Halo current studies with self-consistent MHD simulations ...

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F.J. Artola, 7 th annual Theory and Simulation of Disruptions Workshop © 2019, ITER Organization Page 1 IDM UID: ITER_D_YE5HWZ Disclaimer: The views and opinions expressed herein do not necessarily reflect those of the ITER Organization Halo current studies with self-consistent MHD simulations for ITER 15 MA plasmas F.J. Artola 1 , G.T.A. Huijsmans 2 , M. Lehnen 1 , I. Krebs 3 , A. Loarte 1 1. ITER Organization, SCD, 13067 Saint Paul Lez Durance Cedex, France 2. CEA, IRFM, F-13108 Saint-Paul-Lez-Durance, France 3. Princeton Plasma Physics Laboratory, Princeton, New Jersey, USA email: [email protected]

Transcript of Halo current studies with self-consistent MHD simulations ...

Page 1: Halo current studies with self-consistent MHD simulations ...

F.J. Artola, 7th annual Theory and Simulation of Disruptions Workshop

© 2019, ITER Organization

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Disclaimer: The views and opinions expressed herein do not necessarily reflect those of the ITER Organization

Halo current studies with self-consistent

MHD simulations

for ITER 15 MA plasmas

F.J. Artola1, G.T.A. Huijsmans2, M. Lehnen1, I. Krebs3, A. Loarte1

1. ITER Organization, SCD, 13067 Saint Paul Lez Durance Cedex, France

2. CEA, IRFM, F-13108 Saint-Paul-Lez-Durance, France

3. Princeton Plasma Physics Laboratory, Princeton, New Jersey, USA

email: [email protected]

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F.J. Artola, 7th annual Theory and Simulation of Disruptions Workshop

© 2019, ITER Organization

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Outline

• The JOREK-STARWALL code for halo current modelling

• 2D VDE benchmark with M3D-C1 and NIMROD

• Understanding the 2D halo currents at ITER (15 MA/5.3T)

• Prediction of the halo properties and B.C.s

• Conclusions and future work

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The JOREK-STARWALL code

for halo current modelling

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© 2019, ITER Organization

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The JOREK-STARWALL code for halo current modelling

JOREK

• 3D non-linear MHD equations• Toroidal geometry

• C1 Finite elements in poloidal plane

• Fourier harmonics for 𝜙 direction• Fully implicit time evolution

[Huysmans, NF2007]

STARWALL

• Solves Maxwell’s equations and Ohm’s law

• Green’s function method

• Thin wall approximation

[P. Merkel, 2015]

Implicit coupling through B.C.s for 𝐵

[Hoelzl, 2012]

𝐵tan = Ԧ𝑓 𝐵𝑛, 𝒀

Tangential fieldNormal field Wall currents

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© 2019, ITER Organization

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The JOREK-STARWALL code for halo current modelling

EM boundary conditions

Reduced MHD, the E-field is

⚫ has resistive wall free-boundary conditions

⚫ Ideal wall BCs for poloidal E-field

⚫ Poloidal currents calculated from

force balance

Strong assumption. Poloidal

currents do not decay in the

wall (infinite conductivity in

the poloidal direction)

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2D VDE benchmark with

M3D-C1 and NIMROD

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© 2019, ITER Organization

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2D VDE benchmark with M3D-C1 and NIMROD

VDE based on the NSTX #139536 discharge

[I. Krebs, F.J. Art ola, C. Sovinec 2019]

Phase 1: Hot VDE until wall contact

Phase 2: Artificially triggered TQ

when the plasma becomes limited

(increasing 𝜅⊥ )

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© 2019, ITER Organization

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2D VDE benchmark with M3D-C1 and NIMROD

VDE based on the NSTX #139536 discharge

[I. Krebs, F.J. Art ola, C. Sovinec 2019]

Phase 1: Hot VDE until wall contact

Phase 2: Artificially triggered TQ

when the plasma becomes limited

(increasing 𝜅⊥ )

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Understanding 2D halo currents

at ITER (15 MA / 5.3T)

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© 2019, ITER Organization

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Understanding 2D halo currents at ITER (15 MA / 5.3T)

Halo current different regimes

⚫ Hot VDE regime

𝐼𝑝 ~ cte during VDE

⚫ Ideal wall regime

𝑍𝑎𝑥𝑖𝑠 = 𝑓(𝐼𝑝) [D. Kiramov 2017 PoP]

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Understanding 2D halo currents at ITER (15 MA / 5.3T)

Parametric scan in CQ time

Plasma resistivity is prescribed as a flux function

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Understanding 2D halo currents at ITER (15 MA / 5.3T)

