平成24年ダイバータおよびPWI合同研究会

日時:

場所:

平成24年7月23日(月) - 24日(火)筑波大学内・筑波大学自然 B 棟 119 講義室

非接触プラズマ研究と課題
名古屋大学大学院工学研究科
エネルギー理工学専攻
大野 哲靖

高性能炉心プラズマの定常維持・制御に対する周辺プラズマの役割
必要条件- 炉壁の耐久性- 燃料粒子，不純物粒子輸送制御

炉心プラズマの定常維持・制御の基盤を与える

境界プラズマ

炉心
プラズマ
Ｘ点

課題

プラズマ対向壁への粒子・熱負荷制御- 非接触プラズマの理解と制御

セパラトリクス

熱・粒子流

磁気ダイバータ
ダイバータ板ダイバータコイル2

JT-60SAでのダイバータ板への熱負荷評価
具体的な設計を行うと問題が顕在化‒ 過酷な熱・粒子負荷

部分非接触プラズマの定常維持を前提とした設計
Shinji Sakurai and JT-60SA design team, Proc. of Int. Sympo. on EcoTopia Science 2007, ISETS07 (2007)

Japan Society of Plasma Science and Nuclear Fusion Research

非接触プラズマとは（１）ダイバータ部あるいはSOL領域からの強い放射損失（２）ダイバータ板近くのプラズマ温度の著しい低下
The Japan Society of Plasma Science and Nuclear Fusion Research
The Japan Society of Plasma Science and Nuclear Fusion Research（３）ダイバータ領域における中性ガス密度の増大（４）ダイバータ板へのプラズマ粒子束及び熱流束の著しい低下（５）ダイバータ領域において磁力線に沿ったプラズマ圧力の低下

高村秀一：プラズマ核融合学会誌1996

非接触プラズマの構造
Radiation
Zone

Ionizaion
Front

Ⅰ
Hot Plasma
Ⅰ

Momentum
Loss
Region

+

e
N

N
N

N

→放射冷却によるN

電子温度の低下+
Divertor
Plate

B
Wall

Plasma Pressure

ダイバータ領域の中性ガ
ス圧の増加→低温高密度プラズマの生成→体積再結合の発生

Plasma Temperature→プラズマの消失

Plasma Density→ダイバータ板へのDistance along the Magnetic Field

熱負荷の減少非接触プラズマにおける課題（１）原子･分子過程
電子ーイオン再結合、分子活性化再結合（水素、炭化水素）（2）非接触プラズマ計測
NAGDIS
プローブ計測の異常性 （門先生)
MAP-II（３）非接触プラズマのエネルギーバランスの理解
TPD
中性ガス温度の影響、輻射輸送の影響（４）非接触プラズマの動的応答
ELM様熱負荷への応答、接触-非接触-再接触遷移過程（５）非接触プラズマ中の径方向輸送
Gamma10
非拡散的輸送現象（Plasma Blobs)(田中先生）（６）非接触プラズマの安定性
LHD
熱的不安定性、2次元効果（部分非接触）
JT-60U(SA)（７）金属壁での非接触プラズマ生成
適切な不純物ガスの選定ーコアプラズマとの共存（８）非接触プラズマの制御手法の確立
Puﬀ&Pump, エルゴディック磁場（磁気島）（増崎先生）（９）先進ダイバータ配位への適用性 ーダイバータ幾何学構造への依存性
Super-X, Snow ﬂake, Isolated divertor etc.

非接触プラズマにおける課題（１）原子･分子過程
電子ーイオン再結合、分子活性化再結合（水素、炭化水素）（2）非接触プラズマ計測
NAGDIS
プローブ計測の異常性 （門先生)
MAP-II（３）非接触プラズマのエネルギーバランスの理解
TPD
中性ガス温度の影響、輻射輸送の影響（４）非接触プラズマの動的応答
ELM様熱負荷への応答、接触-非接触-再接触遷移過程（５）非接触プラズマ中の径方向輸送
Gamma10
非拡散的輸送現象（Plasma Blobs)(田中先生）（６）非接触プラズマの安定性
LHD
熱的不安定性、2次元効果（部分非接触）
JT-60U(SA)（７）金属壁での非接触プラズマ生成
適切な不純物ガスの選定ーコアプラズマとの共存（８）非接触プラズマの制御手法の確立
Puﬀ&Pump, エルゴディック磁場（磁気島）（増崎先生）（９）先進ダイバータ配位への適用性 ーダイバータ幾何学構造への依存性
Super-X, Snow ﬂake, Isolated divertor etc.

非接触プラズマの生成と電子-イオン再結合過程.

Attached Plasma

Detached Plasma

接触プラズマ

接触プラズマ

非接触プラズマ

Heat Flux (kW/m2)

200

プラズマの消失
ガスバッファ層の形成

50

0
5
テキスト
近紫外発光スペクトル

15

P (mTorr)
21S-61P

0.8

10

21S-71P

非接触プラズマ

100

0Intensity [mW cm-2 sr-1 µm-1]..

プラズマ対向材への熱流の
著しい低減

150

14
15
16

0.4

Continuum emission
into 23P

18

電子-イオン体積
再結合によるプラ
ズマ消失の実証350

23P-p3D

0330

340
Wavelength [nm]３体再結合に伴う高励起準位からの発光線
放射再結合に伴う連続スペクトル172020分子活性化再結合過程
分子活性化再結合 MAR：Molecular Activated Recomination→

H- + H

H- + A+ → A + H(荷電交換再結合)
H2(v) + A+ → (AH)+ + H(AH)+ + e → A + H(解離性再結合)振動励起水素分子を起点とした一種の化学反応-�大きな反応確率
粒子バランス∂ne+ ∇⋅Γ = <σv>ionnenn - <σv>EIRne2∂t- <σv>MARnenH2
水素分子密度も重要！

3/s]
Rate
Coefficient[m3/s]
反応速度係数[mH2(v) + e

.

