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Japan-US Workshop on Fusion Power Plants Related Advanced Technologies with participants from China and Korea Kyoto University, Uji, Japan, 26-28 Feb. 2013

Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

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Page 1: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

Japan-US Workshop on Fusion Power Plants Related Advanced Technologies with participants from China and Korea

(Kyoto University, Uji, Japan, 26-28 Feb. 2013)

Page 2: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, Japan-US WS on Fusion Power Plants Related Advanced Technologies (Kyoto Univ., 26-28 Feb. 2013) 2/22

Page 3: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

Schematic view of FFHR-d1 (by H. Tamura)

Vertical slices of FFHR-d1 (by T. Goto)

FFHR-d1 Rc = 15.6 m Bc = 4.7 T Pfusion ~ 3 GW

3/22 J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, Japan-US WS on Fusion Power Plants Related Advanced Technologies

(Kyoto Univ., 26-28 Feb. 2013)

Page 4: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

Experiment

Reactor

J. Miyazawa et al., Fusion Eng. Des. 86, 2879 (2011)

pGB-BFM(ρ) = α0 ne(ρ)0.6 P0.4 B0.8 J0(2.4ρ/α1)

4/22 J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, Japan-US WS on Fusion Power Plants Related Advanced Technologies

(Kyoto Univ., 26-28 Feb. 2013)

Page 5: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

γDPE ∝ ((Pdep/Pdep1)avg,reactor) / (Pdep/Pdep1)avg,exp)0.6 = (0.65 / (Pdep/Pdep1)avg)0.6 …where 0.65 is the assumed peaking factor of the alpha heating in the reactor

J. Miyazawa et al., Nucl. Fusion 52 (2012) 123007.

FFHR-d1

5/22 J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, Japan-US WS on Fusion Power Plants Related Advanced Technologies

(Kyoto Univ., 26-28 Feb. 2013)

Page 6: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

One from the standard configuration of Rax = 3.60 m, γc = 1.25

Another from the high aspect ratio configuration of Rax = 3.60 m, γc = 1.20

The high-aspect ratio configuration is effective for Shafranov shift mitigation

γc = (m ac) / (l Rc) is the pitch of helical coils, where m = 10, l = 2, ac ~ 0.9 – 1.0 m, and Rc = 3.9 m in LHD

6/22

Page 7: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

FFHR-d1 Device Parameters

・device size Rc = 15.6 m

・mag. field Bc = 4.7 T

・fusion output PDT ~ 3 GW

・radial profiles given by DPE

MHD Equilibrium and Stability

・HINT2

・VMEC

・TERPSICHORE

Neoclassical Transport

・GSRAKE/DGN

・DCOM

・FORTEC-3D

α Particle Transport

・GNET

・MORH

Anomalous Transport

・GKV-X

Detailed physics analyses on MHD, neoclassical transport, and alpha particle transport using profiles given by the DPE method have been started

7/22 J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, Japan-US WS on Fusion Power Plants Related Advanced Technologies

(Kyoto Univ., 26-28 Feb. 2013)

Page 8: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

By Y. Suzuki

Rax = 14.4 m

“Vacuum”

Rax = 14.4 m

“w/o Bv”

Rax = 14.0 m

“w/ Bv”

Rax = 14.4 m

“Vacuum”

Rax = 14.4 m

“w/o Bv”

Rax = 14.0 m

“w/ Bv”

8/22 J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, Japan-US WS on Fusion Power Plants Related Advanced Technologies

(Kyoto Univ., 26-28 Feb. 2013)

Page 9: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

By S. Satake

Neoclassical heat flow in various cases Comparison with Pα in Case B w/ Bv

0

0.1

0.2

0.3

0.4

0.5

0.6

0 0.2 0.4 0.6 0.8 1

Qto

tneo S

(GW

)

ρ

Qtot

neo S Pα - P

B

PB

Qineo S

Qe

neo S

0

1

2

3

4

0 0.2 0.4 0.6 0.8 1

Qto

tneo S

(GW

)

ρ

case A, w/o Bv

case A, w/ Bv

case B, w/ Bv

vacuum

9/22 J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, Japan-US WS on Fusion Power Plants Related Advanced Technologies

(Kyoto Univ., 26-28 Feb. 2013)

Page 10: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

By Y. Masaoka and S. Murakami (Kyoto Univ.)