Scan in CQ time (scaling plasma resistivity profile)

𝐼 ℎ𝑎𝑙𝑜/𝐼 𝑝0(%

)

𝜏𝐶𝑄/𝜏𝑤 (Log-scale)

• Strong dependence on

CQ time to wall time ratio

(𝝉𝑪𝑸/𝝉𝒘)

• Maximum at 𝜏𝐶𝑄/𝜏𝑤 → ∞

Halo currents stabilize

VDE

• Minimum at 𝜏𝐶𝑄/𝜏𝑤 → 0

Eddy currents stabilize

VDE

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© 2019, ITER Organization

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Understanding 2D halo currents at ITER (15 MA / 5.3T)

Scan in CQ time (scaling plasma resistivity profile)

𝐼 ℎ𝑎𝑙𝑜/𝐼 𝑝0(%

)

𝜏𝐶𝑄/𝜏𝑤 (Log-scale)

• Strong dependence on

CQ time to wall time ratio

(𝝉𝑪𝑸/𝝉𝒘)

• Maximum at 𝜏𝐶𝑄/𝜏𝑤 → ∞

Halo currents stabilize

VDE

• Minimum at 𝜏𝐶𝑄/𝜏𝑤 → 0

Eddy currents stabilize

VDE

CAT I I EM loads(up to 300 events

at 15 MA)

CAT I EM loads

(up to 3000 events

at 15 MA)

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F.J. Artola, 7th annual Theory and Simulation of Disruptions Workshop

© 2019, ITER Organization

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Understanding 2D halo currents at ITER (15 MA / 5.3T)

Halo current different regimes

⚫ Hot VDE regime

➢ Cold halo

➢ Hot halo

⚫ Ideal wall regime

➢ Cold halo

➢ Hot halo

also discussed in [Boozer PoP 2013]

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© 2019, ITER Organization

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Understanding 2D halo currents at ITER (15 MA / 5.3T)

Hot VDE + cold halo

⚫ Currents are lost in wall and halo

faster than in plasma core

⚫ Currents are re-induced in plasma

edge (large current densities)

⚫ Big drop of edge safety factor

𝐼𝑝 is largely conserved (𝑞𝑎 ∝ 𝑎2)

⚫ Potential destabilization of

external kink modes

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© 2019, ITER Organization

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Understanding 2D halo currents at ITER (15 MA / 5.3T)

Hot VDE + hot halo

⚫ Toroidal current is transferred into

the halo region as the plasma

moves vertically

⚫ Halo currents stabilize vertical

motion

⚫ After stabilization, motion is given

by resistive decay of core + halos

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© 2019, ITER Organization

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Understanding 2D halo currents at ITER (15 MA / 5.3T)

Hot VDE + hot halo

Halo resistivity scan

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F.J. Artola, 7th annual Theory and Simulation of Disruptions Workshop

© 2019, ITER Organization

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Understanding 2D halo currents at ITER (15 MA / 5.3T)

Hot VDE + hot halo

Halo resistivity scanLarger 𝜼𝒉(faster halo

decay)

Smaller halos

Less vertical stabilization

Faster VDE

Larger halo drive

Increase in halos

Regulating

mechanism for

𝐼ℎ𝑎𝑙𝑜,𝜙

𝑰𝒉𝒂𝒍𝒐,𝝓 depends weakly on 𝜼𝒉

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F.J. Artola, 7th annual Theory and Simulation of Disruptions Workshop

© 2019, ITER Organization

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Understanding 2D halo currents at ITER (15 MA / 5.3T)

Hot VDE + hot halo

Halo resistivity scan

But 𝑰𝒉𝒂𝒍𝒐,𝒑𝒐𝒍 depends strongly

on 𝜼𝒉 through 𝒒𝒂

Finally increasing the halo

resistivity gives larger poloidal

halo currents

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© 2019, ITER Organization

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Understanding 2D halo currents at ITER (15 MA / 5.3T)

Hot VDE + hot halo

Halo width scan

𝑰𝒉𝒂𝒍𝒐,𝝓 also has a weak

dependence on the halo width

Weak dependence through

𝝉𝒉 ∝ 𝒘𝒉/𝜼𝒉

Page 21: Halo current studies with self-consistent MHD simulations ...

