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Tiêu đề Confinement and heating of a deuterium tritium plasma
Tác giả Strachan, JD, Adler, H, Alling, P, et al.
Trường học University of California, Irvine
Chuyên ngành Plasma Physics
Thể loại journal article
Năm xuất bản 1994
Thành phố Irvine
Định dạng
Số trang 6
Dung lượng 809,92 KB

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UC Irvine Previously Published Works Title Confinement and heating of a deuterium tritium plasma Permalink

Trang 1

UC Irvine

UC Irvine Previously Published Works

Title

Fusion power production from TFTR plasmas fueled with deuterium and tritium.

Permalink

https://escholarship.org/uc/item/1mj5r9vt

Journal

Physical review letters, 72(22)

ISSN

0031-9007

Authors

Strachan, JD

Adler, H

Alling, P

et al.

Publication Date

1994-05-01

DOI

10.1103/physrevlett.72.3526

License

https://creativecommons.org/licenses/by/4.0/ 4.0

Peer reviewed

University of California

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Fusion Power Production from TFTR Plasmas Fueled with Deuterium and Tritium

J.D Strachan, ' H Adler, ' P.Ailing, ' C.Ancher, ' H Anderson, ' J.L.Anderson, D.Ashcroft, ' Cris W,

Budny, ' C E. Bush, R. Camp, ' M Caorlin, ' S.CauA'man, ' Z Chang, C Z. Cheng, ' J.Collins, ' G

Fisher, R J.Fpnck, E.Fredrickspn, ' N Frpmm, ' G Y.Fu,' H P.Furth, ' C.Gentile, ' N Gprelenkpv,

LeBlanc,' M Leonard, ' F.M Levinton, J.Machuzak, D K.Mansfield, ' A Martin, ' E.Mazzucato, ' R.

D M Meade, ' S S.Medley, ' D R. Mikkelsen, ' D Mueller, ' M Murakami, A Nagy, ' R. Nazikian„'

Park, ' W Park, ' S F. Paul, ' G. Pearson, ' E. Perry, ' M Petrov, ' C. K Phillips, ' S.Pitcher, ' A T.

Sissingh, ' C. H Skinner, ' J. A Snipes, J.Stevens, ' T.Stevenson, ' B C. Stratton, ' E.Synakowski, ' W

Plasma Physics Laboratory, Princeton Unit ersity, P.O.Box 451,Princeton, New Jersey 08543

Los Alamos National Laboratory, Los Alamos, New Mexico 87745

Fusion Physics and Technology, Torrance, California 9050l

Oak Ridge National Laboratory, Oak Ridge, Tennessee 37830

University ofWisconsin, MadisonWisco, nsin 5370I

General AtomicsSan D,iego, California 92IOl Massachusetts Institute ofTechnology, Cambridge, Massachusetts 02138

University ofCalifornia, Irvine, California 92714

' JETJoint Undertaking, Abingdon, United Kingdom

'iNational Institute for Fusion Science, Nagoya, Japan

' loge Physical Technical -Institute, leningrad, .Russia

' Canadian Fusion Fuels Technology Project, Toronto, Canada

' Columbia University, New York, New York 10027

(Received 10 February 1994)

Peak fusion power production of6.2~0.4 M% has been achieved in TFTR plasmas heated by

deu-terium and tritium neutral beams at a total power of29.5M% These plasmas have an inferred central

fusion alpha particle density of 1.2 &10' m without the appearance ofeither disruptive

magnetohy-drodynamics events or detectable changes in Alfven wave activity The measured loss rate ofenergetic

alpha particles agreed with the approximately 5%losses expected from alpha particles which are born on