10-15

分子活性
化再結合

5x1019m-3
5x1018m-3

MAR
10-16
電子-イオ
ン再結合

10-17

EIR

電離
Ionization

10-18
10-19
0

1

2
3
4
Te [eV]
電子温度
[eV]

5

分子活性化再結合過程の実験的検証

テキスト

ヘリウム
ガス導入

水素ガス
導入
イオン粒子束の減少
３体再結合線の消失

N.Ohno et al.,PRL
81(1998)818

炭化水素分子活性化再結合の実証

CH4+H+(or He+) →CH4+ + H (or He)
CH4+ + e → CH3 + H

ダイバ
増加

→放射

電子

→低温

の生

→体積

MAP-IIでの
実験的検証

→プラ

→ダイ

熱負

非接触プラズマにおける課題（１）原子･分子過程
電子ーイオン再結合、分子活性化再結合（水素、炭化水素）（2）非接触プラズマ計測
NAGDIS
プローブ計測の異常性 （門先生)
MAP-II（３）非接触プラズマのエネルギーバランスの理解
TPD
中性ガス温度の影響、輻射輸送の影響（４）非接触プラズマの動的応答
ELM様熱負荷への応答、接触-非接触-再接触遷移過程（５）非接触プラズマ中の径方向輸送
Gamma10
非拡散的輸送現象（Plasma Blobs)(田中先生）（６）非接触プラズマの安定性
LHD
熱的不安定性、2次元効果（部分非接触）
JT-60U(SA)（７）金属壁での非接触プラズマ生成
適切な不純物ガスの選定ーコアプラズマとの共存（８）非接触プラズマの制御手法の確立
Puﬀ&Pump, エルゴディック磁場（磁気島）（増崎先生）（９）先進ダイバータ配位への適用性 ーダイバータ幾何学構造への依存性
Super-X, Snow ﬂake, Isolated divertor etc.





ÊÔßÐÒÖÔÓÆÎØÐÞÙÐ

ÈÚÛÓÔTe[eV]

Ï×ÚÕØÔÆÎÝÛÑÔ

B
ĚĞĎĜÎØÐÞÙÐ

ÍÜß×ÒÐØÆÌÔßÖÛÓ

P[mTorr]ËÚÓÆÎØÐßÔ

非接触プラズマにおける課題（１）原子･分子過程
電子ーイオン再結合、分子活性化再結合（水素、炭化水素）（2）非接触プラズマ計測
NAGDIS
プローブ計測の異常性 （門先生)
MAP-II（３）非接触プラズマのエネルギーバランスの理解
TPD
中性ガス温度の影響、輻射輸送の影響（４）非接触プラズマの動的応答
ELM様熱負荷への応答、接触-非接触-再接触遷移過程（５）非接触プラズマ中の径方向輸送
Gamma10
非拡散的輸送現象（Plasma Blobs)(田中先生）（６）非接触プラズマの安定性
LHD
熱的不安定性、2次元効果（部分非接触）
JT-60U(SA)（７）金属壁での非接触プラズマ生成
適切な不純物ガスの選定ーコアプラズマとの共存（８）非接触プラズマの制御手法の確立
Puﬀ&Pump, エルゴディック磁場（磁気島）（増崎先生）（９）先進ダイバータ配位への適用性 ーダイバータ幾何学構造への依存性
Super-X, Snow ﬂake, Isolated divertor etc.

almost constant. These results indicate that the
Axial Positlon: X ( m )electron energy is effectively lost by the
FIG. 6 . Axial profiles of :(a) Te,T,.n. and plasma
charge exchange and elastic collisionpressure ; (b) ionization and charge exchange
processes due.to a strong coupling between
energy losses, energy transition by temperatureelectrons and ions in such a high density
relaxation process and plasma energy flux in Fig. 4
NAGDIS, Nagoya Univ.
plasma. In fact, the energy balance is342 高密度estimated from Fig. 6(b): ionization energy
drops around X=0.9m. Ti is almost constant.
Electron and ion energy loss rates are shown
loss 22.8%of total energy input and charge
in Fig. 6(b). Electrons mainly lose their energy
exchange energy loss 73.6%. Please pay
by ionization process near the plasma source
attention that electrons have the energy more
the 80% of plasma energy at X=Om.
because T, is relatively high enough forthan
ionization process. Above X-0.35m, the In a lower density case as shown in Fig.
ionization energy loss becomes small due
7, tocorresponding to Fig. 5, the axial profile ofa decrease
in
T,
and
the
energy
loss
with
the
低密度
低密度
T, does not change so much because
the energy
高密度
charge exchange and elastic collision becomesloss due to ionization process is small and thedominant. It should be noted that the energy
relaxations mentioned above isloss rate of electron by energy exchange temperature
with
also
of weak, so there is no way to lose theions -K(T,-T~)has the same value as thatelectron energy. Therefore, Ti is found to beions by charge exchange and elastic collisions.
rapidly
decreasing to a value around theisThis is the reason why the ion temperature
0
0.2
0.4
0.6
0.8
1
neutral gas temperature To 0.03eV,
almost constant. These results indicate
thatambient
the
低密度
A
x
l
d
Porttion:X(
rn)
Axial Positlon: X ( m )the ions can not gain the energy fromtheelectron energy is effectively lost bybecause
FIG. 6 . Axial profiles of :(a) Te,T,.n. and plasma FIG. 7.Axial profiles of :(a)T, and plasma
charge exchange and elastic collision
the electrons.
In this case, loss
the energy
lossexchangedue
gain
N. Ohno CPP1996
pressure ; (b) ionizationand chargeionization
1 collision is pressure ; (b) ionization and charge exchange energy
高密度
a strong coupling between
processes due.toto chargeenergy
exchangeradiation
losses, energy
by temperaturee transition
losses, energy transition
by temperature relaxation
電子ｰイオン間のエ
3electrons and ions in such a high density
relaxation forprocess
and plasmaenergy andflux inno
Fig. 4 process and plasma energy flux in Fig. 5.
not SO effective
plasmaCooling,
recombination
ネルギー緩和が重要
isplasma. In fact, the energy balancedetached
plasmaappears.
Figure6(b)givesenergy relaxation
estimated from Fig. 6(b): ionization energy
N. Ezumi JNM1997
4
loss 22.8%of total energy input and charge
charge exchange 中性ガス温度がイオ
2exchange energy
loss - 73.6%. Please payi
非接触プラズマ生成
ン温度を決める
elastic collision3
attention thatelectrons
havetheenergymoreに密度の閾値が存在
recombination

非接触プラズマ中のエネルギーバランス
-

-

-

-

B~~

-

than 80% of plasma energy at X=Om.
In a lower density case as shown in Fig.

-

非接触プラズマにおける課題（１）原子･分子過程
電子ーイオン再結合、分子活性化再結合（水素、炭化水素）（2）非接触プラズマ計測
NAGDIS
プローブ計測の異常性 （門先生)
MAP-II（３）非接触プラズマのエネルギーバランスの理解
TPD
中性ガス温度の影響、輻射輸送の影響（４）非接触プラズマの動的応答
ELM様熱負荷への応答、接触-非接触-再接触遷移過程（５）非接触プラズマ中の径方向輸送
Gamma10
非拡散的輸送現象（Plasma Blobs)(田中先生）（６）非接触プラズマの安定性
LHD
熱的不安定性、2次元効果（部分非接触）
JT-60U(SA)（７）金属壁での非接触プラズマ生成
適切な不純物ガスの選定ーコアプラズマとの共存（８）非接触プラズマの制御手法の確立
Puﬀ&Pump, エルゴディック磁場（磁気島）（増崎先生）（９）先進ダイバータ配位への適用性 ーダイバータ幾何学構造への依存性
Super-X, Snow ﬂake, Isolated divertor etc.

