Inertial Fusion Energy Research Papers (original) (raw)

Fast ignition requires a precise knowledge of fast electron propagation in a dense hydrogen plasma. In this context, a dedicated HiPER (High Power laser Energy Research) experiment was performed on the VULCAN laser facility where the propagation of relativistic electron beams through cylindrically compressed plastic targets was studied. In this paper, we characterize the plasma parameters such as temperature and density during the compression of cylindrical polyimide shells filled with CH foams at three different initial densities. X-ray and proton radiography were used to measure the cylinder radius at different stages of the compression. By comparing both diagnostics results with 2D hydrodynamic simulations, we could infer densities from 2 to 11 g=cm 3 and temperatures from 30 to 120 eV at maximum compression at the center of targets. According to the initial foam density, kinetic, coupled (sometimes degenerated) plasmas were obtained. The temporal and spatial evolution of the resulting areal densities and electrical conductivities allow for testing electron transport in a wide range of configurations. V

- by
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- Kinetics, High Energy Density Physics, Laser Plasma Interactions, Inertial Fusion Energy

The application of selective resonant tunneling model is extended from d ϩ t fusion to other light nucleus fusion reactions, such as d ϩ d fusion and d ϩ 3 He. In contrast to traditional formulas, the new formula for the cross-section needs only a few parameters to fit the experimental data in the energy range of interest. The features of the astrophysical S-function are derived in terms of this model. The physics of resonant tunneling is discussed.

- by Shawn Chen
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- Inertial Fusion Energy, Cross Section, Experimental Data, Resonant Tunneling

With the completion of the National Ignition Facility (NIF) and upcoming ignition experiments, there is renewed interest in laser fusion-fission hybrids and pure fusion systems for base load power generation. An advantage of a laser fusion based system is that it would produce copious neutrons (~ 1.8x10 20 /s for a 500 MW fusion source). This opens the door to hybrid systems with once through, high burn-up, closed fuel cycles.

- by Wayne Meier
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- Inertial Fusion Energy, Economic evaluation, Electric Power
- by Lisa Elkins Goodman
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- Weapons Systems, Uav, Walter Benjamin, War on Terror

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

This paper presents the goals and some of the results of experiments conducted within the Working Package 10 (Fusion Experimental Programme) of the HiPER Project. These experiments concern the study of the physics connected to 'advanced ignition schemes', i.e. the fast ignition and the shock ignition approaches to inertial fusion. Such schemes are aimed at achieving a higher gain, as compared with the classical approach which is used in NIF, as required for future reactors, and make fusion possible with smaller facilities.

- by D. Batani and +2
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- Inertial Fusion Energy, Fast Ignition Fusion, Inertial Confinement Fusion, Plasma Physics and Controlled Fusion

Significant experimental and theoretical progress has been made in the US heavy-ion fusion program on high-current sources, injectors, transport, final focusing, chambers and targets for high-energy density physics (HEDP) and inertial fusion energy (IFE) driven by induction linac accelerators. One focus of present research is the beam physics associated with quadrupole focusing of intense, space-charge dominated heavy-ion beams, including gas and electron cloud effects at high currents, and the study of long-distance-propagation effects such as emittance growth due to field errors in scaled experiments. A second area of emphasis in present research is the introduction of background plasma to neutralize the space charge of intense heavy-ion beams and assist in focusing the beams to a small spot size. In the near future, research will continue in the above areas, and a new area of emphasis will be to explore the physics of neutralized beam compression and focusing to high intensities required to heat targets to high-energy density conditions as well as for inertial fusion energy.