10/22 J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, Japan-US WS on Fusion Power Plants Related Advanced Technologies

(Kyoto Univ., 26-28 Feb. 2013)

Page 11: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

Rax = 14.4 m Vacuum

Rax = 14.4 m β0 ~ 8.5 %

Rax = 14.0 m β0 ~ 10 %

By R. Seki

11/22 J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, Japan-US WS on Fusion Power Plants Related Advanced Technologies

(Kyoto Univ., 26-28 Feb. 2013)

Page 12: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

By R. Seki and T. Goto

12/22 J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, Japan-US WS on Fusion Power Plants Related Advanced Technologies

(Kyoto Univ., 26-28 Feb. 2013)

Page 13: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

Case A Rax = 3.60 m

γc = 1.254

neo/nebar ~ 1.5

MHD equilibrium

Shafranov shift is too large

Neoclassical

→ ✖

α confinement

→ ✖

Case B Rax = 3.60 m

γc = 1.20

neo/nebar ~ 0.9

MHD equilibrium

Shafranov shift is mitigated by

applying Bv

Neoclassical

α confinement

α heating profile

→ ✖ (hollow)

Case C Rax = 3.55 m

γc = 1.20

neo/nebar ~ 1.5

MHD equilibrium

?

Neoclassical

→ ? α confinement

→ ?

α heating profile

→ ?

Both NC and α confinement are bad in the Case A, due to the large Shafranov shift.

Both NC and α confinement are good in the Case B where Shafranov shift is mitigated. However, α heating profile is hollow (not consistent with the assumption for γDPE).

Case C’ Rax = 3.55 m

γc = 1.20

neo/nebar ~ 1.5

MHD equilibrium

?

Neoclassical

→ ? α confinement

→ ?

α heating profile

→ ?

α heating efficiency

→ ?

In the Case C’, α heating efficiency, ηα = 0.85 is assumed (ηα = 1.0 in Cases A, B, and C).

A new profile “Case C” has been chosen. Peaked density profile as the Case A. High-aspect ratio as the Case B but more inward-shifted.

13/22 J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, Japan-US WS on Fusion Power Plants Related Advanced Technologies

(Kyoto Univ., 26-28 Feb. 2013)

Page 14: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

14/22

Page 15: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

15/22

Rax = 14.4 m, β0 ~ 7.5 %, “w/o Bv”

Rax = 14.2 m, β0 ~ 7.6 %, “w/o Bv”

Rax = 14.0 m, β0 ~ 7.6 %, “w/ Bv”

Rax = 14.0 m, β0 ~ 9.1 %, “w/ Bv”

Rax = 14.0 m, β0 ~ 8.2 %, “w/ Bv”

MHD equilibrium is ready

Bad?

Good?

??

Bad

Good

Page 16: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, FFHR-d1炉設計合同タスク会合(1 Feb. 2013) 16/22

Page 17: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

Device Name LHD FFHR-c1.0 FFHR-c1.1 FFHR-d1 Target Experiment Q ~ 7 Self-ignition Self-ignition

Rc helical coil major radius

3.9 m 13.0 m (10/3 times LHD)

15.6 m (4 times LHD)

Vp plasma volume

~30 m3 ~1,000 m3

(similar to ITER) ~2,000 m3

Bc magnetic field strength at the helical coil center

2.5 T 4.0 T

(design value of LHD) NbTiTa (He II) / HTS

5.3 T (similar to ITER)

Nb3Sn / Nb3Al / HTS

4.7 T Nb3Sn / Nb3Al / HTS

Wmag stored magnetic energy

1.6 GJ (at 4 T)

67 GJ 113 GJ 160 GJ

Paux auxiliary heating power

25 MW (short pulse) ? ? 50 MW - 1 hour

(for start-up)

Pfusion fusion power

– ? ? ~3 GW (Q = ∞)

τduration duration time of a shot

~1 hour ? ? ~1 year

Φn dpa per shot

– ? ? ~15 dpa (1.5 MW/m2 x 1 year)

Issues DD exp. ? ? large HC winding

react & wind nuclear heating on SC

lifetime of SC/insulator

17/22

Page 18: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

- The confinement enhancement factor is proportional to the 0.6 power of the heating profile peaking factor:

