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10 May 2011 Presented by Y. Yang Title: Concept Design of the ITER Glow Discharge Cleaning System P38A Concept Concept Concept Concept Design of the ITER Glow Discharge Cleaning Design of the ITER Glow Discharge Cleaning Design of the ITER Glow Discharge Cleaning Design of the ITER Glow Discharge Cleaning System System System System Y. Yang 1 , S. Maruyama 1 , G. Kiss 1 , Y. Pan 2 , M. Wang 2 , T. Jiang 2 , B. Li 2 1 ITER Organization, Route de Vinon sur Verdon, 13115 St. Paul-Lez-Durance, France 2 Southwestern Institute of Physics, Chengdu, P.R. China Corresponding Author: Corresponding Author: Corresponding Author: Corresponding Author: Yu YANG [email protected] Tel: +33 (0) 4 42 17 63 24 Abstract Abstract Abstract Abstract: The concept design of ITER Glow Discharge Cleaning (GDC) system based on the present ITER baseline is introduced. This presentation lists the over-all description of the requirements, including the main function, GDC parameters, working positions at different states, main interfacing systems. The concept design for implementation is introduced. The near term plan is discussed. ITER and its Wall Conditioning ITER and its Wall Conditioning ITER and its Wall Conditioning ITER and its Wall Conditioning Acknowledgement: Acknowledgement: Acknowledgement: Acknowledgement: The authors would like to thank M. Shimada, R. Pitts, E. Polunovskiy and J. Palmer in ITER Organization, for the helpful discussion on physics, nuclear analysis and remote handling. This paper was prepared as an account of work by or for the ITER Organization. The Members of the Organization are the People's Republic of China, the European Atomic Energy Community, Republic of India, Japan, Republic of Korea, the Russian Federation, and the United States of America. The views and opinions expressed herein do not necessarily reflect those of the Members or any agency thereof. Dissemination of the information in this paper is governed by the applicable terms of the ITER Joint Implementation Agreement. Design requirements and design boundary conditions Design requirements and design boundary conditions Design requirements and design boundary conditions Design requirements and design boundary conditions The main function of ITER GDC system is to reduce and control impurity and hydrogenic fuel out-gassing, particularly oxygen, from plasma-facing components. The design of the GDC shall provide suitable nuclear shielding for the systems that are behind the electrode during the plasma operation. GDC concept design based on the present baseline GDC concept design based on the present baseline GDC concept design based on the present baseline GDC concept design based on the present baseline Open questions Open questions Open questions Open questions Service lines (cooling and electrical) Service lines (cooling and electrical) Service lines (cooling and electrical) Service lines (cooling and electrical) International Thermonuclear Experimental Reactor http://www.iter.org/ ITER, currently under construction in the South of France, aims to demonstrate that fusion is an energy source of the future” “Wall conditioning for ITER-limit the outgassing, T inventory in PFCs Baking (superconducting coils between 5 K and 293 K) blankets at about 240°C divertor up to 350°C vacuum vessel and the other in-vessel components at 200°C all other surfaces exposed to the primary vacuum >180°C Lower temperature at or beyond the vessel ports boundary treated on a case-by-case basis. DC GDC (Hydrogen, Deuterium, and Helium) RF (IC/EC) wall conditioning (between pulses) GDC parameters GDC parameters GDC parameters GDC parameters DC GDC is used in the present baseline design, which requires the magnetic fields to be zero. Taking j=0.15 A/m 2 , and ITER internal area be 1000 m 2 . Total GDC current shall be about 150 A. Vacuum conditions: 0.1-0.5 Pa – Operating temperature: up to 350°C Baking temperature: up to 240°C Nucl. Shielding Nucl. Shielding Nucl. Shielding Nucl. Shielding Integrated with In Vessel Viewing System (IVVS) Integrated with In Vessel Viewing System (IVVS) Integrated with In Vessel Viewing System (IVVS) Integrated with In Vessel Viewing System (IVVS) GDC/IVV GDC/IVV GDC/IVV GDC/IVV GDC/IVV GDC/IVV GDC needs to be integrated with IVVS, which similarly requires uniform coverage. There are six sets of GDC/IVVS assembly on ITER. Heat load Heat load Heat load Heat load VV PF TF Nuclear heat in TF assembly & PF coils; Helium concentration & DPA level in steel in the vicinity. During plasma operation, Nuclear heating Radiation and charge exchange 29 kW each electrode at maximum. During GDC, the rejected power at nominal operation is 0.7 kW per electrode, calculated from the anode voltage drop (~20V) times current plus ohmic heating. -ITER Design Description Document 2001 version Electrode Electrode Electrode Electrode Cleaning Cleaning Cleaning Cleaning Plasma Operation Plasma Operation Plasma Operation Plasma Operation Material candidates: Be, stainless steel, Copper alloy. Cap (CuCrZr) Jacket (316LN) Total Mass ~ 250 kg Total Mass ~ 250 kg Total Mass ~ 250 kg Total Mass ~ 250 kg Shell (316LN) Core rod (CuCrZr) [316LN] [316LN] GDC probe structure IVVS deployment will provide the service for moving GDC electrode among different positions. Cleaning Cleaning Cleaning Cleaning Plasma Operation Plasma Operation Plasma Operation Plasma Operation Two step deployment Two step deployment Two step deployment Two step deployment A booster water pump is used for ensuring enough cooling water flow-rate. Connection to the “Drain” is for the depressurization of the high pressure water loop. Internal pressure~4MPa. Tmax~350 degree C. Length~7 meters. Moving at 10mm/s for ~6meters. A few times a month. ~ 7 m Near term work plan Near term work plan Near term work plan Near term work plan Physics Physics Physics Physics Engineering Engineering Engineering Engineering Glow distribution. Heat load on the electrode during DC GDC. Plasma facing material selections. Bellows. Electrical cable, connector and feed- through. Electrical insulation. Anti-arcing. Electrode temperature measurement. Nuclear analysis Possibility of decoupling the glow and shielding functions. Deciding the nuclear shielding position. Mechanical design for a lighter electrode head. Study for isolation of the port and the main chamber. Further research on in vessel space sharing with IVVS. These need to be answered before the end of 2011. These need to be answered before the end of 2011. These need to be answered before the end of 2011. These need to be answered before the end of 2011. Main function of GDC Main function of GDC Main function of GDC Main function of GDC Flexible connection: Flexible connection: Flexible connection: Flexible connection:

