NDLI: The mechanical measurement system of RFX

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Volume 2 - 1993

15th IEEE/NPS Symposium Fusion Engineering Volume Two

ICH RF system data acquisition and real time control using a microcomputer system

DIII-D cryogenics control system status

DIII-D neutral beam control system operator interface

Effectiveness and constraints of using the refueling system to control fusion reactor burn

Conceptual design for the TPX Central Instrumentation and Control System

Expansion of the TFTR neutral beam computer system for D-T operations

TdeV control system upgrade

Graphical user interface of RFX control and data acquisition system

Pellet injector development and experiments at ORNL

Design and control of phased ICRF antenna airways

Application of divertor cryopumping to H-mode density control in DIII-D

The ITER divertor

TESTING OF DRY MECHANICAL VACUUNI PUMPS FOR ITER

Steady-state and plasma start-up operations for the ARIES-IV second-stability tokamak reactor

Two frequency ICRF heating of D-T plasmas on TFTR

Start-up simulations of the PULSAR pulsed tokamak reactor

ITER plasma start-up modeling

Simulation of the breakdown in TEXTOR

Plasma vertical stability and feedback control for TPX

Integrated, model based feedback control in fusion reactors

Plasma response modeling for multivariable tokamak control design

Experimental and analytical study of the electromagnetomechanics in fusion reactors

Influence of RFX engineering parameters on plasma behaviour

Tokamak Physics Experiment poloidal field design

Design methods and actual performances of conductors for the superconducting coils of tokamaks

ITER compact design

ITER EDA in-plane structural design, finite friction effects, central solenoid tension and compressive preload

ITER EDA out-of-plane structural design and analysis

US conductor R&D and small scale experiments for the ITER magnets

Study on current sharing phenomena observed during the testing of ITER prototype cable-in-conduit conductors in the FENIX test facility

Experimental estimation of energy dissipation in ITER central solenoid superconductor

Development and implementation of the TPX structural and cryogenic design criteria

TPX assembly plan

Structural design of the superconducting poloidal field coils for the Tokamak Physics Experiment

The TPX cryostat conceptual design

Detailed structural evaluation of the TPX toroidal field magnet nose region

Electromagnetic modeling of the TPX coils and the cold structure

Thermo-hydraulic analysis of the TPX superconducting toroidal field magnets

Conceptual design of the tokamak radiation shielding for the Tokamak Physics Experiment (TPX)

Assessment of a magnet system combining the advantages of cable-in conduit forced-flow and pool-boiling magnets

Modification to the Long Pulse Ion Source for operation on the Tokamak Physics Experiment (TPX)

Modifications of a barium surface conversion source for operation with RF discharge

Radio frequency power system for inductive heating in ion sources

Conceptual design for the OMEGA Upgrade Cryogenic Target Delivery System

Fast-formed liquid surfaces for inertial confinement fusion target shells

Design integration of Prometheus-H: a heavy ion inertial fusion energy reactor power plant

Design of 7.8 MJ 4 GeV Pb/sup ++/ heavy ion inertial fusion energy driver

Nuclear analysis of the first wall/blanket/shield of the Prometheus inertial fusion energy reactors

Nuclear analysis for the blanket and shield of the KrF laser driven inertial fusion reactor SOMBRERO

Thermal and structural analysis of the first wall in the SIRIUS-P reactor

Recent progress and future prospects of the JT-60 program

The TPX superconducting magnet system

The TPX magnet R&D program

The TPX superconducting magnet fabrication process

Quench detection & instrumentation for the Tokamak Physics Experiment magnets

The Princeton Beta Experiment-Modification's advanced tokamak program

Start-up and early results from Alcator C-MOD

TFTR DT preparation project status

Physics design requirements for the Tokamak Physics Experiment (TPX)

Status of machine and operation of JT-60

High heat flux experiments of plasma facing components for next fusion devices

TPX divertor design: neutral atom behavior and optimization for pumping

TPX divertor design

TPX poloidal limiter design

Electromagnetically plugged gaseous divertors [fusion reactor]

Performance of the PBX-M passive plate stabilization system

A high performance water-cooled thermal shield device

Transport of energetic ion and electron energy through the vapor shield during a tokamak plasma disruption

Optimization studies on interfacial mechanical strength in the graphite-copper bonded structure for a divertor application

Development of low-Z divertor plate material with functionally gradient material layer

Manufacturing and testing of a relevant scale mockup based on monoblock concept

Operation of the Alcator C-MOD power system

Alternator control system for the Alcator C-MOD tokamak

Ground fault monitoring in Alcator C-MOD

Direct current interrupting system using an iron core for quench protection of the superconducting coil

Upgrade of DIII-D toroidal magnetic field power supply controls

TFTR ECS safety ground switch soft close modification

The power supply and control system for the MM-2U neutral beam injector

TPX power systems design overview

TPX poloidal field (PF) power systems simulation

Neutral beam power system for TPX

Limitations of power conversion systems under transient loads and impact on the pulsed tokamak power reactor

Characterization of oxide breakup by convective currents [fusion reactor]

Chemical and Waste Management Tracking and Report-Generating Systems

Activation and waste disposal of the ARIES-II tokamak fusion power reactor

Environmental and safety assessment of the inertially confined direct drive laser fusion power reactor SIRIUS-P

A systems module for environmental and safety assessment in fusion reactor studies-illustrative results for HT-9 structures

Assessment of personnel accessibility in the Particle Beam Fusion Accelerator facility PBFA-II