Fusion nuclear technology (FNT) research in the United States encompasses many activities and requires expertise and capabilities in many different disciplines. The US Enabling Technology program is divided into several task areas, with aspects of magnet fusion energy (MFE) fusion nuclear technology being addressed mainly in the Plasma Chamber, Neutronics, Safety, Materials, Tritium and Plasma Facing Component Programs. These various programs work together to address key FNT topics, including support for the ITER basic machine and the ITER Test Blanket Module, support for domestic plasma experiments, and development of DEMO relevant material and technological systems for blankets, shields, and plasma facing components. In addition, two inertial fusion energy (IFE) research programs conducting FNT-related research for IFE are also described. While it is difficult to describe all these activities in adequate detail, this paper gives an overview of critical FNT activities. (N.B. Morley). ponents, systems and technologies of the plasma chamber that are required to contain, shield, extract energy from, and breed tritium fuel for the thermonuclear fusion plasma. FNT advances will be needed both for near-term magnetic (MFE) and inertial (IFE) fusion energy experiments, and ultimately for MFE and IFE energy-producing power reactors. An incomplete list of FNT components and systems includes: 0920-3796/$ -see front matter

- by S. Willms
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- Mechanical Engineering, Inertial Fusion Energy, United States, Fusion Engineering

Demonstrating ignition and net energy gain in the near future on MJ-class laser facilities will be a major step towards determining the feasibility of Inertial Fusion Energy (IFE), in Europe as in the United States. The current status of the French Laser MégaJoule (LMJ) programme, from the laser facility construction to the indirectly driven central ignition target design, is presented, as well as validating experimental campaigns, conducted, as part of this programme, on various laser facilities. However, the viability of the IFE approach strongly depends on our ability to address the salient questions related to efficiency of the target design and laser driver performances. In the overall framework of the European HiPER project, two alternative schemes both relying on decoupling target compression and fuel heating-fast ignition (FI) and shock ignition (SI)-are currently considered. After a brief presentation of the HiPER project's objectives, FI and SI target designs are discussed. Theoretical analysis and 2D simulations will help to understand the unresolved key issues of the two schemes. Finally, the on-going European experimental effort to demonstrate their viability on currently operated laser facilities is described.

- by M. Temporal and +8
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- Inertial Fusion Energy, Nuclear Fusion, United States, Theoretical Analysis

The coupling of a new radiation transport (RT) solver with an existing multimaterial fluid dynamics code (ARWEN) using Adaptive Mesh Refinement named DAFNE, has been completed. In addition, improvements were made to ARWEN in order to work properly with the RT code, and to make it user-friendlier, including new treatment of Equations of State, and graphical tools for visualization. The evaluation of the code has been performed, comparing it with other existing RT codes (including the one used in DAFNE, but in the single-grid version). These comparisons consist in problems with real input parameters (mainly opacities and geometry parameters). Important advances in Atomic Physics, Opacity calculations and NLTE atomic physics calculations, with participation in significant experiments in this area, have been obtained. Early published calculations showed that a DT x fuel with a small tritium initial content (x53%) could work in a catalytic regime in Inertial Fusion Targets, at very high burning temperatures (4100 keV). Otherwise, the cross-section of DT remains much higher than that of DD and no internal breeding of tritium can take place. Improvements in the calculation model allow to properly simulate the effect of inverse Compton scattering which tends to lower T e and to enhance radiation losses, reducing the plasma temperature, T i . The neutron activation of all natural elements in First Structural Wall (FSW) component of an Inertial Fusion Energy (IFE) reactor for waste management, and the analysis of activation of target debris in NIF-type facilities has been completed. Using an original efficient modeling for pulse activation, the FSW behavior in inertial fusion has been studied. A radiological dose library coupled to the ACAB code is being generated for assessing impact of environmental releases, and atmospheric dispersion analysis from HIF reactors indicate the uncertainty in tritium release parameters. The first recognition of recombination barriers in SiC, modify the understanding of the calculation of displacement per atom, dpa, to quantify the collisional damage. An important analysis has been the confirmation, using Molecular Dynamics (MD) with an astonishing agreement, of the experimental evidence of low-temperature amorphization by damage accumulation in SiC, which could modify extensively its viability as a candidate material for IFE (fusion in general) applications. The radiation damage pulse effect has also been assessed using MD and Kinetic Monte Carlo diffusion of defects, showing the dose and driver frequency dependences. #

