NDLI: Conceptual Study of Integrated Chamber Core for Laser Fusion with Magnetic Intervention

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2013 IEEE 25th Symposium on Fusion Engineering (SOFE)

2011 IEEE/NPSS 24th Symposium on Fusion Engineering

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2007 IEEE 22nd Symposium on Fusion Engineering

Proceedings of the 22nd IEEE/NPSS Symposium on Fusion Engineering - SOFE 07

Table of contents

ITER Neutronics Analysis for the Design of Diagnostics and Port Plugs Using ATTILA Discrete Ordinates Software

High Pressure Supersonic Gas Jet Fueling on NSTX

Pellet Dropper Device for ELM Control on DIII-D

Metrology for the NCSX Project

NCSX Component Fabrication Challenges

Assembly Status of the W7-X Stellarator

Development of Water Hydraulic Remote Handling System for Divertor Maintenance of ITER

Manufacture of Inter-Coil Support-Elements of the W7-X Magnet System

Hydrogen isotopes permeation evaluation in the advanced material for nuclear fusion blanket use

Basic research of the solid electrolyte as a sensor for the purity control of the liquid metal LiPb

Improvements of the DIII-D Cryosystem from Analysis of Failure Modes and Their Effects

Intensity Distribution of D-3He Fusion Reaction Rate in an IEC Device

Design and Performance of NSTX Movable GDC Probe

Divertor Heat Loads from Thermal and Alpha Particles in a Compact Stellarator Reactor

Phase Lag Infra-red Thermal Examination (PLITE); A New Non-destructive Test Process

Design of an experimental facility to study convection in liquid lithium

Engineered Surfaces for the Lithium Tokamak Experiment (LTX)

NSTX OH Coil Design Improvements

A Conceptual Design for the Magnets in an IFE Magnetic Intervention Chamber

Design Optimization of the ITER TF Coil Structure for Manufacturing and Assembly

ITER Magnet Design Criteria and their Impact on Manufacturing and Assembly

The Superconducting Bus-Bar System for Wendelstein 7-X - A Challenge to Engineering

Conceptual Design of Advanced Blanket Using Liquid LiPb

A New Overcurrent Protection System for the DIII-D Field Shaping Coils

Phased Array Ultrasonic Non-Destructive Evaluation of ITER Plasma Facing Components

Helium Jet-Cooled Tungsten Divertor Concept

He-cooled Divertor for DEMO Status of Design and HHF Tests

Material Surface Ablation with ELM-like E-beam Thermal Load

Effect of Transient Heat Loads on Neutron Irradiated Tungsten and Carbon Based Materials

Development Status of the Helium-Cooled Porous Tungsten Heat Exchanger Concept

Encapsulation of Low Density Materials for the First Stage of Fast Ignition Realization Experiment (FIREX-I) - Control of Microstructure and Gelation Process using a Phase-Transfer Catalyst and Tailored Polymers

Target Fabrication for Sandia's Z-Pinch Accelerator

Upgrading the General Atomics Radio-Frequency Sources for Higher Power

Numerical Simulations of Transient Electromagnetic Processes for ITER Thermal Shield Design

Computational Analysis of the Magnetic Intervention Concept for First Wall Protection from Energetic Ions in a Direct Drive Laser Fusion Chamber

Dose Measurement and Analysis of EAST in the 2007 Spring Experiment

The numerical simulation of two-phase flow heat transfer of the dual-coolant waste transmutation blanket for the FDS-I

Flow Optimization Studies for the ITER Shield Modules

The Princeton FRC Rotating-Magnetic-Field-Experiment RF System

Low Pressure Operation of Radially Convergent Beam Fusion Using Differentially-Pumped Ion Sources

Design and test of the support elements of the W7-X superconducting magnets

A powerful tool to quantitatively detect tiny amounts of 4He in a deuterium rich background for fusion research

Engineering Assessment of a National High-power Advanced Torus Experiment (NHTX)

The Compact, Four Barrel High Speed Pellet Injector For The Ignitor Experiment

NCSX Modular Coil Fabrication

Conceptual Design of a Plasma Exhaust and Fuel Recovery System for an Inertial Fusion Energy (IFE) Power Reactor

Thermo-mechanical design of the ITER Neutral Beam Injector grids for Radio Frequency Ion Source and SINGAP Accelerator

Main Results and Critical Issues of W7-X Structural Analysis

A Thermocouple Telemetry System Replacement for the DIII-D Neutral Beams

Development of a Portable Reaming Tool for the Coil Supporting Structures of Wendelstein 7-X

Analysis on Tritium Permeation and Inventory in China DFLL-TBM for ITER

Three Dimensional Neutronics Analysis of the ITER First Wall/Shield Module 13

Preliminary Probabilistic Safety Assessment of Chinese Dual Functional Lithium Lead Test Blanket Module System for ITER