Environment source terms for a few NET plant reference accident sequences

Preliminary occupational radiation exposure evaluation related to NET II/ITER

A complete loss of coolant accident (LOCA) analysis for the inboard component of ITER CDA

Impact of environmental regulations on control of copper ion concentration in the DIII-D cooling water system

Tokamak Physics Experiment safety analyses and enviromental safety, and health compliance activities

Dynamic tritium accountancy for ITER

Correlation of tritium outgassing from metal surfaces with surface smearing

Tritium outgassing from solid waste

Installation of Decon facility in preparation for TFTR D-T operations

Research and development assessments for Prometheus heavy ion and laser driven inertial fusion energy reactor designs

The Prometheus IFE reactor cavity

Industry cooperates to advance IFE reactor design-the results of Prometheus

An integrated test facility for inertial fusion energy using heavy ion drivers

Generation of sawtooth and square waveforms for heavy ion induction accelerator cells using impedance tapered PFN's

Requirements for U.S. regulatory approval of the International Thermonuclear Experimental Reactor (ITER)

Preparations for deuterium-tritium operations at TFTR

The Tokamak Fusion Test Reactor tritium systems test contractor operational readiness review

Recommended in-vessel tubing failure rates for the International Thermonuclear Experimental Reactor

Safety analyses of the ARIES-II and ARIES-IV tokamak reactor designs

Argon frost continuous cryopump for fusion applications

Installation and initial operation of the DIII-D advanced divertor cryocondensation pump

Performance characteristics of the DIII-D advanced divertor cryopump

Design, control and operation of the vacuum and gas systems for Alcator C-Mod

Conceptual design of the vacuum pumping system for the Tokamak Physics Experiment

RF modeling and design of a folded waveguide launcher for the Alcator C-Mod tokamak

ICRH system for the Ignitor machine

Antennas for ICRF heating in the Alcator C-Mod tokamak

4 MW upgrade to the DIII-D fast wave current drive system

Experimental test of a two-port decoupler in the DIII-D fast wave current drive system

Upgrading and operating of the 80 MHz transmitter on the Alcator C-MOD tokamak

Design of folded waveguide antenna for Alcator C-Mod

Feedback controlled hybrid fast ferrite tuners

Performance of the DIII-D 110 GHz ECH system during the first year of operations and testing

Operational upgrades to the DIII-D 60 GHz electron cyclotron resonant heating system

Compact ITER-relevant ECH beam steering antenna design

Experimental study of megawatt gyrotrons

Quasi-optical mode converters for high order mode gyrotrons

Determination of vacuum pumping characteristics for an evacuated ECH circular waveguide system

Mean time between failures (MTBF) and availability of the gyrotron system used on the microwave tokamak experiment at Lawrence Livermore National Laboratory

Repair of poloidal field magnets on Alcator C-Mod

Development of high strength electrical connections using copper electrodeposition

Anomalous behaviour in ICCS

MHD-driven internal coils for tokamak divertor operation

Modelling of quench in CICC with a central channel in the conduit

Analytic and numerical theory of quench in CICC

A new integrated 3D pulsed losses and heat removal code for ICCS magnets

Status and test results of the Tokamak-15 superconducting toroidal field coil

The mechanical measurement system of RFX

Strength considerations on the magnetic field coils of the Spanish Stellarator TJ-II

Drastic improvement of I/sub c/ of Nb/sub 3/Sn CIC conductor by prestraining at room temperature

Computational model of surface ablation from tokamak disruptions

Methodology for first wall design

Surface impurity removal from DIII-D graphite tiles by boron carbide grit blasting

Upgrade of the DIII-D vacuum vessel protection system

Thermal hydraulic analysis of the TPX plasma facing components

Design of the TPX limiter and armor components

Structural analysis of the TPX plasma facing components

Aspect ratio effects on heat transfer in MHD laminar flow through rectangular channels in the plasma facing components of fusion reactors

Heat transfer in MHD laminar flow through a rectangular channel in the plasma facing components of fusion reactors

Evaluation of porous media heat exchangers for plasma facing components

Conference Author Index

Implementation of a quasi-realtime display of DIII-D neutral beam heating waveforms

Two-gigawatt burst-mode operation of the intense microwave prototype (IMP) free-electron laser (FEL) for the microwave tokamak experiment (MTX)

Volume 1 - 1993

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

IEEE Thirteenth Symposium on Fusion Engineering

The mechanical measurement system of RFX

Content Provider	IEEE Xplore Digital Library
Author	Zaccaria, P.
Copyright Year	1993
Description	Author affiliation: Gruppo di Padova per Richerche sulla Fusione, Padova Univ., Italy (Zaccaria, P.)
Abstract	The mechanical behaviour of the RFX machine is monitored during the pulses and the baking operations, both to verify the agreement between the actual and the design values of strains and displacements and to assess the effects of possible faults or anomalous operations of the machine. A specific measurement system was designed to provide quasistatic and dynamic measurements of strains and displacements. The paper describes the criteria which guided the design of the system, pointing out the specific requirements which had to be met to obtain a complete and correct mechanical information of the machine, as confirmed by the first results obtained during the RFX operations.
Starting Page	1158
Ending Page	1161
File Size	488839
Page Count	4
File Format	PDF
ISBN	0780314123
DOI	10.1109/FUSION.1993.518528
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	1993-10-11
Publisher Place	USA
Access Restriction	Subscribed
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	Mechanical variables measurement Coils Condition monitoring Strain measurement Assembly Time measurement Displacement measurement Noise measurement Electromagnetic measurements Position measurement
Content Type	Text
Resource Type	Article

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