CERC plasmas in the International Stellarator/Heliotron...

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CERC plasmas in the International Stellarator/Heliotron Database J.L. Velasco 1 thanks to A. Alonso 1 , E. Ascas´ ıbar 1 , I. Calvo 1 ,C. Deng 2 , N. Pablant 3 , S. Satake 4 , F. Warmer 5 ... and all the contributors to the ISHDB 1 Laboratorio Nacional de Fusi´on, CIEMAT 2 Madison University 3 Princeton Plasma Physics Laboratory 4 National Institute for Fusion Science 5 Max Planck IPP Greifswald 16th Coordinated Working Group Meeting, 2017, Madrid

Transcript of CERC plasmas in the International Stellarator/Heliotron...

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CERC plasmas in the InternationalStellarator/Heliotron Database

J.L. Velasco1

thanks to A. Alonso1, E. Ascasıbar1, I. Calvo1,C. Deng2, N. Pablant3, S.

Satake4, F. Warmer5... and all the contributors to the ISHDB

1 Laboratorio Nacional de Fusion, CIEMAT2 Madison University

3 Princeton Plasma Physics Laboratory4 National Institute for Fusion Science

5 Max Planck IPP Greifswald

16th Coordinated Working Group Meeting, 2017, Madrid

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CERC in the ISHPDB

One of the goals of CWGM isto contribute to the Interna-tional Stellarator- Heliotron Confinement (Profile) Database,ISH-C(P)DB.This database is intended to compare confinement, transportand various physical phenomena which may be commonly ob-served among several stellarator-heliotron devices.ISHPDB public data consist of the results of joint researchactivities and joint papers.

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EUROfusion and the ISHDB

EUROfusion wants to promote the exploitation of scientific re-sults obtained accros various experiments within EUROfusion.

Establish and exploit several databases:

WJPET1 (JET campaigns).

WPMST1 (Medium-Size Tokamak campaigns).

Stellarator/Heliotron database

Plan is to use common infrastructure using IMAS.

Should be able to handle stellarator-specific datasets.

No much progress since last CWGM.

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CERC in the ISHPDB [Yokoyama et al. 2007 NF]

Improved energy confinement; highly peaked Te.

Positive and large (Er � 1 kV/m) radial electric field.

Hollow density profiles.

ECH-heated plasmas above a power threshold.

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CERC profile documentation

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0-D energy balance in CERC plasmas

Pb ∼ Qb ∼ ΓbTb

For the electrons, pe ∼ pECH + prad + pei ≈ pECH .

For the ions, pi ≈ pie = −pei.Ions in the

√ν regime, Γi = Γ

√ν

i .Electrons:

in the√ν regime for electron root, Γe = Γ

√ν

e .

in the 1/ν regime for ion root, Γe = Γ1/νe .

Radial electric field:Er ∼ −T ′

e/e > 0 for electron root.Er ∼ T ′

i/Zie < 0 for ion root.

It can be shown that:

Γ1/νb ∼ (ε3/2R−1B−2)(A

1/2b Z−6b )(n0bT

7/2b )

Γ√ν

b ∼ (ε3R2B−1/2)(A−1/4b Z

3/2b )(n

3/2b T

−1/4b )

pie ∼ A−1i Zin2eT−1/2e

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Energy conf. and core parameters: equations

Electron energy balance:

PECH ∼ TeΓe

For electrons in the√ν regime, Γe = Γ

√ν

e :

PECHT−3/4e n−3/2e ∼ ε3R2B−1/2

For electrons in the 1/ν regime, Γe = Γ1/νe :

PECHT−9/2e ∼ ε3/2R−1B−2

TJ-II: Te reduction with ne [Estrada 2004]

LHD: Te∼n−0.6e [Ida 2003]

LHD: P ∼T−0.5e [Ida 2004]

No isotopic effect could not be revealed in W7-AS [Hirsch 2008]

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Energy confinement and core parameters: ISHDB scaling

100

1000

10000

100000

0.001 0.01 0.1

P abs

n e(0

)-3/2

Te(

0)-3

/4 [

A.U

.]

R2*(a/R)3*B-1/2 [A.U]

CERC databaseν

1/2 NC scaling 1e-06

1e-05

0.0001

0.001

0.01

0.001 0.01 0.1

P abs

Te(

0)-9

/2 [

A.U

.]

R-1*(a/R)3/2*B-2 [A.U]

CERC databaseν

-1 NC scaling

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Energy confinement and core parameters: ISHDB scaling

100

1000

10000

100000

0.001 0.01 0.1

P abs

n e(0

)-3/2

Te(

0)-3

/4 [

A.U

.]

R2*(a/R)3*B-1/2 [A.U]

CERC databaseν

1/2 NC scaling

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Threshold to CERC

From ion to electron root:

Γ1/νe ∼> ZΓ

√ν

i (forEr < 0)⇒ needEr > 0

PECH ∼ Γ1/νe Te

ε2R3pie ∼ Γ√ν

i Ti

we have:

n−9/5e PECH ∼ (ε159/40R13/5B−1/5)(Z9/10)

TJ-II: ne ∼ P+0.34ECH ε−1.0 [Guimaraes 2008 PFR]

i.e. approximately n−9/5e P

3/5ECH ∼ ε9/5

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Threshold to CERC

From ion to electron root:

Γ1/νe ∼> ZΓ

√ν

i (forEr < 0)

PECH ∼ Γ1/νe Te

ε2R3pie ∼ Γ√ν

i Ti

we have:

n−9/5e PECH ∼ (ε159/40R13/5B−1/5)(Z9/10)

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Relevance for impurity hole?

Collisionality diagram (relevant for neoclassics).

Devices:

Black triangles: TJ-II

Red circles: LHD

Blue squares: W7-AS

Green elipse: W7-X (∼OP1.1 and OP1.2)

Stars are reactor scenarios.

Sign code:

thin open: CERC

full: NC validation

thick open: high Ti / im-purity hole

High Ti and impurity hole plasmas relatively close to CERCplasmas.

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LHD: std. ion root vs. imp. hole [Velasco 2016 NF, 2017 EPS].

#109696 (open circles):

Medium-ne, high NBI power.

Used for NC validation[Dinklage 2013 NF; Satake 2015 ISHW].

eEr ∼ T ′i < 0.

#113208 (closed circles):

Impurity hole plasma.[Nakata, this CWGM; Velasco 2016 NF].

Er < 0 but e|Er| � T ′i .

Close to impurity screening:

Need additional effects (e.g. Φ1)

Low collisionality is key element:factor ∼ 20 in core ν∗b .

With slightly higher Te & Ti, jumpto electron root [Nagaoka 2015 NF].

2

4

6

0 0.2 0.4 0.6 0.8 1

n e [

1019

m-3

], T

e,T

i [ke

V]

r/a

neTeTi

-12

-8

-4

0

0 0.2 0.4 0.6 0.8 1

Er,

Ti’/

e, T

ine’

/nee

[kV

/m]

r/a

Ti’/eTine’/nee

Er

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High Ti/impurity hole as plasmas close to trans. to CERC.

ZEr vs. T ′iScan in low collisionalities.

Connection to W7-X: threshold plasmas willbe studied in OP1.2.

Similar proposals being discussed for OP1.2impurity program.XICS key diagnostics.

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Summary

New devices and new plasma conditions:

CERC database can probably expanded.

Several complementary approaches.

Impurity hole plasmas not so far from CERC in the parameterspace:

Opportunity for impurity studies in both LHD and W7-X.

Resources in EUROfusion for upgrading the database:

Requests from users?

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