Centro de Fusão Nuclear 17th TM on Research Using Small Fusion Devices Summary 3 TOPICS: G: Materials Research I: Diagnostic Systems and Components K:

17th TM on Research Using Small Fusion Devices

Centro de Fusão Nuclear

Summary 3

TOPICS:

G: Materials Research

I: Diagnostic Systems and Components

K: Control and Data Acquisition Systems and Remote Participation Tools

25 contributions



G: Materials Research

Interaction of a liquid Gallium jet with ISTTOK edge plasmas R.B. Gomes OP2

Installation of plasmatron at the Belgian Nuclear Research Centre and its use for Plasma-Wall Interaction studies I. Uytdenhouwen OP8

Novel approach to plasma facing materials in nuclear fusion reactors V. Livramento OP20

Study of plasma interaction with Titanium coated ferretic steel in IR-T1 tokamak M. Ghoranneviss P 11

Positron Lifetime Calculations of defects in α-iron containing hydrogen L.Petrov P 12



G: Materials Research (II)

Small devices are ideally suitable for test of new materials More flexible Less strict with impurity contamination

Can provide valuable information to test new materials and systems for large devices

Limitation – power density. Density much small than in the edge of large fusion devices

OT2: Liquid Gallium Limiter on ISTTOK: Lithium as PCF as been extensively investigated (US, FTU) but experiments with Gallium very limited. It has demonstrated that a Gallium is compatible with tokamak operation but power handing capabilities not assessed.

OT8: Installation of Plasmatron for plasma-wall interaction: Important to test materials and plasma wall interaction in reactor relevant conditions (power density, capability to work with Beryllium, D/T, ..)



• Cold self-sustained volumetric plasmaVolume: 18 litres Target diameter: ~25cm Ion energies: 20 - 500 eVMagnetic field: 0.2T Pulse duration: steady stateFlux density target: ~ 1020-1021 ions/m2.s

• Designed for PWI studies • Installation for operation in glove box• A gas mixture with a certain D/T ratio can be created in a

volume by measuring the pressure and the mass flow of D/T coming from volumes containing D and T. Both loops have a separate control system.

Brief plasmatron facility description

Tominetti S. et al., Vuoto 26 (1997)



G: Materials Research (III)

OT20: Novel approach for plasma facing materials: Develop functional materials to better perform the reactor wall purposes (compatible with plasma, heat removal, neutron load damage… ). Develop reactor compatible materials with higher thermal conductivity.

P11: Study of plasma interaction with Titanium coated ferretic steel in IR-T1 tokamak Plasma facing components with better properties (content

of O, N) P12: Positron Lifetime Calculations of defects in α-iron

containing hydrogen Study of the materials damage in reactors

Small Fusion Devices have an important role in Materials Research and positive results have been achieved

Plasma Focus experiments and Z-pinch used for materials tests (source of neutrons)



ObjectiveProduce a W-nDiamond composite, using High Energy milling of powders and consolidation in order to develop a suitable material for the first wall of nuclear fusion reactors.

Why Nanostructure? Nanoparticles act as effective

sink for radiation defects.

Why W?• Highest melting point;• Highest resistance to irradiation (doesn’t contaminate the plasma);• High corrosion resistance;• Doesn’t produce armful radioactive elements

Why nD?• High thermal condutivity;• Very hard material

Challenge: Avoid the carbide formation!

W-nD nanocomposite is

a good option!




Electric probes for edge plasma diagnostics in the CASTOR tokamak J. Stockel OP11

Development of a multichannel time-of-flight technique for plasma potential profile measurements by heavy ion beam diagnostic on the tokamak ISTTOK I.S.Nedzelskiy OP13

Temporal evolution of plasma rotation measurement in tokamaks using na optical monochromator and two photomultipliers as detector H. Severo OP14

Multipoint Thomson scattering diagnostic for the TCABR tokamak with centimeter spatial resolution M.P. Alonso OP16

