear waste disposition. This Laser Inertial Fusion Energy (LIFE) based system is a logical extension of the NIF laser and the yields expected from the early ignition experiments on NIF. The LIFE concept is a once-through, self-contained closed fuel cycle and would have the following characteristics: (1) eliminate the need for uranium enrichment; (2) utilize over 90% of the energy content of the nuclear fuel; (3) eliminate the need for spent fuel chemical separation facilities; (4) maintain the fission blanket subcritical at all times (keff <0.90); and (5) minimize future requirements for deep underground geological waste repositories and minimize actinide content in the end-of-life nuclear waste below the (the lowest). Options to burn natural or depleted U, Th, U/Th mixtures, Spent Nuclear Fuel (SNF) without chemical separations of weapons-attractive actinide streams, and excess weapons Pu or highly enriched U (HEU) are possible and under consideration. Because the fission blanket is always subcritical and decay heat removal is possible via passive mechanisms, the technology is inherently safe. Many technical challenges must be met, but a LIFE solution could provide a sustainable path for worldwide growth of nuclear power for electricity production and hydrogen generation.


Fusion Science and Technology | 2005

Development Path for Z-Pinch IFE

C.L. Olson; Gary Eugene Rochau; Stephen A. Slutz; Charles W. Morrow; R. Olson; M. E. Cuneo; D.L. Hanson; G. Bennett; T. W. L. Sanford; J. E. Bailey; W. A. Stygar; Roger A. Vesey; T.A. Mehlhorn; K.W. Struve; M.G. Mazarakis; M. E. Savage; T.D. Pointon; M. Kiefer; S. E. Rosenthal; K. Cochrane; L. Schneider; S. Glover; K.W. Reed; Diana Grace Schroen; C. Farnum; M. Modesto; D. Oscar; L. Chhabildas; J. Boyes; Virginia Vigil

Abstract The long-range goal of the Z-Pinch IFE program is to produce an economically-attractive power plant using high-yield z-pinch-driven targets (~3GJ) with low rep-rate per chamber (~0.1 Hz). The present mainline choice for a Z-Pinch IFE power plant uses an LTD (Linear Transformer Driver) repetitive pulsed power driver, a Recyclable Transmission Line (RTL), a dynamic hohlraum z-pinch-driven target, and a thick-liquid wall chamber. The RTL connects the pulsed power driver directly to the z-pinch-driven target, and is made from frozen coolant or a material that is easily separable from the coolant (such as carbon steel). The RTL is destroyed by the fusion explosion, but the RTL materials are recycled, and a new RTL is inserted on each shot. A development path for Z-Pinch IFE has been created that complements and leverages the NNSA DP ICF program. Funding by a U.S. Congressional initiative of


Fusion Science and Technology | 2003

Fused Silica Final Optics for Inertial Fusion Energy: Radiation Studies and System-Level Analysis

Jeffery F. Latkowski; Alison Kubota; Maria Jose Caturla; Sham N. Dixit; Joel A. Speth; Stephen A. Payne

4M for FY04 through NNSA DP is supporting assessment and initial research on (1) RTLs, (2) repetitive pulsed power drivers, (3) shock mitigation [because of the high yield targets], (4) planning for a proof-of-principle full RTL cycle demonstration [with a 1 MA, 1 MV, 100 ns, 0.1 Hz driver], (5) IFE target studies for multi-GJ yield targets, and (6) z-pinch IFE power plant engineering and technology development. Initial results from all areas of this research are discussed.


Fusion Science and Technology | 2009

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

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

The survivability of the final optic, which must sit in the line of sight of high-energy neutrons and gamma rays, is a key issue for any laser-driven inertial fusion energy (IFE) concept. Previous work has concentrated on the use of reflective optics. Here, we introduce and analyze the use of a transmissive final optic for the IFE application. Our experimental work has been conducted at a range of doses and dose rates, including those comparable to the conditions at the IFE final optic. The experimental work, in conjunction with detailed analysis, suggests that a thin, fused silica Fresnel lens may be an attractive option when used at a wavelength of 351 nm. Our measurements and molecular dynamics simulations provide convincing evidence that the radiation damage, which leads to optical absorption, not only saturates but that a “radiation annealing” effect is observed. A system-level description is provided, including Fresnel lens and phase plate designs.