- by Marian Velarde
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- RADIATION DAMAGE, Waste Management, Fluid Dynamics, Inertial Fusion Energy

Most of the modern high-current high-voltage pulsed power generators require several stages of pulse conditioning (pulse forming) to convert the multimicrosecond pulses of the Marx generator output to the 40-300-ns pulses required by a number of applications including X-ray radiography, pulsed highcurrent linear accelerators, Z-pinch, isentropic compression, and inertial fusion energy drivers. This makes the devices large, cumbersome to operate, and expensive. Sandia, in collaboration with a number of other institutions, is developing a new paradigm in pulsed power technology: the linear transformer driver (LTD) technology. This technological approach can provide very compact devices that can deliver very fast high-current and high-voltage pulses. The output pulse rise time and width can be easily tailored to the specific application needs. Trains of a large number of high-current pulses can be produced with variable interpulse separation from nanoseconds to milliseconds. Most importantly, these devices can be rep-rated to frequencies only limited by the capacitor specifications (usually 10 Hz). Their footprint, as compared with current day pulsed power accelerators, is considerably smaller since LTD do not require large oil and deionized water tanks. This makes them ideally suited for applications that require portability. In this paper, we present Sandia National Laboratories' broad spectrum of developmental effort to design construct and extensively validate the LTD pulsed power technology.

- by Keith Matzen
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- Inertial Fusion Energy, High Voltage, X Rays, Power Generation

The high average power laser program is developing an inertial fusion energy demonstration power reactor with a solid first wall chamber. The first wall (FW) will be subject to high energy density radiation and high doses of high energy helium implantation. Tungsten has been identified as the candidate material for a FW armor. The fundamental concern is long term thermo-mechanical survivability of the armor against the effects of high temperature pulsed operation and exfoliation due to the retention of implanted helium. Even if a solid tungsten armor coating would survive the high temperature cyclic operation with minimal failure, the high helium implantation and retention would result in unacceptable material loss rates. Micro-engineered materials, such as castellated structures, plasma sprayed nano-porous coatings and refractory foams are suggested as a first wall armor material to address these fundamental concerns. A micro-engineered FW armor would have to be designed with specific geometric features that tolerate high cyclic heating loads and recycle most of the implanted helium without any significant failure. Micro-engineered materials are briefly reviewed. In particular, plasmasprayed nano-porous tungsten and tungsten foams are assessed for their potential to accommodate inertial fusion specific loads. Tests show that nano-porous plasma spray coatings can be manufactured with high permeability to helium gas, while retaining relatively high thermal conductivities. Tungsten foams where shown to be able to overcome thermomechanical loads by cell rotation and deformation. Helium implantation tests have shown, that pulsed implantation and heating releases significant levels of implanted helium. Helium implantation and release from tungsten was modeled using an expanded kinetic rate theory, to include the effects of pulsed implantations and thermal cycles. Although, significant challenges remain micro-engineered materials are shown to constitute potential candidate FW armor materials.

- by Robert S Shaefer and +1
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- Materials Engineering, Kinetics, High Energy Density Physics, Nuclear Materials

HiPER (High Power laser Energy Research) is the first European plan for international cooperation in developing inertial fusion energy. ICF activities are ongoing in a number of nations and the first ignition experiments are underway at the National Ignition Facility (NIF) in the USA. Although HiPER is still in the preparatory phase, it is appropriate for Europe to commence planning for future inertial fusion activities that leverage the demonstration of ignition. In this paper we shall detail some of the key points of the laser design and the way this design is connected to the capsule requirements.