非接触プラズマとELM の相互作用（トカマク実験）•Two negative peaks( negative ELM) appears
in Dα emission.

A. Loarte et al.
Nuclear Fusion 38(1998)331.

ELM熱負荷模擬実験
Divertor Test Region(~2 m)DC Discharge Region(~ 0.5 m)
CathodeFloating
Electrode
Anode

Baratron gauge
Scanning Probes
2.03m

Primary Gas(He)

Target Probe

X=0m

RF Generator
f=13.56MHz
P=10kW

Matching
Box

1.06m

1.39m

1.72m

Spectrometer
PM
HeI( 2p-nd; 3<n<9 )DigitalOscilloscope

Secondary Gas(He)
Isolation
Amplifier

高周波加熱によりELM熱負荷を模擬非接触プラズマへの熱パルス印加実験

Emission Intensity (arb. units)

100

1st negative peakTime evolutionof Balmer series
spectra at P ~9mtorr

2nd negative peak
2p-3d:T10

2p-4d:T
1

2p-5d:T

0.1

2p-6d:T
2p-7d:T
2p-8d:T

Negative spikes
appear2p-10d:T
0.01

0.001

rf pulse
0

0.5

1

1.5

Time (msec)

2

2.5

10 9
10

Recombining
Phase

Ionizing
Phase(a)2p-3d;T8

n e=5x10 19m-3

10 7
10 6
10 5

n e =1x1019m-3

10 4

ne =5x1018m-3

10 3

0

1

eq

Te

Te

2

3

4

5

Emission Intensity (arb. units.)

衝突輻射モデルによるNegative Spikeの解析

10 7
10

(b)2p-8d;T

6

10 5
10 4
10 3
10 2
10

0

Te (eV)

1

2

Te eq

3

4

Te (eV)

Te

Transition between the ionizing phase and recombining phase gives minimum points

5

1st Negative Spikeの詳細観測

1.5

0.6
1
0.4

Ion Flux

0.2

0

0.5
2p-5d:T

0
0

0.1

0.2

0.3

0.4

0.5

0.6

Time (ms)- Ion flux to the target
plate is substantially
increased near the 1st
negative spike.

5

-10

4

-15

3
-20
2
-25
-30

1
0
0 0.1 0.2 0.3 0.4 0.5 0.6
Time (ms)Ion Flux into the Target (a.u.)

2p-3d:T(587.5 nm)

almostconstant at 1st negative spike.
End Plate Floating Potential (V)0.8- Floating potential remains
Ion Flux to the Target (a.u.)

RF Pulse

1

Emission Intensity (a.u.)

P He =7.5 mtorr
P rf =1 kW
2



Pump

(b)

P [mTorr]divertor
test region

Anodedischarge
region(i)

Pump

Cathode

Gas

Pump

Gas
Close
a gate valve Pump

Te [eV](a)

Volume 4, 000 (2009)

Cathode

Gas

Gas

15

10

32 kHzCS(f)Fig. 1 Schematic illustration of the linear plasma divertor simulator NAGDIS-II. (a) attached and (b) detachedplasma conditions.

(a)

(iii)

30
20
10
0
6
4
2
0
0

(a)
12

(b) 8

(c)

-5

8.5 kHz

Detached

4
0
16
8
0

-10
0.9

0.45

Attached

10

10

Fluctuationlevel of ne

Vf [V]

Anode

(ii)

Vs [V] ne [1018m-3]

and Fusion Research: Rapid Communications(d)0Phase difference [ ]0-90 (b)

-170

-180
-270
-360
0

Attached-18-90

Transition-180-270 (c)
-360
-1
10

(e)

Detached
0

10

1

2

10
10
Frequency [kHz]3

10

Okazaki PFR2012

R(τ)
-0.8

-0.4

0

0.4

) Cross spectrum, CS ( f ), of ne and Vf under the attached and detached
Frequency
Fig. 2conditions.
Experimental
resultsdependenceof triple probe measurement at the r = 15 mm. Time evolutions of the moving average非接触プラズマにおける課題（１）原子･分子過程
電子ーイオン再結合、分子活性化再結合（水素、炭化水素）（2）非接触プラズマ計測
NAGDIS
プローブ計測の異常性 （門先生)
MAP-II（３）非接触プラズマのエネルギーバランスの理解
TPD
中性ガス温度の影響、輻射輸送の影響（４）非接触プラズマの動的応答
ELM様熱負荷への応答、接触-非接触-再接触遷移過程（５）非接触プラズマ中の径方向輸送
Gamma10
非拡散的輸送現象（Plasma Blobs)(田中先生）（６）非接触プラズマの安定性
LHD
熱的不安定性、2次元効果（部分非接触）
JT-60U(SA)（７）金属壁での非接触プラズマ生成
適切な不純物ガスの選定ーコアプラズマとの共存（８）非接触プラズマの制御手法の確立
Puﬀ&Pump, エルゴディック磁場（磁気島）（増崎先生）（９）先進ダイバータ配位への適用性 ーダイバータ幾何学構造への依存性
Super-X, Snow ﬂake, Isolated divertor etc.

周辺プラズマ領域での非拡散的径方向プラズマ輸送
第一壁近傍に比較的プラズマ密度が高く平坦化した領域(2nd SOL)が存在する→ 第一壁でのリサイクリングの増加→ 不純物発生の増加

2nd SOL

径方向拡散によるプラズマ輸送のみでは説明が困難

dnΓ⊥ = − D⊥+ nV⊥ (r )dr
磁力線を横切る対流的プラズマ輸送？

€→ Plasma Blob輸送

プラズマの塊(Blobs)が最外殻磁気面付近で生成され， 磁力線を横切って第一壁に向かって飛行する現象

M. V. Umansky et al. Phys. Plasma 5, 3373(1998).

第一壁

ne
1st SOLBlobs
2nd SOL

セパラトリクス

Plasma Blob®²§ÂkB,

â

Plasma Blob®²¨
S.I. Krasheninnikov, Phys. Lett. A 283 (2001) 368.

zHéĀPlasma Blobê»ïòĘąĞĝĤĒi´ĄDLáá4!·ĥ^e÷ÿā¼»ê+«áâČĦčOM÷ÿāhĄQâ
¼4Eô4BøExBēğĘĒ÷ÿā®²áĥĥĥĆćĤô¼9øh÷ÿā¼4EêLâĥĥĥ+«÷uăĂ¼uêOMR÷ºîă¼4Eê¼4Eør;
ĥĥĥ®²³AħàEĨĥ®²ª»÷8ëìEÀQîăĂ<Äög£ù"

