NDLI: Engineering a remote survey of JET's divertor structure under conditions of restricted access using digital photogrammetry

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Volume 2 - 1998

Recent advances and challenges for diode-pumped solid-state lasers as an inertial fusion energy driver candidate

Status of direct-drive laser fusion target designs

KrF lasers for inertial fusion energy

Systems modeling for heavy ion drivers-an induction linac example

Engineering physics inside the LMJ target chamber

Fabrication and the modeling of large diameter fuel capsules for laser fusion

Issues for fielding large experiment packages in NIF and implications for IFE target chamber research

A multilayered annular liquid metal jet blanket concept for ICF reactors

Prospects for 2 mm diameter NIF polymer capsules

Recent progress on the International Thermonuclear Experimental Reactor (ITER) magnet systems

ITER plasma shaping capability: comparison of alternative magnetic configurations

National Spherical Torus Experiment (NSTX) center stack design and assembly

KSTAR poloidal and toroidal field design

The KSTAR superconducting magnet system

Rebuilding of the HT-7 TF coil current leads

Design and reconstruction of the nitrogen screen system for HT-7 superconducting tokamak

Support structure of toroidal field magnet system of SST-1

Design of the ohmic system for SST-1

SST-1 poloidal field magnets

Restoration of the DIII-D solenoid

Thermal analysis and testing for DIII-D ohmic heating coil repair

Analysis and testing of the DIII-D ohmic heating coil lead repair clamp

Structural analysis of the International Thermonuclear Experimental Reactor magnet system: comparative study of two central solenoid configurations

Alternative poloidal field configurations for ITER

Evaluation of insulation shear stresses in the ITER central solenoid

Engineering overview of the ITER hybrid central solenoid

Experiment of current imbalance in superconducting cable strands

Calculations for the coupled resonant circuits of the dynamic ergodic divertor coils at TEXTOR-94 and consequences for their power supplies

The engineering design of the dynamic ergodic divertor (DED) for TEXTOR-94

Effects of the fast discharge system on the ITER poloidal and toroidal field circuits

3D, coupled electromagnetic, thermal, current diffusion in the finger joints of the Alcator C-Mod toroidal field coils

Power and particle exhaust in tokamaks

The design of the Korea Superconducting Tokamak Advanced Research (KSTAR)

Advanced regimes in ITER with non-inductive current drive

Physics and systems design analyses for spherical torus (ST) based VNS

Engineering issues of gridded inertial electrostatic confinement devices

Evolution of field-reversed configuration by flux enhancement with rotating magnetic field

Preliminary studies of potential well measurement in inertial-electrostatic confinement fusion experiments

Prospects for electron cyclotron current drive stabilization of neoclassical tearing modes in ITER

Q, break-even and the n/spl tau//sub E/ diagram for transient fusion plasmas

Edge plasma analyses for KSTAR divertor design

Using the Internet for plasma physics education

ITER fusion performance projections and operation modeling

Diagnostics for the Korea Superconducting Tokamak Advanced Research (KSTAR) project

Design of a ferroelectric bolometer

Development of improved methods for remote access of DIII-D data and data analysis

Overview of the DIII-D program computer systems

Experiences with remote collaborations in fusion research

Central Thomson scattering upgrade on DIII-D

Mechanical design of the TFTR poloidal rotation diagnostic

Development of a precise long-time digital integrator for magnetic measurements in a tokamak

Upgrade of the TEXTOR-94 data acquisition system for plasma diagnostics

Recent improvements to the DIII-D neutral beam instrumentation and control system

Software development on the DIII-D control and data acquisition computers

Advances in the operation of the DIII-D neutral beam computer systems

Use of the accessware interface/database software in the neutral beam control systems used by the DIII-D tokamak

Design and construction of a stationary magnetic field sensor [fusion technology]

Effects of resonance absorption in fusion device heterogeneous media

Nuclear heating and damage profiles in the ITER divertor cassette

Three-dimensional analysis of nuclear heating in the superconducting magnet system due to gamma-rays from /sup 16/N in the ITER water cooling system of the shielding blanket

Neutronics analysis of a spherical torus based volumetric neutron source

Measurement of radioactivity in mixed D-T and D-D neutron field at TFTR

The potential use of zirconium-based alloys in fusion power plants

GlidCop(R) AL-25 first wall plates-IG1 grade compared to IG0 grade

Prospects of the cylindrical IEC fusion device as a neutron source

Degradation of plasma facing materials due to severe thermal shocks

Development of lithium deposition techniques for TFTR

DOLLOP (deposition of lithium by laser outside of plasma)-an overview [fusion materials]

Ablation measurement technique for fusion reactor components

Hydrogen isotope retention in B/sub 4/C coating on RGT graphite under high heat fluxes of DIII-D divertor plasma