- by L. Gizzi and +1
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- International Cooperation, Inertial Fusion Energy, High Power

In inertial fusion energy (IFE) power plant designs, the fuel is a spherical layer of frozen DT contained in a target that is injected at high velocity into the reaction chamber. For direct drive, typically laser beams converge at the centre of the chamber (CC) to compress and heat the target to fusion conditions. To obtain the maximum energy yield from the fusion reaction, the frozen DT layer must be at about 18.5 K and the target must maintain a high degree of spherical symmetry and surface smoothness when it reaches the CC. During its transit in the chamber the cryogenic target is heated by radiation from the hot chamber wall. The target is also heated by convection as it passes through the rarefied fill-gas used to control chamber wall damage by x-rays and debris from the target explosion. This article addresses the temperature limits at the target surface beyond which target uniformity may be damaged. It concentrates on direct drive targets because fuel warm up during injection is not currently thought to be an issue for present indirect drive designs and chamber concepts. Detailed results of parametric radiative and convective heating calculations are presented for direct-drive targets during injection into a dry-wall reaction chamber. The baseline approach to target survival utilizes highly reflective targets along with a substantially lower chamber wall temperature and fill-gas pressure than previously assumed. Recently developed high-Z material coatings with high heat reflectivity are discussed and characterized. The article also presents alternate target protection methods that could be developed if targets with inherent survival features cannot be obtained within a reasonable time span.

- by Farrokh Najmabadi
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- Inertial Fusion Energy, Power Plant, Nuclear, X Rays

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 and then position cryogenic targets at chamber center is at the heart of futureIFE power plants. For direct drive IFE (laser fusion) energy is applied

- by James Maxwell
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- Plasma Physics, Science and Technology, Inertial Fusion Energy, Power Plant
- by Robert Fagaly
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- Inertial Fusion Energy

The optical reflectance of a strong shock front in water increases continuously with pressure above 100 GPa and saturates at ϳ45% reflectance above 250 GPa. This is the first evidence of electronic conduction in high pressure water. In addition, the water Hugoniot equation of state up to 790 GPa ͑7.9 Mbar͒ is determined from shock velocity measurements made by detecting the Doppler shift of reflected light. From a fit to the reflectance data we find that an electronic mobility gap ϳ2.5 eV controls thermal activation of electronic carriers at pressures in the range of 100-150 GPa. This suggests that electronic conduction contributes significantly to the total conductivity along the Neptune isentrope above 150 GPa.

- by Kanani Lee
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- Physics, High Pressure, High Energy Density Physics, Inertial Fusion Energy

Key scientific results from recent experiments, modeling tools, and heavy ion accelerator research are summarized that explore ways to investigate the properties of high energy density matter in heavy-ion-driven targets, in particular,... more

- by Ronald Davidson and +2
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- Plasma Physics, Energy Conservation, High Energy Density Physics, Inertial Fusion Energy
- by Jeffrey Freidberg and +1
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- Inertial Fusion Energy, Heavy Ions Physics, Fusion, Inertial Confinement Fusion

Radiation shielding structure of a design concept with inertial fusion energy propulsion for manned or heavy cargo deep space missions beyond earth orbit has been investigated. Fusion power deposited in the inertial con®ned fuel pellet debris delivers the rocket propulsion with the help of a magnetic nozzle. The nuclear heating in the super conducting magnet coils determines the radiation shielding mass of the spacecraft. It was possible to achieve considerable mass saving with respect to a recent design work, coupled with higher design limits for coil heating (up to 5 mW/cm 3 ). The neutron and -ray penetration into the coils is calculated using the x methods with a high angular resolution in (r±z) geometry in S 16 P 3 approximation by dividing the solid space angle in 160 sectors. Total peak nuclear heat generation density in the coils is calculated as 3.143 mW/cm 3 by a fusion power of 17 500 MW. Peak neutron heating density is 1.469 mW/cm 3 and peak -ray heating density is 1.674 mW/ cm 3 . However, volume averaged heat generation in the coils is much lower, namely 74, 163 and 337 mW/cm 3 for neutron, -ray and total nuclear heating, respectively. The net mass of the radiation shielding for the magnet coils is 200 tonne by a total mass of 6000 tonne of the space craft. #