¾U¾UđĆĕĦĐK]ø®²JđĆĕĦĐÁ2ø¯=¶

¾UĚĞĎĜø1

U¾U

Jĉč-P6

đĆĕĦĐcûø~ĥ9©
U

K]



+«ĩ

ČĦčOM
óh Q



+«Ī

ÿāuó
h Q

w÷`GħITERóþT
¾U

;Ĩ

K]
P8

ĘąĞĝĤĒi´êđĆĕĦĐc÷U

P8

EÀ>Ĭ

đĆĕĦĐc÷aUEÀ8Ĭ

f&÷èíĂ
<Äg£ù|æNAGDIS-II÷èíĂ¾PX®²øy1đĆĕĦĐkW¥Ä
NAGDIS-IIø¹æðÁ2÷LîăðĚĞĎĜĄ¿éĀÅ³ĈĝĞ÷ÿā¡y

Å³ĈĝĞ

¿,
ne<1020m-3
Te~10eV

P=3.6mTorr

probe

plasma column

P=9.0mTorr

P=13.6mTorr

2nÎØÐÞÙÐÆÉØÛÑ®²R
1đĆĕĦĐkW¥ÄNAGDIS-II(°ó¡yîăðĆćĤÃ)¼utDo÷čĖĆĊU

1Ą æðU ĥ¾U
K]ø½¼VJp­
Plasma Blobjø®²ħ¾PX®²Ĩ
ø:.ù¦vüP8øôëVS?ĥ@/6Jĉč-P8¾U đĆĕĦĐK]÷
®²ø68Ą*4ĄlĂ2nY¿øĚĞĎĜ®²Rù[¾U®²øoöJ
ħ³AĥZ'öõĨĄ¤ óëöæ

¤søêI

N. Ohno et al., J. Plasma Fusion Res. (Rapid Communications) 80 (2004) 275.

¾U
¾U

ĚĞĎĜøĚĞĎĜøRđĆĕĦĐ5óø4¿øÅ³ĈĝĞ¡y¡yeø

128x256pixel (~54x108mm2)

Probe 30000fps
P=11mTorr
B=0.05T

Plasma column
B

ErxB direction

~20mm

¿,
ĚĢĦęĥÅ³ĈĝĞôþ÷
f=4.1kHz, 8.2kHz÷ėĦĊ

}{¿÷èíĂĚĞĎĜVĄ#\xøĚĞĎĜø+¬Ąýòy+¬Z'īExBēğĘĒZ'ĚĢĦęèÿúÅ³ĈĝĞ¡y %øĖģĦčěĊĒĠħB=50mTĨ

非接触プラズマにおける課題（１）原子･分子過程
電子ーイオン再結合、分子活性化再結合（水素、炭化水素）（2）非接触プラズマ計測
NAGDIS
プローブ計測の異常性 （門先生)
MAP-II（３）非接触プラズマのエネルギーバランスの理解
TPD
中性ガス温度の影響、輻射輸送の影響（４）非接触プラズマの動的応答
ELM様熱負荷への応答、接触-非接触-再接触遷移過程（５）非接触プラズマ中の径方向輸送
Gamma10
非拡散的輸送現象（Plasma Blobs)(田中先生）（６）非接触プラズマの安定性
LHD
熱的不安定性、2次元効果（部分非接触）
JT-60U(SA)（７）金属壁での非接触プラズマ生成
適切な不純物ガスの選定ーコアプラズマとの共存（８）非接触プラズマの制御手法の確立
Puﬀ&Pump, エルゴディック磁場（磁気島）（増崎先生）（９）先進ダイバータ配位への適用性 ーダイバータ幾何学構造への依存性
Super-X, Snow ﬂake, Isolated divertor etc.

熱的不安定性-X点MARFE
非接触プラズマは不安定→容易にＸ点MARFEに移行

N. Asakura et al. PSI18

X点MARFEによるコアプラズマ閉じ
込め特性の劣化
ダイバータ配位およびダイバータ排気量制御による非接触プラズマの定
常維持・制御の実証が必要（高性能炉心プラズマとの両立性）

(%'!
  the Heaviside function H A , which is unity for 0 ȟ  L A . The Braginski
fluid
equations
are theL$& :":/& 458:)8#
4&5808:)"3"1 :/& 10"3:4 ;8$4&7 >9
w
n
X
*
H
w
n
the combined ion and electron momentum AbalanceA:/& :&%5&08:$0& 7&5&37&3;&"1 7)M&0&3: 8:"%); 50"=
, equation(21)n Q ion Q rec ;&44&42 5"<&0 >8#83;& )3 :/& ?@A ')3!"#!)3* :/& 5"<&0[
wt
wcontinuity' nX ionization source and recombination
ion particle
equation, withsink;"%)3* )3:" :/& ?@A 10"% :/& ;"0&2 ! 2 )%5$0):9 08=

非接触プラズマの熱的不安定性(1次元解析）
!)%5"

w nmX

w
2nT  nmX 2 nmX Q at  Q rec
wt ionw[and electron momentum balance equation
the combinedwn w nXwtw[

n Q ion Q rec *A H A,' nX

and the combined ion and electron energy balance equation

w nmX

w

2nT  nmX 2 nmX Q at  Q recwtw[
the combined ion and electron momentum balance equation
1
w§
w §
w §1
·
2·
5 2 wT ·
3
X
N
nT

nm

T

nmX 3  5nTX ¸
¨ 0
¸
¨
¸
¨
2
wt ©
w[ ¹ w[ © 2¹ w[ ©
¹

and the combined ion and electron energy balance equation
w nmX
w
2
2nT  nm
QAXH A  nmX Q at  Q rec
3 
2nTQwat[ nEQ ion  n f z Lw
,
z t

(22)

'E

2

1
w§
w §1
· w §
·
5 2 wT ·:J;VmgM23p{\`2KZ[R
3nT  nmX 2 ¸ 
nmX 3  5nTX ¸¨ N 0T¸¨¨2w[ ¹ w[ © 2©
¹  w[ ©
¹wt#%%&and the combined ion and electron energy balance equation
wv@HI?3=J8>?Ls05ksN43
oQ,%&"""#)QA H A .
3
2
Q
Q
n
f
L
nT
nE




