Results of the first experiments on the T-10 Tokamak

Berlizov, A. B.; Bobrovskii, G. A.; Bagdasarov, A.A.; Vasin, N.L.; Vertiporokh, A.N.; Vinogradov, V. P.; Vinogradova, N. D.; Gegechkori, N.M.; Gorbunov, E.P.; Dnestrovskii, Yu.N.; Zaveryaev, V.S.; Izvozchikov, A.; Luk'yanov, S. Yu.; Лысенко, С. Е.; Maksimov, Yu. S.; Notkin, G.E.; Петров, М. П.; Popkov, G. N.; Razumova, K. A.; Strelkov, V. S.; Shcheglov, D. A.

doi:10.1007/bf01118277

Cited by 20 publications

(32 citation statements)

References 2 publications

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“…As in other experiments [ 1,2,8], the fast schemes lead to disruption immediately after the q(a) = 2 crossing.…”

supporting

confidence: 78%

“…4) Some tokamaks without shell stabilization have tried to cross the q(a) = 2 barrier. In T-10, stable discharge with cylindrical q*(a) > 1.8 could be obtained, provided the liner-limiter radii ratio b/a is large enough [8]. These results were confirmed by Doublet III [ 1 ], and considerations on the role of surface kink modes and the effect of a cold plasma blanket were published [9].…”

Section: Soft X-rays Profiles Atmentioning

confidence: 69%

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Low-Q MHD activity studies on TFR

1984

Nucl. Fusion

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“…As in other experiments [ 1,2,8], the fast schemes lead to disruption immediately after the q(a) = 2 crossing.…”

supporting

confidence: 78%

Section: Soft X-rays Profiles Atmentioning

confidence: 69%

Low-Q MHD activity studies on TFR

1984

Nucl. Fusion

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“…According to radiation loss calculations based on the corona model ( [18,19]; a review is given in.Ref. [20]), an upper limit of about 2 X 10' 4 for the iron content in the centre of the DL plasma can be deduced from PRAD (0) ^ o n e assumes that only iron radiates in the centre. More detailed calculations using spectroscopic results and taking into account anomalous transport and inward drift processes [21 ] yield an iron content of 1.0 X 10" 4 for L discharges.…”

Section: Radiation Profiles Of Different Discharge Typesmentioning

confidence: 99%

Radiation losses and global energy balance for Ohmically heated discharges in ASDEX

1982

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Global energy balance, radiation profiles and dominant impurity radiation sources are compared for Ohmically heated limiter and divertor discharges in the ASDEX tokamak. In discharges with a poloidal stainless-steel limiter, total radiation from the plasma is the dominant energy loss channel. The axisymmetric divertor reduces this volume-integrated radiation to 30-35% of the heating power and additional Ti-gettering halves it again to 10-15%. Local radiation losses in the plasma centre, which are mainly due to the presence of iron impurity ions, are reduced by about one order of magnitude. In high-current (I p = 400 kA) and high-density (n e = 6 X 10 13 cm" 3 ) ungettered divertor discharges, up to 55% of the heating power is dumped into a cold-gas target inside the divertor chambers. The bolometrically detected volume power losses in the chambers can mainly be attributed to neutral hydrogen atoms with kinetic energies of a few eV. In this parameter range, the divertor plasma is dominated by inelastic molecular and atomic processes, the main process being Franck-Condon dissociation of H 2 molecules.

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“…For pellet fusion p would include neutron energy losses (and Q = Qn + Q+)-A set of coupled particle conservation equations must also be included. Table I gives experimental results from the MIT ALCATOR [14], the ORNL ORMAK [15], the Kurchatov T-10 [16], the Princeton PLT [17], the Fontenay-aux-Roses TFR [18], the LLL 2XII-B [19], the ORNL DCX-1 [20], and the FEC MIGMA [21]. The present status of plasma experiments is clearly far short of ignition feasibility, whether measured by direct comparison of the f value, i.e.…”

Section: + P Extmentioning

confidence: 99%

Interaction of neutrons at high energies

Lyubimov¹

1977

Sov. Phys. Usp.

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This paper presents some novel interpretations of fusion plasmas which may be of interest to both fission and fusion scientists and engineers. A new fusion ignition parameter (Tn e r E )i is proposed which is proportional to 0 2 B 4 and inversely proportional to the fusion power density (PFusion) °f a reacting plasma. Curves are given for many potential nuclear fusion fuels. The energy utilization factor in existing devices is defined as f = PFusion/PLoss = (Tn e TL)/(Tn e TE)i; in experimental plasmas, f has increased by about two orders of magnitude in the past decade and now exceeds 10" 4 (a "nearest" f* exceeds 10~3). The f factor is also analogous to its fission counterpart in the four-factor neutron multiplication factor k = f rj e p, where f is the neutron thermal utilization factor. Past, present, and future fusion experiments are discussed briefly in this context.

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Results of the first experiments on the T-10 Tokamak

Cited by 20 publications

References 2 publications

Low-Q MHD activity studies on TFR

Low-Q MHD activity studies on TFR

Radiation losses and global energy balance for Ohmically heated discharges in ASDEX

Interaction of neutrons at high energies

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