Electra is a 700 J, repetitively pulsed, electron beam pumped Krypton Fluoride (KrF) laser that is developing technologies to meet the inertial fusion energy (IFE) requirements for rep-rate, efficiency, durability and cost . We have designed a pulsed power system for the preamplifier in the Electra KrF laser system. This preamplifier is designed to produce 40 J of laser light in a 40 nsec pulse which will be used to provide the input to the main amplifier. The pulsed power for the front end will serve two roles. It will complete the laser system and it will serve as the demonstrator for the new advanced pulsed power topology that can meet the fusion energy requirements for durability, repetition rate, and cost. The pulsed power will first employ a gas-switched Marx, with anticipated maintenance intervals similar to that of the existing Electra main amplifier . Later the driver will be replaced (circa 2006) with a solid-state-switched Marx generator .

- by T Dasilva
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- Power System, Mechanism Design, Inertial Fusion Energy, Circuit simulation

Direct-drive inertial confinement fusion (ICF) is expected to demonstrate high gain on the National Ignition Facility (NIF) in the next decade and is a leading candidate for inertial fusion energy production. The demonstration of high areal densities in hydrodynamically scaled cryogenic DT or D2 implosions with neutron yields that are a significant fraction of the "clean" 1-D predictions will validate the ignition-equivalent direct-drive target performance on the OMEGA laser at the Laboratory for Laser Energetics (LLE). This paper highlights the recent experimental and theoretical progress leading toward achieving this validation in the next few years. The NIF will initially be configured for X-ray drive and with no beams placed at the target equator to provide a symmetric irradiation of a direct-drive capsule. LLE is developing the "polar-direct-drive" (PDD) approach that repoints beams toward the target equator. Initial 2-D simulations have shown ignition. A unique "Saturn-like" plastic ring around the equator refracts the laser light incident near the equator toward the target, improving the drive uniformity. LLE is currently constructing the multibeam, 2.6-kJ/beam, petawatt laser system OMEGA EP. Integrated fast-ignition experiments, combining the OMEGA EP and OMEGA Laser Systems, will begin in FY08.

- by P. McKenty
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- Inertial Fusion Energy, X Rays, Physical sciences, Inertial Confinement Fusion

Effective integration of nonproliferation management into the design process is key to the broad deployment of advanced nuclear energy systems, and is an explicit goal of the Laser Inertial Fusion Energy (LIFE) project at Lawrence Livermore National Laboratory. The nuclear explosives utility of a nuclear material to a state (proliferator) or sub-state (terrorist) is a critical factor to be assessed and is one aspect of material attractiveness. In this work, we approached nuclear explosives utility through the calculation of a "figure of merit" (FOM) that has recently been developed to capture the relative viability and difficulty of constructing nuclear explosives starting from various nuclear material forms and compositions. We discuss the integration of the figure of merit into an assessment of a nuclear material theft scenario and its use in the assessment. This paper demonstrates that material attractiveness is a multidimensional concept that embodies more than the FOM. It also seeks to propose that other attributes may be able to be quantified through analogous FOMs (e.g., transformation) and that, with quantification, aggregation may be possible using concepts from the risk community.

- by Keith Bradley
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- Risk communication, Nuclear Energy, Inertial Fusion Energy, Design process

The high average power laser (HAPL) program aims at developing laser inertial fusion energy (Laser IFE) based on lasers, direct drive targets and a solid wall chamber. The preferred first wall configuration is based on tungsten and ferritic steel as armor and structural materials, respectively. A key concern is the survival of the first wall under the X-ray and ion energy deposition from the fusion micro-explosion. The HAPL design and R&D effort in the chamber and material area is focused toward understanding and resolving the key armor survival issues. This includes modeling and experimental testing of the armor thermo-mechanical behavior in facilities utilizing ion, X-rays and laser sources to simulate IFE conditions. Helium management is addressed by conducting implantation experiments along with modeling of He behavior in tungsten. This paper summarizes the HAPL chamber activities. The first wall/armor configuration and design analysis are described, key chamber issues are discussed, and the R&D to address them is highlighted.