unconfined orbits

PACS numbers: 52.25.Fi, 2S.52.Cx, 52.55.pi

Most previous experiments in magnetic fusion research

have been conducted with hydrogen or deuterium

plas-mas, even though first generation fusion reactors are

higher than the Dfusion reactivity, more fusion reactions

occur and a significant population of the charged fusion

(TFTR) has performed initial D-T experiments and has

tokamak to use T [1]and the first touse equal

concentra-tions of D and T. A separate paper [2] describes the

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VOLUME 72, NUMBER 22 PHYSICAL REVIEW LETTERS 30MAY 1994

the fusion reactions, and the search for alpha-induced

in-stabilities

fusion power of 6 2~0.4 MW was produced with a

cor-responding 14 MeV neutron emission rate of up to

field, 2.52 m major radius, and 0.87m minor radius The

D-T was fueled by operating one to eight of the twelve

power including one with 10%ofthe beam power in

MeV neutron emission ofabout 3.5x 10' sec

The neutron emission rates and yields were measured

with fission chambers [4],silicon surface barrier diodes

[6]and ZnS scintillators [7],and a variety ofelemental

more sensitive to the latter An absolute calibration of

the fission chambers, proportional counters, and

gen-erator [9].The estimated absolute accuracy ofeach

cali-bration isabout +10%to +25/0 while the statistical

de-viation of all available calibration data is ~7%. The

calibrat-ed signals with the ~7% standard deviation.

was I0% 15%grea-ter than that calculated from the

individual neutron measurement uncertainty, which is

plasma energy content (Fig 3) displays a broad

10

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CO

K

UJ

Z

0

K 1—

UJ

0

UJ

1—

0 0

10

10

10 1016

I I I I I I I I I I I II

MEASURED NEUTRON EMISSION (/sec) 10

FIG I. The neutron emission calculated by the equilibrium code SNAP (crosses) and calculated by the time-dependent code TRANSP (solid squares) as a function of the neutron source strength measured bythe TFTRfission detectors

neutron emission The D-T neutron rate in the 100%T

con-sistent with a significant (40%)concentration ofthermal

D in the plasma core during pure-T injection

The D-T neutron emission [Fig 2(a)] reached a

max-imum at 3.45 s and then decreased to about 80% ofthe peak level by 3.68 s when a source fault caused a

simu-lation reproduces this decrease in emission, indicating that it does not occur as a result ofthe anomalous loss of energetic ions but is associated with the evolution ofthe

simultaneously, the plasma stored energy are often

ob-served in deuterium supershots with high neutral beam

powers These decreases have been correlated

quantita-tively with the amplitudes of low mode-number (m/n

and with secular increases in the deuterium influx from

with m/n =4/3 was detected in the electron temperature

profile starting at about 3.4 s It is interesting to note,

however, that the fractional decline in the D-T neutron

rate for this plasma in the interval 3 45-3.68 s was less

plas-mas having the same ratio of stored energy to plasma current and the same magnetic field

The fusion alpha particles escaping from the plasma

low-power plasmas, the relative alpha particle loss decreased

by a factor of about 4 between 0.6 MA and 1.8 MA, in rough agreement with the calculated variation in the first-orbit loss to this detector (Fig.4). The total loss of

3527

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Fluctuations Fluctuations

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TIME (sec) 4.0

was also roughly consistent with expectations based on

the simple first-orbit loss model calibrated by the signal

lost) In particular, the alpha loss fraction did not

in-FIG 2 Time evolution of the plasma with the highest D-T

neutron emission. (a) The beam power (in units of 10 MW),

the measured D-T neutron emission (in units of 10Issec ')

(solid line), and the TRANSP calculated value (dashed line),

in-cluding the calculated contributions of beam target, beam

beam, and thermonuclear reactions (b) The measured

collec-tion rate of energetic (&1 MeV) escaping alphas (solid line),

the calculated central alpha particle denisty (in units of 10'

m ), and the calculated detector signal (by TRANsP) due to

classical first orbit loss. (c)The TRANSP calculated central

al-pha pressure (p,=2@opJa ) (in units of 10 ),the ratio of

al-pha velocity to Alfven velocity, and the measured amplitude of

the Mirnov signal at the TAE frequency range taken from

several D-Tand D comparison plasmas

I I I I

I I I

I I

FRACTION OF BEAM POWER IN TRITIUM

FIG 3 D-T neutron emission at peak stored energy divided

by the square ofthe plasma energy content plotted asa function

ofthe fraction ofthe beam heating coming from Tbeams The solid curve isthe expected dependence ifthe fueling ofthe

plas-ma were entirely from the beams The dashed curve corre-sponds to one-half ofthe fueling from the beams and one-half from the walls (deuterium only) The normalization ofthe neu-tron emission tothe square ofthe energy content was chosen on the basis of the empirical scaling of D-D neutron emission