γDPE = ((Pdep/Pdep1)avg,reactor) / (Pdep/Pdep1)avg,exp)0.6

= (0.65 / (Pdep/Pdep1)avg)0.6

- The heating profile peaking factor with the central auxiliary heating can be larger than 0.65

- Assume that the auxiliary heating is focused on the center and expressed by the delta function, i.e.,

(Pdep/Pdep1)avg,reactor = 0.65 (1/Caux) +(1.0 – 1/Caux)

= 1.0 – 0.35/Caux

- The confinement enhancement factor is given by

γDPE* = ((1.0 – 0.35/Caux ) / (Pdep/Pdep1)avg)0.6

Caux = 1.0

Caux = 2.0

Caux = 7.0

18/22 J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, Japan-US WS on Fusion Power Plants Related Advanced Technologies

(Kyoto Univ., 26-28 Feb. 2013)

Pα – PB = (1 / Caux) Preactor Paux = (1 – 1 / Caux) Preactor

Page 19: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

FFHR-c1.0, Caux = 1.8

Pfusion ~ 1 GW with Paux ~ 140 MW

19/22 J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, Japan-US WS on Fusion Power Plants Related Advanced Technologies

(Kyoto Univ., 26-28 Feb. 2013)

Page 20: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

FFHR-c1.1, Caux = 1.0

Pfusion ~ 2 GW without Paux

20/22 J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, Japan-US WS on Fusion Power Plants Related Advanced Technologies

(Kyoto Univ., 26-28 Feb. 2013)

Page 21: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

21/22

Device Name LHD FFHR-c1.0 FFHR-c1.1 FFHR-d1 Target Experiment Q ~ 7 Self-ignition Self-ignition

Rc helical coil major radius

3.9 m 13.0 m (10/3 times LHD)

15.6 m (4 times LHD)

Vp plasma volume

~30 m3 ~1,000 m3

(similar to ITER) ~2,000 m3

Bc magnetic field strength at the helical coil center

2.5 T 4.0 T

(design value of LHD) NbTiTa (He II) / HTS

5.3 T (similar to ITER)

Nb3Sn / Nb3Al / HTS

4.7 T Nb3Sn / Nb3Al / HTS

Wmag stored magnetic energy

1.6 GJ (at 4 T)

68 GJ 113 GJ 160 GJ

Paux auxiliary heating power

25 MW (short pulse)

140 MW - CW (for sustainment)

50 MW - 1 hour (for start-up)

50 MW - 1 hour (for start-up)

Pfusion fusion power

– ~1 GW (Q > 7)

~2 GW (Q = ∞)

~3 GW (Q = ∞)

τduration duration time of a shot

~1 hour ~1 year ~5 month ~1 year

Φn dpa per shot

– ~8 dpa (0.8 MW/m2 x 1 year)

~7 dpa (10 dpa at peak) (1.7 MW/m2 x 5 month)

~15 dpa (1.5 MW/m2 x 1 year)

Issues DD exp. large HC winding

R&D of (NbTiTa & He II cooling) or HTS

large HC winding react & wind

nuclear heating on SC lifetime of SC/insulator

large HC winding react & wind

nuclear heating on SC lifetime of SC/insulator

Page 22: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

22/22 J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, Japan-US WS on Fusion Power Plants Related Advanced Technologies

(Kyoto Univ., 26-28 Feb. 2013)

Page 23: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

FFHR-d1, Caux = 1.0

Pfusion ~ 2 GW without Paux

23/22 J. Miyazawa, “Core Plasma Design for FFHR-d1 and c1”, Japan-US WS on Fusion Power Plants Related Advanced Technologies

(Kyoto Univ., 26-28 Feb. 2013)

Page 24: Japan-US Workshop on Fusion Power Plants Related …aries.ucsd.edu/LIB/MEETINGS/1302-USJ-PPS/Miyazawa.pdfFusion Power Plants Related Advanced Technologies with participants from China

The central pressures similar to those in the γc = 1.254 configuration have also been achieved in the γc = 1.20 configuration, in spite of smaller plasma volume (i.e., better confinement in γc = 1.20)

fβ as low as ~3 has been achieved

Preactor can be as low as ~200 MW

Density peaking factor is high (density peaking was observed after NB#1 break down)

24/22