- by Robert S Shaefer and +1
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- Mechanical Engineering, Inertial Fusion Energy, X Rays, Ion Implantation

The promise of inertial fusion energy driven by heavy ion beams requires the development of accelerators that produce ion currents (~100's Amperes/beam) and ion energies (~1 -10 GeV) that have not been achieved simultaneously in any existing accelerator. The high currents imply high generalized perveances, large tune depressions, and high space charge potentials of the beam center relative to the beam pipe. Many of the scientific issues associated with ion beams of high perveance and large tune depression have been addressed over the last two decades on scaled experiments at

- by Ronald Davidson and +3
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- Inertial Fusion Energy, Power Plant, Heavy Ions Physics, Fill Factor

An experiment was done at the Rutherford Appleton Laboratory ͑Vulcan laser petawatt laser͒ to study fast electron propagation in cylindrically compressed targets, a subject of interest for fast ignition. This was performed in the framework of the experimental road map of HiPER ͑the European high power laser energy research facility project͒. In the experiment, protons accelerated by a picosecond-laser pulse were used to radiograph a 220 m diameter cylinder ͑20 m wall, filled with low density foam͒, imploded with ϳ200 J of green laser light in four symmetrically incident beams of pulse length 1 ns. Point projection proton backlighting was used to get the compression history and the stagnation time. Results are also compared to those from hard x-ray radiography. Detailed comparison with two-dimensional numerical hydrosimulations has been done using a Monte Carlo code adapted to describe multiple scattering and plasma effects. Finally we develop a simple analytical model to estimate the performance of proton radiography for given implosion conditions.

- by L. Volpe and +2
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- Monte Carlo, High Energy Density Physics, Laser Plasma Interactions, Inertial Fusion Energy
- by Joe Schumer
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- Inertial Fusion Energy, Particle in Cell, Energy System, Transmission Line

Fusion energy is a process that gives power to the sun and stars following its explosion from the sun. It's a source of energy that is reliable and completely harmless and planet friendly. In the near future it will take total control of the world energy market. But, it's not so easy to produce that Fusion energy as the costs are too high. It is being planned that in the next 40 years time scientists will establish a demo for Fusion energy. Fusion energy has the potential to hold the World energy monopoly. It's a energy source that is promising. İn the process of the production of Fusion energy, aside from helium gas, it produces zero greenhouse gass emmission and has no long term waste. There is enough resourses in the World to provide with Fusion energy for millions of years in our planet. The production of Fusion energy doesn't get affected by negative weather conditions. This paper emphasizes the importance of Fusion energy and mentions the researches done in our country and the World.

- by Sercan ÖZTÜRK
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- Electrical Engineering, Physics, Quantum Physics, Renewable Energy

- by David Baca and +1
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- Inertial Fusion Energy, Power Plant, Heavy Ions Physics, Fill Factor
- by Al Erlandson
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- Solid State Laser, Inertial Fusion Energy, Laser Diode

A two-year study of recirculating induction heavy ion accelerators as low-cost driver for inertial-fusion energy applications was recently completed. The projected cost of a 4 MJ accelerator was estimated to be about $500 M (million) and the efficiency was estimated to be 35%. The principal technology issues include energy recovery of the ramped dipole magnets, which is achieved through use of ringing inductive/capacitive circuits, and high repetition rates of the induction cell pulsers, which is accomplished through arrays of field effect transistor (FET) switches. Principal physics issues identified include minimization of particle loss from interactions with the background gas, and more demanding emittance growth and centroid control requirements associated with the propagation of space-charge-dominated beams around bends and over large path lengths. In addition, instabilities such as the longitudinal resistive instability, beam-breakup instability and betatron-orbit instability were found to be controllable with careful design.