IEEE Transactions on Plasma Science | 2010

The Science and Technologies for Fusion Energy With Lasers and Direct-Drive Targets

J. D. Sethian; D. G. Colombant; J. L. Giuliani; R.H. Lehmberg; M.C. Myers; S. P. Obenschain; A.J. Schmitt; J. Weaver; Matthew F. Wolford; F. Hegeler; M. Friedman; A. E. Robson; A. Bayramian; J. Caird; C. Ebbers; Jeffery F. Latkowski; W. Hogan; Wayne R. Meier; L.J. Perkins; K. Schaffers; S. Abdel Kahlik; K. Schoonover; D. L. Sadowski; K. Boehm; Lane Carlson; J. Pulsifer; F. Najmabadi; A.R. Raffray; M. S. Tillack; G.L. Kulcinski

Abstract 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 Monte burns 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 6Li 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.


Fusion Science and Technology | 2011

CHAMBER DESIGN FOR THE LASER INERTIAL FUSION ENERGY (LIFE) ENGINE

Jeffery F. Latkowski; R. P. Abbott; S Aceves; T Anklam; D Badders; Andrew W. Cook; James A. Demuth; L Divol; B El-Dasher; J C Farmer; D Flowers; Massimiliano Fratoni; R G ONeil; T Heltemes; J Kane; Kevin J. Kramer; Richard Kramer; A Lafuente; G A Loosmore; K R Morris; Gregory A. Moses; B Olson; Carlos Pantano; S. Reyes; M Rhodes; K Roe; R Sawicki; Howard A. Scott; M Spaeth; M Tabak

We are carrying out a multidisciplinary multi-institutional program to develop the scientific and technical basis for inertial fusion energy (IFE) based on laser drivers and direct-drive targets. The key components are developed as an integrated system, linking the science, technology, and final application of a 1000-MWe pure-fusion power plant. The science and technologies developed here are flexible enough to be applied to other size systems. The scientific justification for this work is a family of target designs (simulations) that show that direct drive has the potential to provide the high gains needed for a pure-fusion power plant. Two competing lasers are under development: the diode-pumped solid-state laser (DPPSL) and the electron-beam-pumped krypton fluoride (KrF) gas laser. This paper will present the current state of the art in the target designs and lasers, as well as the other IFE technologies required for energy, including final optics (grazing incidence and dielectrics), chambers, and target fabrication, injection, and tracking technologies. All of these are applicable to both laser systems and to other laser IFE-based concepts. However, in some of the higher performance target designs, the DPPSL will require more energy to reach the same yield as with the KrF laser.


Fusion Science and Technology | 2009

Thermal and Mechanical Design Aspects of the LIFE Engine

Ryan P. Abbott; Michael A. Gerhard; Kevin J. Kramer; Jeffery F. Latkowski; Kevin Morris; Per F. Peterson; Jeffrey E. Seifried

Abstract 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.


Fusion Science and Technology | 2004

OPERATIONAL WINDOWS FOR DRY-WALL AND WETTED-WALL IFE CHAMBERS

F. Najmabadi; A.R. Raffray; S. I. Abdel-Khalik; Leslie Bromberg; L. El-Guebaly; D. T. Goodin; D. Haynes; Jeffery F. Latkowski; Wayne R. Meier; Richard L. Moore; S. Neff; C.L. Olson; J. Perkins; David A. Petti; D. Rose; W. M. Sharp; P. Sharpe; M. S. Tillack; Lester M. Waganer; D.R. Welch; Minami Yoda; S. S. Yu; Mofreh R. Zaghloul

Abstract The Laser Inertial confinement fusion - Fission Energy (LIFE) engine encompasses the components of a LIFE power plant responsible for converting the thermal energy of fusion and fission reactions into electricity. The design and integration of these components must satisfy a challenging set of requirements driven by nuclear, thermal, geometric, structural, and materials considerations. This paper details a self-consistent configuration for the LIFE engine along with the methods and technologies selected to meet these stringent requirements. Included is discussion of plant layout, coolant flow dynamics, fuel temperatures, expected structural stresses, power cycle efficiencies, and first wall survival threats. Further research to understand and resolve outstanding issues is also outlined.

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Kevin J. Kramer

Lawrence Livermore National Laboratory

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S. Reyes

Lawrence Livermore National Laboratory

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Wayne R. Meier

Lawrence Livermore National Laboratory

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Ryan P. Abbott

University of California

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J. Sanz

Technical University of Madrid

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A. Bayramian

Lawrence Livermore National Laboratory

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E. I. Moses

Lawrence Livermore National Laboratory

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Jeffrey J. Powers

Oak Ridge National Laboratory

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M. S. Tillack

University of California

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