Concept Design of the ITER Glow Discharge Cleaning Concept ... · 10 May 2011 Presented by Y. Yang Title: Concept Design of the ITER Glow Discharge Cleaning System P38A Concept Design

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Page 1: Concept Design of the ITER Glow Discharge Cleaning Concept ... · 10 May 2011 Presented by Y. Yang Title: Concept Design of the ITER Glow Discharge Cleaning System P38A Concept Design

10 May 2011Presented by Y. YangTitle: Concept Design of the ITER Glow Discharge Cleaning SystemP38A

Concept Concept Concept Concept Design of the ITER Glow Discharge Cleaning Design of the ITER Glow Discharge Cleaning Design of the ITER Glow Discharge Cleaning Design of the ITER Glow Discharge Cleaning SystemSystemSystemSystem

Y. Yang1, S. Maruyama1, G. Kiss1, Y. Pan2, M. Wang2, T. Jiang2, B. Li2

1 ITER Organization, Route de Vinon sur Verdon, 13115 St. Paul-Lez-Durance, France2 Southwestern Institute of Physics, Chengdu, P.R. China

Corresponding Author: Corresponding Author: Corresponding Author: Corresponding Author: Yu YANG [email protected] Tel: +33 (0) 4 42 17 63 24

AbstractAbstractAbstractAbstract:The concept design of ITER Glow Discharge Cleaning (GDC) system based on the present ITER baseline is introduced. This presentation lists the over-all description of the requirements, including the main function, GDC parameters, working positions at different states, main interfacing systems. The concept design for implementation is introduced. The near term plan is discussed.

ITER and its Wall ConditioningITER and its Wall ConditioningITER and its Wall ConditioningITER and its Wall Conditioning

Acknowledgement: Acknowledgement: Acknowledgement: Acknowledgement: The authors would like to thank M. Shimada, R. Pitts, E. Polunovskiy and J. Palmer in ITER Organization, for the helpful discussion on physics, nuclear analysis and remote handling.This paper was prepared as an account of work by or for the ITER Organization. The Members of the Organization are the People's Republic of China, the European Atomic Energy Community, Republic of India, Japan, Republic of Korea, the Russian Federation, and the United States of America. The views and opinions expressed herein do not necessarily reflect those of the Members or any agency thereof. Dissemination of the information in this paper is governed by the applicable terms of the ITER Joint Implementation Agreement.

Design requirements and design boundary conditionsDesign requirements and design boundary conditionsDesign requirements and design boundary conditionsDesign requirements and design boundary conditions

� The main function of ITER GDC system is to reduce and control impurity and hydrogenic fuel out-gassing, particularly oxygen, from plasma-facing components.