- by A. Faltens
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- Plasma Physics, Inertial Fusion Energy, Power Plant, Heavy Ions Physics

The National Ignition Facility (NIF) is a 192 beam Nd-glass laser facility presently under construction at Lawrence Livermore National Laboratory (LLNL) for performing ignition experiments for inertial confinement fusion (ICF) and experiments studying high energy density (HED) science. NIF will produce 1.8 MJ, 500 TW of ultraviolet light ( = 351 nm) making it the world's largest and most powerful laser system. NIF will be the world's preeminent facility for the study of matter at extreme temperatures and densities producing and for developing ICF. The ignition studies will an essential step in developing inertial fusion energy. The NIF Project is over 93% complete and scheduled for completion in 2009. Experiments using one beam have demonstrated that NIF can meet all of its performance goals. A detailed plan called the National Ignition Campaign (NIC) has been developed to begin ignition experiments in 2010. The plan includes the target physics and the equipment such as diagnostics, cryogenic target manipulator and user optics required for the ignition experiment. Target designs have been developed that calculate to ignite at energy as low as 1 MJ. Plans are underway to make NIF a national user facility for experiments on HED physics and nuclear science, including experiments relevant to the development of IFE.

- by Edward Moses and +1
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- Mechanical Engineering, High Energy Density Physics, Inertial Fusion Energy, Interdisciplinary Engineering
- by Per Peterson and +1
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- Mechanical Engineering, Plasma Physics, Solid State Laser, Inertial Fusion Energy
- by Phillip Colella
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- Inertial Fusion Energy, Heavy Ions Physics, Fusion, Inertial Confinement Fusion
- by Robert Shaefer
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- Materials Engineering, Materials Science, Kinetics, High Energy Density Physics

New results of the jet driven ignition target are presented, both with direct and indirect drive. This target is based on the conical guided target used in fast ignition, but use only one laser pulse. The ignition of the target is started by the impact of a jet produced in the guiding cone, instead of using charged particles generated by a other high power laser. We have shown that a laser or X-ray pulse could be used to produce a high velocity jet of several hundred of km/s by an accumulative effect, and we use these ideas to design this new kind of targets. In order to increase the efficiency of the process, we scan in the simulations different materials, cone profiles and laser intensities. ANALOP is a code developed to calculate opacities for hot plasmas, using analytical potentials including density and temperature effects. It has been recently updated to include the radiative transport into the rate equations by mean of the escape factors, and in parallel a line transport code which solve self-consistently the rate equation and radiative transfer equation in 1D planar geometry has been also developed. We have developed a comprehensive methodology to compute uncertainties on activation calculations. First we developed a sensitivity-uncertainty analysis method, providing the uncertainties of the different inventory responses functions due to the uncertainty of each of the reaction cross sections separately. Lately, we have developed and proved the excellent behaviour of a Monte Carlo-based methodology in assessing the synergetic/global effect of the complete set of cross-sections uncertainties on calculated radiological quantities. The methods have been applied to the activation analysis of the National Ignition Facility (NIF) and different IFE concepts (HYLIFE and Sombrero). Research on multiscale modelling of radiation damage in metals will be presented in comparison with "ad hoc" experiments. Research on SiC composite is being pursued at macroscopic level. However, results from theory and simulation to explain that physics is being slowly progressing. The systematic identification of type of stable defects is the first goal that will presented after verification of a new tight binding MD technique. The different level of knowledge between simulation and experiments will be remarked. Our research on simulation of Silica Irradiation Damage will also be presented. We also will present the role of ingestion by tritiated foods, when the most important chemical forms of tritium, elemental tritium (HT) and tritiated water (HTO) derive in special form of tritium: Organically Bound Tritium (OBT)

- by Pablo Martel
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- Plasma Physics, Chemistry, Technology, RADIATION DAMAGE

Fast ignition (FI) has significant potential advantages for inertial fusion energy and it is therefore being studied as an exploratory concept in the US fusion energy program. FI is based on short pulse isochoric heating of pre-compressed DT by intense beams of laser accelerated MeV electrons or protons. Recent experimental progress in the study of these two heating processes is discussed. The goal is to benchmark new models in order to predict accurately the requirements for full-scale fast ignition. An overview is presented of the design and experimental testing of a cone target implosion concept for fast ignition. Future prospects and conceptual designs for larger scale FI experiments using planned high energy petawatt upgrades of major lasers in the US are outlined. A long-term roadmap for FI is defined.