Plasma-sprayed coatings for plasma-facing components

Development of tungsten brush structures for PFC armor applications

Melt layer erosion and resolidification of metallic plasma facing components

Beryllium-copper diffusion bonding for an ITER first wall application

A comparison of stresses in armor joints with and without interlayers

Steady-state impurity control, heat removal and tritium recovery by moving-belt plasma-facing components

Development of tungsten coatings for ITER divertor components

Assembly of the ITER tokamak

Development of bore tools for blanket cooling pipe connection in ITER

Development of divertor cassette transporters for ITER

Remote handling test and full-scale equipment development for ITER blanket maintenance

Fabrication of full-scale sector model for ITER vacuum vessel

Manufacturing of a middle-scaled shielding blanket module for ITER

A laser metrology/viewing system for ITER in-vessel inspection

Development and fabrication of ITER divertor cassette body

ITER divertor dome manufacturing development

Preparations for the fully remote exchange of JET divertor modules

Operator interfaces for JET remote handling equipment

Engineering a remote survey of JET's divertor structure under conditions of restricted access using digital photogrammetry

Progress in the design of the ITER divertor maintenance system

Conceptual study on flexible guidance and navigation for ITER remote handling transport casks

Active docking of a transport cask vehicle subject to 6 degrees of freedom misalignments

Radiation effects on optical components of a laser radar sensor designed for remote metrology in ITER

Helium loops of an ITER HCPB test blanket module

Progress in the ITER blanket design

Profit from borating concrete in the ITER biological shield

Status of the radiation shielding analyses for ITER

High performance PbLi blanket

The European breeding blanket design for ITER

Lifetime estimation of a possible ITER EPP blanket

Design progress of the vacuum vessel for ITER

Thermal and hydraulic assessments of the cooling system for ITER vacuum vessel

Conceptual design of KSTAR vacuum vessel

Design analysis of vacuum vessel and cryostat of SST-1 tokamak

Design-point determination for the commercial spherical tokamak, ARIES-ST

A comparative assessment of centerpost design options for ARIES-ST

Assessment of markets and customers for fusion applications

A compact reversed shear tokamak reactor sustained by beam driven currents

Plasma physics basis and operations of the ARIES-ST tokamak power plant

The low aspect ratio design concept possibility of an acceptable fusion power system

Configuration and maintenance options for low aspect ratio tokamaks

A high voltage power supply for negative ion NBI based on PSM technology

Development of high power negative ion source/accelerator for ITER-NBI

Tritium consumption and retention in TFTR neutral beams

Analysis of ion source arc chamber failure and grid damage sustained during high power operation

The TFTR neutral beam pulse length limit

Compact beam line design for the SST-1 NB injector

Ion deflection system for SST-1 neutral beam injector

High voltage power supply of negative-ion based NBI for JT-60U

Comparison of calculated neutral beam shine-through with measured shine-through in DIII-D

The JET active phase gas introduction systems for neutral beam injection and beamline commissioning and operation with tritium

Experimental study of curved guide tubes for pellet injection

Pumping speed and selectivity phenomena for cryopumping of ITER relevant exhaust gas mixtures

Detailed design of the ITER primary cryopump model

The integrated KSTAR vacuum pumping system

TdeV power supplies interaction with the utility power grid

Windage loss reduction study for TFTR pulse generator

The development and testing of a 66 kA by-pass switch with arc commutation capability for the ITER coil power supply system

Power supply system for 1000s neutral beam injector

Design, construction and operation of the 66 kA life test facility for the ITER magnet protection vacuum circuit breakers

Bypass operation of the ITER AC/DC converters for reactive power reduction

Volume 1 - 1998

Proceedings of 16th International Symposium on Fusion Engineering

15th IEEE/NPSS Symposium on Fusion Engineering - Supplement,

15th IEEE/NPSS Symposium. Fusion Engineering

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering

IEEE Thirteenth Symposium on Fusion Engineering

Engineering a remote survey of JET's divertor structure under conditions of restricted access using digital photogrammetry

Content Provider	IEEE Xplore Digital Library
Author	Rlacklin, B. Brade, R. Hurd, F. Mills, S.F. Sanders, S. Stokes, R. Tait, J.
Copyright Year	1998
Description	Author affiliation: JET Joint Undertaking, Abingdon, UK (Rlacklin, B.)
Abstract	JET is currently planning to install its new Gasbox Divertor remotely. In line with JET's policy and philosophy it was decided to survey the divertor structure remotely to confirm its position, shape and integrity prior to installing the new tile configuration. A survey to metrology standards is required, i.e. with sub-millimetre accuracy. While remote surveys have been carried out in the past, they have not been to this level of accuracy.
Starting Page	961
Ending Page	964
File Size	636538
Page Count	4
File Format	PDF
ISBN	0780342267
DOI	10.1109/FUSION.1997.687784
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	1997-10-06
Publisher Place	USA
Access Restriction	Subscribed
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	Tiles Remote handling Shape Assembly Computer aided manufacturing Milling machines Metrology Charge coupled devices Digital cameras Charge-coupled image sensors
Content Type	Text
Resource Type	Article

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