� The design of the GDC shall provide suitable nuclear shielding for the systems that are behind the electrode during the plasma operation.

GDC concept design based on the present baselineGDC concept design based on the present baselineGDC concept design based on the present baselineGDC concept design based on the present baseline

Open questionsOpen questionsOpen questionsOpen questions

Service lines (cooling and electrical)Service lines (cooling and electrical)Service lines (cooling and electrical)Service lines (cooling and electrical)

International Thermonuclear Experimental Reactor

http://www.iter.org/

“ITER, currently under construction in the South of France, aims to demonstrate that fusion is an energy source of the future”

“Wall conditioning for ITER”

-limit the outgassing, T inventory in PFCs

� Baking (superconducting coils between 5 K and 293 K)

blankets at about 240°C

divertor up to 350°C

vacuum vessel and the other in-vessel components at 200°C

all other surfaces exposed to the primary vacuum >180°C

Lower temperature at or beyond the vessel ports boundary treated on a case-by-case basis.

� DC GDC (Hydrogen, Deuterium, and Helium)

� RF (IC/EC) wall conditioning (between pulses)

GDC parametersGDC parametersGDC parametersGDC parameters

DC GDC is used in the present baseline design, which requires the magnetic fields to be zero.

Taking j=0.15 A/m2, and ITER internal area be 1000 m2. Total GDC current shall be about 150 A.

– Vacuum conditions: 0.1-0.5 Pa

– Operating temperature: up to

350°C

– Baking temperature:

up to 240°C

Nucl. ShieldingNucl. ShieldingNucl. ShieldingNucl. Shielding

Integrated with In Vessel Viewing System (IVVS)Integrated with In Vessel Viewing System (IVVS)Integrated with In Vessel Viewing System (IVVS)Integrated with In Vessel Viewing System (IVVS)

GDC/IVV

GDC/IVV

GDC/IVV

GDC/IVV

GDC/IVV

GDC/IVV

� GDC needs to be integrated with IVVS, which similarly requires uniform coverage.

� There are six sets of GDC/IVVS assembly on ITER.

Heat loadHeat loadHeat loadHeat load

VV

PFTF

� Nuclear heat in TF assembly & PF coils;

� Helium concentration & DPA level in steel in the vicinity.

During plasma operation,

� Nuclear heating

� Radiation and charge exchange

29 kW each electrode at maximum.

During GDC, the rejected power at nominal operation is 0.7 kW per electrode, calculated from the anode voltage drop (~20V) times current plus ohmic heating.

-ITER Design Description Document 2001 version

ElectrodeElectrodeElectrodeElectrode

CleaningCleaningCleaningCleaningPlasma OperationPlasma OperationPlasma OperationPlasma Operation

Material candidates:

� Be,

� stainless steel,

� Copper alloy.

Cap (CuCrZr)

Jacket (316LN)

Total Mass ~ 250 kgTotal Mass ~ 250 kgTotal Mass ~ 250 kgTotal Mass ~ 250 kg

Shell (316LN)

Core rod (CuCrZr)

[316LN]

[316LN]

GDC probe structure

IVVS deployment will provide the service for moving GDC electrode among different positions.

CleaningCleaningCleaningCleaning

Plasma OperationPlasma OperationPlasma OperationPlasma Operation

Two step deploymentTwo step deploymentTwo step deploymentTwo step deployment

� A booster water pump is used for ensuring enough cooling water flow-rate.

� Connection to the “Drain” is for the depressurization of the high pressure water loop.

� Internal pressure~4MPa.

� Tmax~350 degree C.

� Length~7 meters.

� Moving at 10mm/s for ~6meters. A few times a month.

~ 7 m

Near term work planNear term work planNear term work planNear term work plan

PhysicsPhysicsPhysicsPhysics EngineeringEngineeringEngineeringEngineering

� Glow distribution.

� Heat load on the electrode during DC GDC.

� Plasma facing material selections.

� Bellows.

� Electrical cable, connector and feed-through.

� Electrical insulation.

� Anti-arcing.

� Electrode temperature measurement.

� Nuclear analysis

� Possibility of decoupling the glow and shielding functions.

� Deciding the nuclear shielding position.

� Mechanical design for a lighter electrode head.

� Study for isolation of the port and the main chamber.

� Further research on in vessel space sharing with IVVS.

These need to be answered before the end of 2011.These need to be answered before the end of 2011.These need to be answered before the end of 2011.These need to be answered before the end of 2011.

Main function of GDCMain function of GDCMain function of GDCMain function of GDC

Flexible connection:Flexible connection:Flexible connection:Flexible connection: