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Robert Pearce et al. July 2007, 51st IUVSTA, Sweden. 1 of 16 slides RJH Pearce RJH Pearce 1,2, 1,2,3 , C Lowry , C Lowry 3 , C Day , C Day 4 ,V Hauer ,V Hauer 4 , MEP , MEP Wykes Wykes 3, 3, . Requirements and progress in vacuum Requirements and progress in vacuum modeling on ITER. modeling on ITER. 1 EFDA CSU EFDA CSU- Garching Boltzmannstr. 2, D Garching Boltzmannstr. 2, D- 85748 Garching bei M 85748 Garching bei München Germany nchen Germany 2 EURATOM/UKAEA Fusion Association, EURATOM/UKAEA Fusion Association, Culham Culham Science Centre, OX143DB Science Centre, OX143DB Abingdon Abingdon , UK , UK 3 ITER IT, Centre de Cadarache, 13108 Saint ITER IT, Centre de Cadarache, 13108 Saint- Paul Paul- Lez Lez- Durance, Durance, France. France. 4 4 FZK Karlsruhe, Germany. FZK Karlsruhe, Germany.

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Page 1: Requirements and progress in vacuum modeling on …lss.fnal.gov/conf/C070709.13/RJH_Pearce.pdfFusion power (1997) 16MW Plasma major radius 6.2m Plasma minor radius 2.0m Vessel height

Robert Pearce et al. July 2007, 51st IUVSTA, Sweden.1

of 16 slides

RJH PearceRJH Pearce1,2,1,2,33, C Lowry, C Lowry33, C Day, C Day44,V Hauer,V Hauer44, MEP , MEP

WykesWykes3, 3, ..

Requirements and progress in vacuum Requirements and progress in vacuum modeling on ITER.modeling on ITER.

11EFDA CSUEFDA CSU--Garching Boltzmannstr. 2, DGarching Boltzmannstr. 2, D--85748 Garching bei M85748 Garching bei Müünchen Germanynchen Germany

22EURATOM/UKAEA Fusion Association, EURATOM/UKAEA Fusion Association, CulhamCulham Science Centre, OX143DB Science Centre, OX143DB AbingdonAbingdon, UK, UK33ITER IT, Centre de Cadarache, 13108 SaintITER IT, Centre de Cadarache, 13108 Saint--PaulPaul--LezLez--Durance, Durance, France.France.

4 4 FZK Karlsruhe, Germany.FZK Karlsruhe, Germany.

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SummarySummary

•• Introduction to ITERIntroduction to ITER•• DivertorDivertor design and torus operational pumping design and torus operational pumping

optimisationoptimisation. . •• Mitigation and Abnormal event modeling. Mitigation and Abnormal event modeling. •• Modeling of plasma breakdown. Modeling of plasma breakdown. •• Modeling of leaks Modeling of leaks •• Wish list for codesWish list for codes

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Introduction to ITERIntroduction to ITERInternational Thermo Nuclear Reactor (ITER)

ITER (“the way” in Latin) is the essential next step in the development of fusion.

Objective is to demonstrate the scientific and technological feasibility of fusion power.

Will take over from JET as the world’s largest fusion energy research project.

Biggest international scientific project since the space station

Will be built at Cadarache near Aix-en

-Provence, France.

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International CollaborationInternational Collaboration7 Parties, signed up, November 2006

Represents approx. half the worlds population

Main supply for ITER is split between the Parties.

Technological split will produces interesting challenges.

Current target is to achieve first plasma in March 2016

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Main ParametersMain Parameters

Vessel major radius 3mVessel minor radius 1.2mVessel height 4.2 m Vacuum volume 189m3

Plasma volume ~100m3

Plasma current to 4.6MA (7MA)Toroidal Magnetic field to 4 TPulse length ~30sAdditional Heating ~30MWFusion power (1997) 16MW

Plasma major radius 6.2mPlasma minor radius 2.0mVessel height 10.2mVacuum volume 1400m3

Plasma volume ~837m3

Plasma current to 15MA Toroidal magnetic field 5.3 TPulse length ~400sAdditional Heating ~73MWFusion power (expected) 500MWCryostat volume 8000m3

JETJET ITERITER

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Objective for 2016Objective for 2016

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DivertorDivertor design and torus operational design and torus operational pumping pumping optimisationoptimisation..

•• DivertorDivertor used for impurity, and used for impurity, and helium ash removal. helium ash removal.