,
z z
at
ion
9705iO16li3j^-xdqAF<Bh2'E
u3KZ[R|Qnp}
+*
1w§
w §w § 1 .:
·
2·
5 38
2 wT ·
3nT  nmX ¸ 
nmX 3  5nTX ¸
CDGJ:EI}¨ N 0T
¸
¨
¨
2
wt ©
w[ ¹ w[ © 2¹ w[ ©
¹
e]@HI?3
&$3ay-e]zU3c
X/bfSlrt3WR- P_p3YT3
%&"""#)#
 QH
 n 2 f L  nTQ  nEQ  A A ,z?@A7)8:)"3 #"44 )3 :/& ?@A2 !087 2 837 !F - ;83 >& <0)::&3 84!)%5"!F # !?@A $ !087 + N& <)## 4&& :/8: :/& &M&;:4 "1 )%=Nagoya Univ. )%5"4& 0&=
5$0):9 087)8:)"3
5#84%8 0&;"%>)38:)"3(22) 837 NAGDIS,
4:0);:)"34 "3 :/& 5"<&0 4"$0;&42 !?@A 837 !F 2 </);/ 80&
3&&7&7 :" 4$4:8)3 8 /)*/ 0&;9;#)3*(21) ?@A 5#84%8 8: 8 *)!&3$54:0&8% 5#84%8 50&44$0&2 #$5 + O":/ !?@A 837 !F %$4:
&D;&&7!8#$&4 </);/! ;0):);8#"! " 7&5&37 "3 #$5 2 !?@A !
" 0&; "$5 2 837 844";)8:&72 0&45&;=" )%5 "$5 837 !F ! !
!
:)!&#92 <):/ )%5$0):9 087)8:)"3 837 5#84%8 0&;"%>)38=:)"3+ @1 ;"$04&2 )3 (22)
&D5&0)%&3:42 :/& &M&;:4 "1 )%5$0):9087)8:)"3 837 5#84%8 0&;"%>)38:)"3 )3 :/& 0&;9;#)3*
0&*)"3 %89 >& 4:0"3*#9 ;"$5#&7+ F"<&!&02 :" &%5/84)E&:/& 7)M&0&3;&4 )3 :/& 5/94);4 "1 :/&4& )34:8>)#):)&42 "$0:/&"0&:);8# %"7&# ;83 :0&8: :/&% 4&5808:&#9 >92 1"0 &D=
8%5#&2 :$03)3* "M :/& )%5$0):9 "0 5#84%8 0&;"%>)38:)"3(23)&M&;:4+

z

2

at

ion

'E

(23)

?'<<Y 4"?)3;&
(Y +)3;0&8
Z"<):/'/ # ;;"37)(P7)! ( !
;"34::/)4 )4;8$4&&D8%7&8#)3:)"3 '
Y&1+ \'84 8
F"/&8: :)4 )%!&0:"0:/8:;"%5:/& 08#"$4 /\`^+ .
;0&84&
4/85&
8:)"34
*(
(Y !
5#84%

$%$% '(23)32 )3 8 :"W8%8W 7)=()*+ ,+ ?;/&%8:); !)&< "1 7)M&0&3: 0&*)"34!&0:"0+

F&
:/& )
5#84%
4$#:4

rap (nv)div sin θ + nn,div,aux vn ,(9)ecycling rate, (nv)div is the plasma partiinr target, and nn,div,aux is the auxiliary
Volume 6, 2403098 (2011)g.
gas
puffing,near
the divertor
plate.
e
n
and
λ
are
the
valuesofnandλn at the mesh
n,
j
n,
j
n
eat and,θ
relevanttotheneutralsareη
j, respectively. At the divertortrap
target and
we adopt theVolume 6, 2403098 (2011)
部分非接触ダイバータ構造による安定化

ma and Fusion Research: Regular Articles

the dess-fieldwing condition:
plasma.

n,div vn = ηtrap (nv)div sin θ + nn,div,aux vn ,alnResults(9)is the recycling
rate,(nv)div is thewere
plasma partieis,
ηtrap
moveITER-like
plasmaparametersing
is theauxiliary inux theatparticle
divertorinputs
target, fromand nn,div,aux
andthe coreto theFig. 2
ematicd neutrals, e.g.
gas puffing, near the divertor plate.
23 −1
ndflux
1.5 × 10 s , respectively. The surwo
t aparameters
relevant to the neutrals are η , θ and∼par640 m2 and the SOL width ∆SOL istrap
exam.
,aux

Plasma and Fusion Research: Regular Articles

time dependent analysis of t
plasma. We employed the
PDD plasma one-dimension
field particle and heat transprevent the detachment fronsuch cross-field transport cof a PDD plasma. It is al
the detachment front in a st
ble against the neutral densi
Finally, we make quali
Snapshots of the spatial profiles of n and T in the attachedulation results reported her
tions. In many tokamak exp((a) and (b)) and detached ((c) and (d)) tubes in the caseaccompanies a high radiati(5).X point (for example [of S ⊥div = 0 and the non-zero Q⊥div expressed in Eq. theFig. 4 Snapshots of the spatial profiles of n and T in the cases of= 2403098
Q⊥div =shown
0 in Figs. 2 (e) and (f) a
The n and T theprofiles
in andtheofVolume
S ⊥div(b))caseand the non-zeroS ⊥div 6,((c)-(f))
zero S ⊥div ((a)(2011)(accompanying the radiationin the detached tube. The time step of each curve is theare also shown((e) and (f)). The detachment fronts thatsame as Fig. 2.
beyond the X point in thetime dependentof thedetachment
fronts inThea PDD transport. Suchmove upstream
in the analysis
detachedtube
are simulated.
cross-field
perimental
plasma.
the ML1D
model2.4
to (blue),describea observations. O
time of eachcurveWeis employed
at t = 0 (red),
1.2 (green),
in interpreting such ex
PDD
one-dimensionally.
We found that thethat
cross3.7
4.9plasma(turquoise)
andprofiles
6.2 (yellow)
Fig.(pink),
2 Snapshotsof the spatialof n ands.T in the attachedvertor detachment, it is imp
field particle and heat transport in the divertor regioncantransport((a) and (b)) and detached ((c) and (d)) tubes in thecasein the divertor regi