[12,13]since there have not been enough D-T data toestablish its scaling

that the alpha particles were not being lost as a result of instabilities driven by the alpha particle pressure itself

fol-lowing the beam heating when the alpha pressure remains

high [Fig.2(c)]and the average alpha velocity reduces to the Alfven velocity However, the plasma fluctuation

ac-tivity [18,19]in the TAE range of frequencies (250kHz

during beam heating, rising to 500 kHz after injection)

reflectometer [19]indicates that the upper limit of

density fluctuation of about 2&&10 [due mostly to the

detect-ed at low field and high density [20,21]by the same

ter-mination ofthe beam heating [Fig.2(c)].

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anoma-VOLUME 72, NUMBER 22 PHYSICAL REVIEW LETTERS 30MAY 1994

10 8

0.5

o 20

norm.

O

C5

O

O

I 6

0

O

4 ~ 90'detector

CL

I I

first-orbit loss (calculated)

ious alpha particle losses nor observable instabilities The TFTR fusion yield can be increased through increases in

con-finement time by lithium wall conditioning [22].

Laborato-ry under the leadership of R. Davidson This work was

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fTAE(q=2)t fTAE(q=

-4

10 =

6$

10::

— (b) D-D'— """': '. .-, :..., ,:

Frequency (kHz)

FIG 5 High frequency fluctuation data taken immediately

after the beam heating for D-Tand D plasmas. The shaded

re-gion shows the approximate lower bound on the previously

ob-served TAE mode (a)Amplitude spectra ofan outboard

Mir-nov coil signal showing a weak power near the expected TAE

frequency. (b) Reflectometer power spectra at a major radius

of2.92m (the plasma magnetic axis isat 2.63m)

Plasma current (MA)

FIG 4 The measured alpha particle loss rate to the vessel

bottom per created alpha (i.e., the global neutron source

strength) as afunction ofplasma current The shaded region is

the calculated alpha first-orbit loss for this location where the

data are calibrated by the signal at 0.6 MA where all the

trapped alpha particles are lost The x points are low power,

quiescent plasmas and the circles are the high power D-T

plas-mas

[I]JETTeam, Nucl Fusion 32,187(1992)

[2] R.J.Hawryluk et al., following Letter, Phys. Rev Lett

72,3530(1994)

[3]J.D Strachan et al.,Phys Rev Lett 58, 1004(1987)

[4) H Hendel et al.,Rev.Sci.Instrum 61,1900(1990) [5]H H.Duong and W W Heidbrink, Nucl Fusion 33, 211 (1933).

[6]J.S.McCauley and J. D Strachan, Rev Sci Instrum.

63, 4536(1992)

[7] L.Johnson, Rev.Sci.Instrum 63, 4517 (1992)

[8] C.W Barnes etal.,Rev Sci.Instrum 61, 3190(1990). [9]A L.Roquemore et al., in Proceedings ofthe 15th IEEE

Symposium on Fusion Engineering, Hyannis, Mass-achusetts, 1993 (tobepublished)

[IO] H H Towner et al.,Rev Sci.Instrum 63, 4753 (1992) [I I] R.Budny etal.,Nucl Fusion 32, 429(1992)

[12]J.D Strachan et al.,Nucl Fusion 33, 991 (1993). [13]M G Bell et al., in Plasma Physics and Controlled Fusion Research (IAEA, Vienna, 1989),Vol I,p.27

published)

[15]J.D Strachan, Report No PPPL-2933, 1993 (tobe pub-lished)

[16]S.J.Zweben et al.,Phys Fluids B(tobe published)

[17]C Z.Cheng et al., in Plasma Physic and Controlled Nu-clear Fusion Research 1992 (IAEA, Vienna, 1993),Vol

II,p.51

[18] E D Fredrickson et al., Rev Sci Instrum. 59, 1797

(1988)

[19] E.Mazzucato and R.Nazikian, Phys. Rev Lett 71,1840

(1993).

[20]G.Taylor et al., Phys Fluids B 5, 2437(1993).

[21] K-L.Wong etal.,Phys. Rev Lett 66, 1874(1991). [22]J.Snipes et al.,J.Nucl Mater 196-19$, 686(1992)

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