•• On JET you have high pumping On JET you have high pumping speed + ability to have very high speed + ability to have very high fueling rate in fueling rate in divertordivertor. .

•• Neutral pressure in Neutral pressure in divertordivertor lead to lead to ““detachmentdetachment”” hence power flux hence power flux control. control.

•• Polyamide mesh used on JET to try Polyamide mesh used on JET to try to reduce conductance on neutrals to reduce conductance on neutrals back from back from divertordivertor to main chamber.to main chamber.

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ITER ITER divertordivertor•• On ITER the there is lower pumping speed than On ITER the there is lower pumping speed than

JET. JET. •• Maximum average fuelling rate is also limited Maximum average fuelling rate is also limited

(currently 120 Pam (currently 120 Pam 3 3 S for DT) S for DT) •• Expected that Pressures 1Expected that Pressures 1--10 Pa required in 10 Pa required in

divertordivertor for desired detachment. for desired detachment. •• Expect to have to optimize Expect to have to optimize divertordivertor design for design for

““gas leakagegas leakage””•• Require conductance to torus Require conductance to torus cryocryo pumps for pumps for

molecular and transition flow. molecular and transition flow. •• Require to understand if Require to understand if cryopumpcryopump entry valve entry valve

can be used for can be used for divertordivertor pressure control. pressure control.

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FZK will use ITERVAC to :FZK will use ITERVAC to :--

•• Develop a full network model of the ITER Develop a full network model of the ITER divertordivertor and pumping connections.and pumping connections.

•• Accurately simulate the Accurately simulate the divertordivertor region a region a comprehensive 3D matrix is required comprehensive 3D matrix is required including including divertordivertor dome slots, dome slots, toroidaltoroidalchannels, channels, divertordivertor carrier slots, gaps carrier slots, gaps between cassettes, paths between between cassettes, paths between cassette and vessel, path between cassette and vessel, path between cassette and vertical targets, mountings cassette and vertical targets, mountings gaps, blockages caused by diagnostics gaps, blockages caused by diagnostics and cooling pipes. and cooling pipes.

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Molecular Flow ConductanceMolecular Flow ConductanceAwait MOVAK3D Await MOVAK3D calculations for total calculations for total molecular flow molecular flow pumping speed for pumping speed for current reference current reference design. design.

Fag packet Fag packet calculations give calculations give >100m>100m33/s for 4 /s for 4 pumps.pumps.

Previous Restricted Previous Restricted pumping configuration gave pumping configuration gave ~28 m~28 m33/s for 4 pumps./s for 4 pumps.

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Mitigation and Abnormal Mitigation and Abnormal Event ModelingEvent Modeling

ITER is a very complex collection of inter related systems. We hITER is a very complex collection of inter related systems. We have to ave to ensure that we design for fault tolerance an ensure that there pensure that we design for fault tolerance an ensure that there problems do roblems do not cascade. Contract just being placed to analyze fault sequencnot cascade. Contract just being placed to analyze fault sequences and to es and to model some key areas which may include: model some key areas which may include: --

•• Response of the cryostat Response of the cryostat cryocryo--pumps to a sudden high helium gas load pumps to a sudden high helium gas load caused by a cryogenic break. caused by a cryogenic break.

•• The The cryocryo--pumps response to and recovery from water ingresses. pumps response to and recovery from water ingresses. •• Tritium permeation into the helium circuits during high temperatTritium permeation into the helium circuits during high temperature ure

regenerations. regenerations. •• Maintenance of pumping capability during increased gas loads forMaintenance of pumping capability during increased gas loads for example example

from operation of the disruption mitigation massive gas injectifrom operation of the disruption mitigation massive gas injection system. on system.

Application of Direct Simulation Monte Carlo (DSMC) would be appApplication of Direct Simulation Monte Carlo (DSMC) would be appropriate ropriate for some of the transition flow situations. for some of the transition flow situations.

Tritium permeation into helium circuit could be an important issTritium permeation into helium circuit could be an important issue but ue but complex to model due to surface effects. complex to model due to surface effects.

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Initial breakdown and formation of a Initial breakdown and formation of a tokamaktokamak plasmaplasma

On JET the first consequence of poor vacuum or surface conditionOn JET the first consequence of poor vacuum or surface conditions is failure to maintain plasma breakdowns is failure to maintain plasma breakdown. .