erefore, thecross-fieldandpar- Articles
Plasmaand Fusionenergy
Research:
Regularplasma,Fig. 1region,
The schematic
pictureandof the multi-layer
ein
outer
the SOLQ⊥SOLS ⊥SOL , 1D model.
widths−3−3 −1and1021 Onmparameters, hand,werebe2.67analysis,
MWmcount onlyin the5.0
SOL×region.
thes othereffects
plasmaIn
our
ITER-like
plasmaof thecross-field source
termsin thedivertorregion, S ⊥div
equathedetached
tube
width
tothe
the
.tratioThe ofpower
andparticle
inputsfromcore
to theand Q⊥div , on stability of the detachment front had not been
ansport23 −1/∆SOL= studied
1/3.
The
distance
fromthe TheDares , werespectively.
sur80 MWand 1.5× 10
so far.
Recently,
showed that Q⊥div can des terms
zsareato creasethetarget= frontL)
isupstream,thethe detachment
is ∼divertor
640speedm2 ofandthe(zSOL
width∆SOL but
is inASOL
in=the0)Q⊥div is given an assumed value uni−2ube,
S ,point
e×X
is previous
set at zwork= 80
m. As forin- and parm; ourtherefore,
thecross-fieldenergy10formly in the divertor region [22].
sourcetoterms
inSOL
region,Qsimulation
andstudy;
S ⊥SOL= 0.8
evant
the neutral
particles,
ηtrap
⊥SOL
We theextended
ourprevious
we ,an−3
21−3
the attached
and anddetachedtubes
5.0
×de10simultaneously,
m s−1 ,
toalyzed
be
2.67
MWm
estimated
auxiliary
neutraldensities
in
the
(1)
andtheQ⊥div
are modeled
as follows;where
S ⊥divof(det)
ectively.
The
ratio
detachedtube
width= $ to thed tubesatthedivertor
plate
is
n
#
(2)
n,div,aux(det)n− n(att)from theD⊥div distance
1/3.
width
(att) is ∆DD /∆SOL =Γ⊥div
19−3 Thedcxnn,div,aux = 3.5S×⊥div10≈ ∆m ≈ ,−respectively.
,(4)
div divertor∆targetDD ∆Γnation point (z = 0) to the
(z
=
L)
is
#
$
(det)
(att)
χ
n̄
T
−
T
q⊥div
100 m, and the XQ pointis setat⊥divz = 80 m. As .for in-(5)≈−⊥div ≈∆divof∆DD ∆q ofηn and=T 0.8
4 Snapshots
the spatial
profilesin the cases ofarameters Fig.
relevant
to theneutralparticles,
trap
p, we
⊥div
(b))onandbethe non-zero S ⊥div ((c)-(f))
theeffects
zero S ⊥divof((a)Qand(3) examined◦

Numerical Results

the cross-field energy transport

prevent the detachment fronts from moving upstream, i.e.
ofS ⊥div = 0 and the non-zero Q⊥div expressed in Eq. (5).
suchtransport
cancasehamperinstability[1] M. Shimada et al., Nucl.
The ncross-field
and T profiles
in theof S thermal⊥div = Q⊥div = 0[2] D.J.
of aalso
PDD
plasma.
It is(f)).
alsoThefoundthat the positionof Ward, Plasma Phy
are
shown
((e) anddetachment
fronts that(2010).
the detachment
a steady tube
stateareis thermallyunstaITER Physics Expert Gro
move
upstream front
in theindetachedsimulated.[3]The
2391(1999).
ble against
neutralat the1.2
divertorplate.
timeof eachthecurve
is atdensityt = 0 (red),(green),2.4 (blue),[4] L. Loarte et al., Nucl. Fu
Finally,4.9
we(turquoise)make qualitative
K. Tobita et al., Nucl. Fu
3.7 (pink),
and 6.2comparison(yellow) s. of the[5]sim[6]H.
ulation results reported here with experimental observa-Kawashima et al., Nuc[7] S.I. Krasheninnikov et ations. In many tokamak experiments divertor detachment(1999).
[8]
D.E.
Post and R.V. Jense
accompanies a highradiation
peak
which
stagnates
near
M. Nakamura PFR2011
397 (1977).
Fig. 5 Snapshots of the spacial profile of the cross field particle
the Xsource
point[27]).
the other hand,[9] E.asHinnov and J.G. Hirsh
in the divertor
region ofOn
the detachedterm(forS ⊥divexample[10]front
Yu. Gordeev et al., Pisma
the2cross-fieldparticlediffusioncoefficientsofshowntube
in with
Figs.
(e)
and
(f)
and
Fig.
4,
the
detachment
2 −1
2 −1

非接触プラズマにおける課題（１）原子･分子過程
電子ーイオン再結合、分子活性化再結合（水素、炭化水素）（2）非接触プラズマ計測
NAGDIS
プローブ計測の異常性 （門先生)
MAP-II（３）非接触プラズマのエネルギーバランスの理解
TPD
中性ガス温度の影響、輻射輸送の影響（４）非接触プラズマの動的応答
ELM様熱負荷への応答、接触-非接触-再接触遷移過程（５）非接触プラズマ中の径方向輸送
Gamma10
非拡散的輸送現象（Plasma Blobs)(田中先生）（６）非接触プラズマの安定性
LHD
熱的不安定性、2次元効果（部分非接触）
JT-60U(SA)（７）金属壁での非接触プラズマ生成
適切な不純物ガスの選定ーコアプラズマとの共存（８）非接触プラズマの制御手法の確立
Puﬀ&Pump, エルゴディック磁場（磁気島）（増崎先生）（９）先進ダイバータ配位への適用性 ーダイバータ幾何学構造への依存性
Super-X, Snow ﬂake, Isolated divertor etc.

Stored energy (MJ)ne,baar (1019m-3) S

2.1䠊䝛䜸䞁䜢⏝䛔䛯ᨺᑕᦆኻቑ኱䛸ᨺᑕᦆኻ๭ྜ
䝛䜸䞁䝟䝣䛻䜘䜛ᨺᑕᦆኻቑ኱
䝛䜸䜛ᨺᑕᦆኻቑ኱

1
0.8
0.6
0.4
0.2
0
6

Ne

ᨺᑕᦆኻ๭ྜPrad/PNBI䛾ᐦᗘ౫Ꮡᛶ
0.7
0.6
0.5

Pradd/PNBI

4
2

0.4
0.3

Prad (MMW)

0Prad,max

0.2

4

0.1

2

0

P

1

2

3

4

rad

before Ne puffing

5

6
19

ne,bar before Ne puffing (10 m )ne, div (1019m-33)

00.6

పᐦᗘ䛷䛿୙⣧≀䝇䜽䝸䞊䝙䞁䜾ຠᯝ䛜ᑠ䛥䛔䛯䜑䛻䜘䜚῝䛟୙⣧≀䛜౵ධ䛧䚸䛭䛾⤖ᯝ䚸ᨺᑕ㡿ᇦ䛜኱䛝䛟䛺䜚䚸ᨺᑕ㔞䛜ቑ䛘䜛䛸⪃䛘䜙䜜䜛䚹
ᨺ
䛜ቑ
⪃

0
20

Tee, div (eV)Peterson et al., PFR 1 (2006) 045.