Assembling and Repairing for ITER Vacuum Vessel with Mobile Parallel Robot

Neutronics Assessment of the ITER First Wall/Shield Modules

Application of Computational Fluid Dynamics analysis to the design of liquid metal technology for fusion devices

Progress in NCSX Construction

Advances in Materials Physics for IFE at DENIM

Helium pre-implantation and post-implantation effects on hydrogen isotope retention in SiC

Comparison of the Au and Ta Foil Parameters from laser Calibration of Imaging Bolometer Foils

DIII-D CAMAC Infrastructure Maintenance Experience and Upgrade Plans

FPGA-Based Pulse-Oriented Digital Acquisition System For Nuclear Detectors

The In-Vessel 3D Inspection System For ITER

Lower Hybrid Current Drive on Alcator C-Mod: System Design, Implementation, Protection, Calibration and Performance

Limiter Thermography in ADITYA Tokamak

Physical and Chemical Erosion of Li Treated ATJ Graphite for NSTX

Overview and Status of the Divertor Erosion and Vapor shielding eXperiment (DEVeX)

Sensitivity Study of Mechanical Behavior of Busbar System Designed for Wendelstein 7-X Stellarator

A Second Generation Timing System for DIII-D Timing Control

Design status of the ITER ECH Upper Launcher Steering Mirror Mechanism

Design of an imaging bolometer upgrade for JT-60U

Design status of ITER ECH upper launcher mirrors

Performance Analysis of a Hybrid IGCTs-Mechanical Dc Circuit Breaker for Quench Protection of Superconducting Magnets

Energy Storage for Power Hole Mitigation on the Electric Grid due to the ITER Neutral Beam Injector

High Power Water Load for Lower Hybrid Current Drive at 4.6 GHz on Alcator C-Mod

Grounding, DC Supplies, and Controlling Signal Issues for a Tunable Reflectometry System

National Compact Stellarator Experiment Vacuum Vessel External Flux Loops Design and Installation

Conceptual Design of the ICRH and LHCD Systems for FT-3

The Coupler Protection System Upgrade for Lower Hybrid Current Drive on Alcator C-Mod

Improved Langmuir Probe Array for DIII-D

Preliminary Design of NCSX Central Computing and Control

A Fast visible camera Divertor-imaging diagnostic on DIII-D

PCB Rogowski Sensor Designs for Plasma Current Measurement

An output LC filter with diode voltage clamp for JET Enhanced Radial Field Amplifier

Electromagnetic Analysis of Transient Forces Due to Disrupted Plasma Currents on the ITER Shield Modules

ITER Divertor Maintenance: Development of a Control System for the Remote Handling of the Divertor Cassette Mover

Thermo-fluid Exploratory Design Analysis for ITER FW/Shield Module 7

Finite Element Stress Analysis OF ITER Module 13

Thermal Analysis of the Vertical Target for the ITER Divertor Design

First Wall Qualification Testing at SNL

Neutronics Analysis of a Molten Salt Blanket for the HAPL Laser Fusion Power Plant with Magnetic Intervention

A Novel Fourier Series Simulation Tool for Pulsewidth Modulation (PWM) in Pulsed Power Systems

Conceptual Study of Integrated Chamber Core for Laser Fusion with Magnetic Intervention

Development of Damage-Resistant Metal Mirrors for Laser-IFE

21st IEEE/NPS Symposium on Fusion Engineering SOFE 05

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Conceptual Study of Integrated Chamber Core for Laser Fusion with Magnetic Intervention

Content Provider	IEEE Xplore Digital Library
Author	Raffray, A.R. Dahlgren, F. Gentile, C. Priniski, C. Robson, A.E. Rose, D. Sawan, M.E. Sethian, J. Snead, L. Sviatoslavsky, G. Wang, X.R.
Copyright Year	2007
Description	Author affiliation: Univ. of California-San Diego, La Jolla (Raffray, A.R.)
Abstract	The possibility of utilizing magnetic intervention (MI) in a laser-driven inertial fusion energy (IFE) dry wall chamber is being considered to steer away the ions from the chamber wall to more readily accessible and replaceable dump regions at the equator and poles. This paper summarizes the current status of this study, describing the overall MI chamber core configuration and layout and highlighting the key design and analysis results for the different components.
Starting Page	1
Ending Page	5
File Size	837469
Page Count	5
File Format	PDF
ISBN	9781424411931
DOI	10.1109/FUSION.2007.4337951
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	2007-06-17
Publisher Place	USA
Access Restriction	Subscribed
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	Magnetic cores Laser fusion Magnetic flux Magnetic analysis Magnetic fields Computational modeling Plasmas Physics Coils Electrons chamber inertial fusion energy magnetic intervention
Content Type	Text
Resource Type	Article

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