•• A long ion path length ( ~1000m) is created by A long ion path length ( ~1000m) is created by creating a magnetic creating a magnetic hexapolarhexapolar null. A loop voltage of null. A loop voltage of ~0.6 V/m is induced, allowing ~0.6 V/m is induced, allowing PaschenPaschen breakdown breakdown with a deuterium pressure of order 5x10with a deuterium pressure of order 5x10--33 Pa in an Pa in an initial volume of ~ 7minitial volume of ~ 7m3 3 . .

•• There is some flexibility on loop voltage and preThere is some flexibility on loop voltage and pre--fill fill pressure and the initial impurity content of the gas is pressure and the initial impurity content of the gas is not so critical for the formation of this initial Townsend not so critical for the formation of this initial Townsend discharge as ionization probabilities for air and discharge as ionization probabilities for air and hydrogen isotopes are not so different. hydrogen isotopes are not so different.

•• As the fraction of ionized particles increases the As the fraction of ionized particles increases the interactions become coulomb dominated and impurity interactions become coulomb dominated and impurity radiation peaks. radiation peaks.

•• An increase in plasma current (An increase in plasma current (““burn throughburn through”” ) is ) is required to produce a stable, confined, plasma. required to produce a stable, confined, plasma.

•• The success of the transition is dependant on wall The success of the transition is dependant on wall conditions. conditions.

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Gas injection on JET for plasma Gas injection on JET for plasma breakdownbreakdown

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•• On ITER the reference is to initiate the discharge using ECRH poOn ITER the reference is to initiate the discharge using ECRH power, with wer, with either a outboardeither a outboard plasma initiation 100mplasma initiation 100m33 or a central plasma initiation of or a central plasma initiation of 340m340m33 and a loop voltage of ~0.3 V/m. and a loop voltage of ~0.3 V/m.

•• Generally this requires lower pressure ~10Generally this requires lower pressure ~10--3 3 Pa. The ECRH can also be Pa. The ECRH can also be used to assist the energy balance in the used to assist the energy balance in the ““burn throughburn through””. .

•• Modeling from an electroModeling from an electro--magnetic/radiation using TRANSMAK [magnetic/radiation using TRANSMAK [A A MineevMineevof RF of RF ] and plasma resistance using SCENPLINT gives limits for the ] and plasma resistance using SCENPLINT gives limits for the maximum impurity content for a particular ECRH power and pressurmaximum impurity content for a particular ECRH power and pressure. e.

•• The big unknown for which there is not an effective model is tThe big unknown for which there is not an effective model is the hydrogen he hydrogen isotope and impurity influx from the first wall. This is complisotope and impurity influx from the first wall. This is complex because it ex because it must :must :--

Consider outgassing from different materials (Beryllium, tungsten, Carbon, Stainless) with different surface properties and implantation histories.

Consider error fields and imperfections in confinement.

Consider leaks

Consider complex surface chemistry with impurities and oxides

Consider gas release by different mechanisms, ion induced (different energies, neutral induced, resonances near surfaces, etc)

•• JET will be converted to metal wall (Be) and hence it will be JET will be converted to metal wall (Be) and hence it will be possible to possible to partially validate a model for this if there is interest in propartially validate a model for this if there is interest in producing such a ducing such a model. model.

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Modeling of leaksModeling of leaks

Helpful if we can get a handle Helpful if we can get a handle on the responses we can expect on the responses we can expect from complex leaks.from complex leaks.

80Km of MI 80Km of MI cablecable

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Conclude with a Conclude with a ““wish listwish list”” for for a new gas modeling codea new gas modeling code

•• Direct CAD interface for physical input ( e.g. CATIA) Direct CAD interface for physical input ( e.g. CATIA) •• Dynamic to take account of transient sources, static Dynamic to take account of transient sources, static

volumes and mechanical pumps. volumes and mechanical pumps. •• Surface temperature input to cope with multiple Surface temperature input to cope with multiple

temperature zones temperature zones •• Applicable across the pressure regimes (3MPa to 1 Applicable across the pressure regimes (3MPa to 1 µµPa)Pa)•• Possible to take into account absorption and Possible to take into account absorption and desorptiondesorption

on surfaces on surfaces •• Clear transparent outputs Clear transparent outputs •• User friendly for non specialists User friendly for non specialists

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ReferencesReferences•• [1] ITER PID see technical WEB site.[1] ITER PID see technical WEB site.•• [4] A [4] A MineevMineev RF ITERRF ITER--DD--2575N22575N2•• ITER graphicsITER graphics