• పᐦᗘ: ᨺᑕᦆኻ๭ྜ䛿60䠂⛬ᗘ䛻ཬ䜆

0.3• 㧗ᐦᗘ: ᨺᑕᦆኻ๭ྜ䛿30䠂⛬ᗘỈ⣲䛾䜏䛾ᨺ㟁䛻䛚䛡䜛ᨺᑕᔂቯ᫬䛾ᨺᑕᦆኻ䛸ᴫ
䛽➼䛧䛔䚹

10
0
3.4

7
-3

3.6

3.8

4
4.2
time (s)4.4

4.6

௚䛾୙⣧≀䜺䝇✀䛷᫬㛫ኚ໬䚸ᨺᑕ๭ྜ䛿䛹䛖䛛䠛P rad, P NBI (MWW)

Ar seeding

1
08
0.8
0.6
0.4
0.2
0

8
6
4
2

Ar

0

n e (10 19 m -3)

W p (MJ)

2.2䠊䜰䝹䝂䞁䛻䜘䜛ᨺᑕᦆኻ≉ᛶ• 䜺䝇䝟䝣䜢ษ䛳䛯ᚋ䜒㧗ᨺᑕ≧ែ䛜⥆䛟䚹• 䜺䝇䝟䝣䛻䜘䜛୰ᚰ⥺ᖹᆒ㟁Ꮚᐦᗘ䛾ቑ኱䚸⵳✚䜶䝛䝹䜼䞊䛾ῶᑡ䛿䚸10䠂⛬ᗘ䚹

10

PNBI

• 㧗ᐦᗘ㡿ᇦ䛷䛾ᨺᑕᦆኻ๭ྜ
䛿30䠂⛬ᗘ䚹

5

Prad• 䛔䛪䜜䜒䚸䜾䝻䞊䝞䝹䛻䛿䝛䜸䞁䛸䜋䜌ྠᵝ䛺≉ᛶ䜢♧䛩䞁䛸䜋䜌ྠᵝ䛺≉ᛶ䜢♧䛩䚹

0

4

4.5
Time (s)1010

to divertor plates3䠊ඹ㬆ᦤື☢ሙ䜢⏝䛔䛯⇕⢏Ꮚ㈇Ⲵ㍍ῶ㐠㌿
共鳴摂動磁場を用いた非接触プラズマの制御
Stochastic region

Edge surface layers

0.6

n/m=1/1
perturbation

XͲpoint

100 (a)n (1019 m-3)
࿘㎶䛾෭༷ຠᯝ䛸䚸ᨺᑕ㡿ᇦ䛾X䝫䜲䞁䝖䜈䛾ᒁᅾw/ Island
10 e

w/o Island
5䛆➨14䝃䜲䜽䝹䜎䛷ᡂᯝ䛇
(a)
0

10

1

Phys. Plasmas 17, 056111 !2010"

3.0

3.5

4.0

4.5

3400A
3000A
2500A

1900A
1500A (collapse)
0A (collapse)

Lower: with the n / m = 1 / 1 resonant magnetic perturbation field. The innerpart with long field lines !bright/white scale" is called stochastic region, the1.500 s2.000 souter part with mixture of2.900
long !bright/whites Detach scale" and short !dark scale" is
3.800 scallededge
surfacelayers.
The
perturbation
field creates remnant island in
4.300
s
3.966 s Collapse
the stochastic region with the O-point located at outboard side in this sec19 m-3)legs are stretched from thetion. The
divertorin- 19andout-boardsides towardne (10m-3)
ne (10target plates, which are not shown.

04

Radiation intensity (a.u.)• ᨺᑕ㡿ᇦ䛾Ᏻᐃಖᣢ
10
Radiation (a.u.)20• ᨺᑕᦆኻ䛾ቑ኱䠄2ಸ⛬ᗘ䠅Collapsetion length inside island. Since the island is embedded in the10• ཷ⇕ᯈ䜈䛾⇕䞉⢏Ꮚ㈇Ⲵῶᑡ䠄1/3~1/10䠅
stochastic
the separatrix is no longer clear. The(b)
2 region,(b) LCFS(d) LCFS
1
0
X-pointoftheislandis, therefore,
visible
4.4
4.5
4.6
4.7
4.8 Sustained
4.9
4.4
4.5
4.6
4.7 not4.8
4.9in the plot. By• 㛢䛨㎸䜑䛾ຎ໬䛺䛧R(m)strictdefinition,
it
may
not
be
calledso.
Inthe following,R(m)Iis (A)detachhowever,
we
may
keep
the
term
“X-point”
representingthe• ⬟ືⓗไᚚ᪉ἲ䛾☜❧䠄ᐦᗘ䚸ᦤື☢ሙᙉᗘ䠅
FIG. 7. "Color online#
Radialwhere
profilesaof
T andn at thewouldedge region"a#0.5
regionclear
X-point
haveforexistedwithout theeeand "b# without the island, where the plasma goes to radiative collapse atstochastization,or justpoloidally
oppositet % 4.0 s, !"c# and "d#$with the island, where
the sustained
detachment
was side torealized at t " 2.900 O-point.
s. The latter case is characterized by the Te flattening
inside the island with "10 eV. LCFS is located around R = 4.55 m. The"a few eV# plasma
is formed outsideWITH
the LCFS.
dense "%1020 m−3# andIII. cold
DETACHMENTSUSTANMENT
N/M=1/1"No. 85946 for withISLAND
island and No. 85948 for without island.#(c)≀⌮ⓗᥥീ䛾⌮ゎ1the• 䝅䝭䝳䝺䞊䝅䝵䞁䛸䛾ẚ㍑
Gas puff2• ☢ሙ㓄఩䝇䜻䝱䞁䛸౫Ꮡᛶ䛾⪃ᐹ
Figure 3 shows the time traces of plasma parameters
21 H/s)(10
the sustained
detachment
ted in Fig. 7. Inobtained
the case inwithout
the island!Figs. 7"a#shot
andwith the n / m(d)14• 㠀ᣑᩓⓗ㍺㏦≉ᛶ0= 1 / 10perturbation
field !shot
number:85946".
7"b#$, the Te monotonicallydecreasesat theentireedge The discharge➨15䝃䜲䜽䝹

0

1

2

3
4
time (s)567

was initiatedt =21.3
s bytheneutralbeamtoinjection!NBI"
4theplasma
6goes
8
10
region as the density
is 0
raised,atand
finallyheating,
ramped
up by
gas
puff
graduradiative collapse
at the andlosstheof density
density wascontrol.
In19
the
case
n
(10
m-3T) current, Fig.
e otherally. The
particle
flux#ion hand,saturation
with the island !Figs.
7"c#divertor
and 7"d#$,on thee
3!b"$ measured
by the Langmuirprobe
as a sum of 39
allcontinuously decreases
with increasing
densityat thearrays,
outerFIG. 11. !Color
online" Evolutionof radiation
intensity measured by the
probe
tips,
increases
linearlywithrespecttothedensityrise
most region, Rresistive" 4.75 bolometerm, untilasthe
detachment
a functionof line transition.
averaged density, for different
until
detachmenttransition
without
exhibitinghighcircles=
3400 A,
openrecycircles/ m =transition,1the/ 1 perturbation
Icoil: closed
However, after nthe
it iscurrent,
stabilizedarounda few=cling3000 regime
A, triangles=
2500
A, diamonds=with
1900theA, squaresquares=scaling
1500 A,asand
thatischaracterized
eV, while keeping almost same T at the inner region

M. Kobayashi PoP2010

FIG. 6. "Color online# Time traces of "a# line averaged density, "b# radiation
intensity measured by AXUVD, "c# divertor particle flux, and "d# gas puff
rate, respectively. Thin lines: sustained detach with n / m = 1 / 1 island; thicklines: radiative collapse without the island. "No. 85946 for with island andNo. 85948 for without island.#

18

5.0

(c)
Te (eV)Te (eV)
FIG. 2. !Color
online" Connection length !LC" distribution
in poloidal cross
Attachsection at horizontally elongated section. Upper: without perturbation field.