F.J. Artola, 7th annual Theory and Simulation of Disruptions Workshop

© 2019, ITER Organization

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Understanding 2D halo currents at ITER (15 MA / 5.3T)

Hot VDE + hot halo

Halo width scan

𝑰𝒉𝒂𝒍𝒐,𝝓 also has a weak

dependence on the halo width

Weak dependence through

𝝉𝒉 ∝ 𝒘𝒉/𝜼𝒉

But 𝐼ℎ𝑎𝑙𝑜,𝑝𝑜𝑙 has a much

stronger dependence

through 𝑞𝑎. More effective

at narrow halos.

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© 2019, ITER Organization

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Understanding 2D halo currents at ITER (15 MA / 5.3T)

Ideal wall regime

Halo resistivity scan

Halo currents also slow

down vertical motion

𝑰𝒉𝒂𝒍𝒐,𝝓 is also not

linear in 𝜼𝒉(self-regulating

mechanism)

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F.J. Artola, 7th annual Theory and Simulation of Disruptions Workshop

© 2019, ITER Organization

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Understanding 2D halo currents at ITER (15 MA / 5.3T)

Ideal wall regime

Halo resistivity scan

𝒒𝒂 and 𝑰𝒉𝒂𝒍𝒐,𝒑𝒐𝒍depend strongly on 𝜼𝒉

The poloidal halo fraction (HF) is a factor 5-10 smaller than in the

hot VDE regime

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Prediction of the halo properties

and B.C.s

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© 2019, ITER Organization

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Prediction of the halo properties and B.C.s

⚫ Temperature dependence for resistivity and

parallel conductivity

⚫ Ohmic heating term in energy equation

⚫ Bohm’s boundary condition

⚫ Sheath heat flux B.C.

Currently working VDE model

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© 2019, ITER Organization

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Prediction of the halo properties and B.C.s

⚫ Neutrals, recycling and atomic processes (key for

density evolution, now 𝒏𝒆(𝝍))

⚫ Impurity evolution and radiation

⚫ Limit on ion saturation current (𝐽 ≤ 𝐽𝑠𝑎𝑡 ), (in progress)

Missing ingredients of VDE model

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© 2019, ITER Organization

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Prediction of the halo properties and B.C.s

⚫ Upward ITER VDE, 15 MA / 5.3 T

⚫ Post-disruption equilibrium (𝛽𝑝 = 0.05)

⚫ Flat J-profile after helicity mixing (from DINA)

⚫ No radiation (ohmic heating re-heats the plasma)

⚫ Realistic Spitzer and Braginskii values for 𝜂0 and 𝜅∥0

⚫ 𝜅⊥ = 4 m2/s, 𝛾𝑠ℎ𝑒𝑎𝑡ℎ = 8, 𝑇𝑒 = 𝑇𝑖, 𝜏𝑤 = 0.5 s

Simulation setup

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© 2019, ITER Organization

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Prediction of the halo width and B.C.s

Δ𝑡sim~0.48 s

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© 2019, ITER Organization

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Prediction of the halo width and B.C.s

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© 2019, ITER Organization

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Prediction of the halo width and B.C.s

Density scan (Zaxis=2.0 m)

Poloidal angle along the wall

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© 2019, ITER Organization

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Conclusions and future work

JOREK / M3D-C1/ NIMROD benchmark: good agreement for 2D halo currents

2D VDEs ITER studies

➢ Hot VDE limit (𝜏𝑤 ≪ 𝜏𝑝) largest halo fractions (HFmax~50 %)

➢ Ideal wall limit (𝜏𝑝 ≪ 𝜏𝑤) smallest halo fractions (HFmax < 10 %)

➢ ITER mitigated disruptions (HFmax ~ 10 − 25 %)

➢ Self-regulating mechanism for 𝐼halo,𝜙 , weak dependence on 𝜏ℎ ∝ 𝑤ℎ/𝜂ℎ

➢ Poloidal halo currents depend strongly on 𝑞𝑎 (𝐼halo,pol = 𝐼halo,𝜙 /𝑞𝑎), which

decreases at shorter 𝜏ℎ

➢ Maximum HF at (𝜏𝑤 ≪ 𝜏ℎ < 𝜏𝑝) with small halo widths

➢ Influence of initial 𝒍𝒊 and core resistivity profile?

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© 2019, ITER Organization

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Conclusions and future work

Prediction of halo width and temperature

➢ Current VDE model including

▪ Realistic resistivities and conductivities▪ Energy balance in the halo: sheath losses and ohmic heating

▪ Sheath B.C.s

▪ Imposed density 𝑛 𝜓

➢ Still missing

▪ Density evolution with neutrals and atomic physics

▪ Impurity radiation

▪ Limit on current density (ion saturation current)

➢ Results for hot VDEs show

▪ Large halo widths (for Jphi) at low temperature (on going density scans)