- by N. Fisch
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- Nuclear Energy, Inertial Fusion Energy, Conceptual Design, Experimental Tests

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. This is true whether the driver is a laser system, heavy ion beams or Z-pinch system. The IFE target fabrication, injection and tracking programmes are focusing on methods that will scale to mass production. We are working closely with target designers, and power plant systems specialists, to make specifications and material selections that will satisfy a wide range of required and desirable target characteristics. One-of-a-kind capsules produced for today's inertial confinement fusion experiments are estimated to cost about US$2500 each. Design studies of cost-effective power production from laser and heavy-ion driven IFE have suggested a cost goal of about $0.25-0.30 for each injected target (corresponding to ∼10% of the 'electricity value' in a target). While a four orders of magnitude cost reduction may seem at first to be nearly impossible, there are many factors that suggest this is achievable. This paper summarizes the design, specifications, requirements and proposed manufacturing processes for the future for laser fusion, heavy ion fusion and Z-pinch driven targets. These target manufacturing processes have been developed-and are proposed-based on the unique materials science and technology programmes that are ongoing for each of the target concepts. We describe the paradigm shifts in target manufacturing methodologies that will be needed to achieve orders of magnitude reductions in target costs, and summarize the results of 'nth-of-a-kind' plant layouts and cost estimates for future IFE power plant fuelling. These engineering studies estimate the cost of the target supply in a fusion economy, and show that costs are within the range of commercial feasibility for electricity production.

- by Craig craig
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- Science and Technology, Inertial Fusion Energy, Power Plant, Cost Estimation

- by John Maxwell
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- Science and Technology, Inertial Fusion Energy, Power Plant, Cost Estimation

- by P. Velarde
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- RADIATION DAMAGE, Waste Management, Fluid Dynamics, Inertial Fusion Energy

The high-current experiment (HCX) at LBNL is a driver scale single beam injector that provides a 1 MeV K + ion beam current of 0.18 A for 5 ls. It transports high-current beams with large fill factor (ratio of the maximum beam envelope radius to the beam pipe radius) and low emittance growth that are required to keep the cost of the power plant competitive and to satisfy the target requirements of focusing ion beams to high-power density. Beam interaction with the background gas and walls desorbs electrons that can multiply and accumulate, creating an electron cloud. This ubiquitous effect grows at higher fill factors and degrades the quality of the beam. We review simulations and diagnostics tools used to measure electron production, accumulation and its properties. Published by Elsevier B.V.

- by David Baca
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- Geochemistry, Materials Science, Plasma Physics, Inertial Fusion Energy

- by Alex Friedman and +5
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- Geochemistry, Inertial Fusion Energy, Power Plant, Focused Ion Beam

In cone coupled electron fast ignition, laser generated electrons transport energy and ignite a small hot spot in the compressed fuel. The laser to plasma coupling is via a hollow cone and the energy is transported by relativistic electrons of a few MeV average energy over a distance of the order of 100 µm into DT at about 300 gcm -3 and confined within a diameter <40 µm. The total energy deposited in the hot spot is about 20kJ in 10ps. Overall coupling efficiency between laser energy and thermal energy in the ignition hot spot should exceed 10% and preferably reach 20% (as seen in the first small scale integrated experiments ) to make the scheme practically attractive.

- by F. Beg and +2
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- High Energy Density Physics, Laser Plasma Interactions, Inertial Fusion Energy, Mathematical Sciences

- by James Maxwell
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- Science and Technology, Inertial Fusion Energy, Power Plant, Cost Estimation