310q// (W/m2)

-0.4

R (m)
056111-8
Kobayashi
et al.detach
Radiative collapse(w/o island)
Sustained(w/ island)

15

(b)

ne (m-3)

10
10Magnetic island
O-point

0

-0.6
2.5

10

19

177 (c)0.2-0.2

Detachment stabilization with n / m = 1 / 1…

Inboa

0.2

6

10

5

10
20

(a.u.)

056111-5

divertor

NAGDIS, Nagoya Univ.0

Wp (kJ)ඹ㬆ᦤື☢ሙ䛻䜘䜚䚸n/m=1/1䛾☢Ẽᓥ䜢ඹ㬆ᦤື☢ሙ䛻䜘䜚/ 1/1䛾☢Ẽᓥ䜢᭱እẆ☢Ẽ㠃እഃ䛻⏕ᡂ

(a)

0

(d)
Radiation(by AXUVD)

10

Phy

(e)
0 500

200
100
0
5

Te (eV)

Z (m)

0.4

5

0.4

0

Hγ / Hβ

LHD䛻䛚䛡䜛ᨺᑕ㡿ᇦ䛾Ᏻᐃ໬ne (1019

10

Iis (A)10

to divertor plates

10

400
(f)

Radia

300

gas puff (102

(g)

200

0.1
(h)
100

0
0

1

2
3
4
LCFStime(s)(without island)

0 online" Time traces of variou
FIG. 3. !Color
4.2 shot with4.4
sustained detachmentn / m = 1 / 1 islan
and !b" divertor particle flux at upper and inbo
R
separated toroidally by %160°. !c" Electron
temperature !open squares" at the inboard div
FIG. 12. T profiles during attachment p
muir probe, !d"e power flux to inboard divert
cation for three different configurations. T
Langmuir probe, !e" radiation intensity measu
theemission
configuration
islands.
!broken theline",!f" stoandforlineof H" without
the each probe,
configuration
is indicatedwithl
diamagnetic!g" net NBI
heating !solid
detachment
was ofrealized
for the con
H$ measuredbyline",
and !h" ratio
H# to only
circles.toroidal locations indicated by torodifferent
detachment occurs at t % 2.9 s and was sustain
terminated by stop of NBI heating !No. 85946

detachment case and nearly 200 e

非接触プラズマにおける課題（１）原子･分子過程
電子ーイオン再結合、分子活性化再結合（水素、炭化水素）（2）非接触プラズマ計測
NAGDIS
プローブ計測の異常性 （門先生)
MAP-II（３）非接触プラズマのエネルギーバランスの理解
TPD
中性ガス温度の影響、輻射輸送の影響（４）非接触プラズマの動的応答
ELM様熱負荷への応答、接触-非接触-再接触遷移過程（５）非接触プラズマ中の径方向輸送
Gamma10
非拡散的輸送現象（Plasma Blobs)(田中先生）（６）非接触プラズマの安定性
LHD
熱的不安定性、2次元効果（部分非接触）
JT-60U(SA)（７）金属壁での非接触プラズマ生成
適切な不純物ガスの選定ーコアプラズマとの共存（８）非接触プラズマの制御手法の確立
Puﬀ&Pump, エルゴディック磁場（磁気島）（増崎先生）（９）先進ダイバータ配位への適用性 ーダイバータ幾何学構造への依存性
Super-X, Snow ﬂake, Isolated divertor etc.

SlimCSóøįİĭøg¢Ç0CëNëZBôq@CëNëZB÷ñæòg¢#3böċĆĠùQïäµđĆĕĦĐøDL÷$môçĀăĂċ ĆĠø±ä7_øüód#Z÷đĆĕĦĐċĆĠĄ3±
Ip=16.7MA, β_p=2.5, l_i=0.6

fsxd=0.99

SlimCS óøčĔĦĘġĦĊđĆĕĦĐ@øg¢HďġĔĆēøċĆĠ(No.20, 21, 22)êä6 ¸h4DL÷¸öFĄeðïòæĂå

先進ダイバータへの適用に関する課題
先進ダイバータでの安定な非接触プラズマの生成は可能か＃熱不安定性＃磁場構造（エルゴディック領域の影響）＃中性ガス（温度）の影響＃径方向輸送（特にblob輸送）

NSTX snowflake experiment(V.A. Soukhanowski, USBPO E-News, #42, p. 3, 2010; V.A.
Soukhanowski et al, PSI poster P1-28, Monday 24 May 2010)
Heat flux reduction by a factor of ~3
Easier detachment (no need in gas puff)
Carbon content in the core down by a factor ~ 2
Radiation from the core down by a factor ~ 2
Radiation from divertor up by a factor of a few
No noticeable adverse effect on core plasma density and temperature非接触プラズマにおける課題（１）原子･分子過程
電子ーイオン再結合、分子活性化再結合（水素、炭化水素）（2）非接触プラズマ計測
NAGDIS
プローブ計測の異常性 （門先生)
MAP-II（３）非接触プラズマのエネルギーバランスの理解
TPD
中性ガス温度の影響、輻射輸送の影響（４）非接触プラズマの動的応答
ELM様熱負荷への応答、接触-非接触-再接触遷移過程（５）非接触プラズマ中の径方向輸送
Gamma10
非拡散的輸送現象（Plasma Blobs)(田中先生）（６）非接触プラズマの安定性
LHD
熱的不安定性、2次元効果（部分非接触）
JT-60U(SA)（７）金属壁での非接触プラズマ生成
適切な不純物ガスの選定ーコアプラズマとの共存（８）非接触プラズマの制御手法の確立
Puﬀ&Pump, エルゴディック磁場（磁気島）（増崎先生）（９）先進ダイバータ配位への適用性 ーダイバータ幾何学構造への依存性
Super-X, Snow ﬂake, Isolated divertor etc.