Real -Time Digital systems for Control on Small Tokamaks B.B. Carvalho OP18




Fast tomographic methods on the tokamak ISTTOK P.J. Carvalho P13

Time scale analysis of ISTTOK probe data R. Coelho P14

Plasma spectroscopy in ISTTOK J. Figueiredo P15

O I spectral lines for diagnostics of laser induced plasmas in air at atmospheric pressure H. Hegazy P16

The Cherenkov detectors for measurements of fast electrons in CASTOR tokamak I. Jakubowski P17

Designing a new teta-function coil for measurement of plasma displacements in the IR-T1 tokamak P. Khorshid P18

Impurity line emissions in VUV region on TCABR tokamak M. Machida P19

Spectral line profile analysis using higher diffraction order in vacuum ultraviolet region M. Machida P20




Most contributions from tokamaks The large number of contributions prove that small

tokamaks have an important role in the development of diagnostics (due to its flexibility and cost efficiency) that can after be installed in larger devices

Most contribution are relevant for larger devices. Techniques can be applied to larger devices after optimization in small devices.




Configuration Control Studies in Heliotron J T. Mizuuchi IT4

Real -Time Digital Systems for Control on Small Tokamaks B.B. Carvalho OP18

New System for tokamak T-10 experimental data acquisition, data handling and remote access D. Nurov OP19

FusionTalk: a remote participation tool for nuclear fusion F. Reis P24

Design and Fabrication a new Feedback System for Control of Plasma A.Talebi Taher P25

ISTTOK Plasma Position Controller Enhancements D.F.Valcárcel P26

COMPASS control, data acquisition and communication system M. Hron P27



Recent digital technologies and tools developed at IST enable a New Paradigm

LOCAL CONTROL

PROCESSOR

D. A

CQ

UN

ITS

D. A

CQ

UN

ITS

ACTUATOR CONTROL

REMOTE PARTICIPATION

TOKAMAKPLASMA

1/10 Gb Ethernet

Db SERVER

DATA ACQ

UNITS

REAL TIME NETWORK

Sensors/Diagnostics

CENTRALCODAC

PSU

GAS PUFFING

FW

FAST SWITCH UNIT

Integrated Digital Control System, Sensors-to-Actuator, based on available low-cost technologies

General Purpose Processors: Intel, PowerPC…

Open-Source Standards and Real-Time Operating Systems: XML, CORBA, SQL, RTAI

DSP - Digital Signal ProcessorsFPGA- Field Programmable Gate Arrays

MIMO Multiple Input- Multiple Output Controller Dedicated real-time synchronous network for

event and timing distribution



User software interfaces.

Shared file storage

Application ServerBlade server unit

Services,data handling and processing routines:integrating data files;math pre-processing;compressing;transferring the data to DB;exporting/importing the data.Service1 for client programs (TCP)Service2 for remote data viewing (remote desktop).Service3 for Web browser clients (http).Service4 for aux. math calculations.

.

DAS System overview.

T-10

_||_… _||_

Experimental shots

Data MeasurementUnit.IndustrialPCs.Data is measured and saved to files.

Database Server

Raw and processed data of experiments, incl.data from other devices.

WebserverDescript.information, links to Services.

Researchers

LAN / Internet

…

Experiment staff Control workstation

Start/stop. Setting up. Data lookup.

Data equipment control utility (DAS-Unit)

Data viewer/analyzer (DAS-Tools)

User applications with integrated library modules (DAS-Access)

t

Internet browsers

Data converters for importing other fusion devices data, exporting native data into other formats.

Data




ITER control and data acquisition presents a large challenge that needs to be tested

COMPASS: new device, good opportunity test solutions for ITER

Due to wide available of new communication technologies, remote data access/operation/participation is now possible and tools have to be tested.

These tolls are essential for the small devices community as they are in general isolated/small groups.

Presentation reflect these observation reflection that these community has understood the important of Remote participation tools and its role in their development

ISTTOK JE intend to test remote participation

Documents

Centro de Fusão Nuclear 17th TM on Research Using Small Fusion Devices Summary 3 TOPICS: G: Materials Research I: Diagnostic Systems and Components K: