Plasma confinement in JET H mode plasmas with H, D, DT and T isotopes

Cordey, J.G.; Balet, B.; Bartlett, D.V.; Budny, R.; Christiansen, J.; Conway, G. D.; Eriksson, L.‐G.; Fishpool, G.; Gowers, C.; Haas, J.C.M. de; Harbour, P.J.; Horton, L. D.; Howman, A.; Jacquinot, J.; Kerner, W.; Lowry, C.; Monk, R.D.; Nielsen, P.; Righi, E.; Rimini, F.; Saibene, G.; Sartori, R.; Schunke, B.; Sips, A. C. C.; Smith, Roger; Stamp, M.; Start, D.F.H.; Thomsen, K.; Tubbing, B.J.D.; Hellermann, M. G. von

doi:10.1088/0029-5515/39/3/301

Cited by 99 publications

(84 citation statements)

References 10 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…In both cases of the circular and vertically elongated configurations, the upper data of β 0 are on a curve proportional to n 0.6 e0 . This is consistent with the gyro-Bohm model, where β 0 ∝ n 0.6 e0 [5][6][7][8][9]. There observed no clear difference between the two configurations in this figure. A clear difference is recognized in the Shafranov shift as shown in Fig.…”

Section: Resultssupporting

confidence: 91%

Assessment of Plasma Performance in a Magnetic Configuration with Reduced Poloidal Coils for a Helical DEMO Reactor FFHR-d1

Miyazawa

Goto

Sakamoto

et al. 2012

Plasma and Fusion Research

View full text Add to dashboard Cite

The performance of high-density plasmas heated by neutral beam (NB) injection in a vertically elongated configuration using four poloidal coils has been investigated in LHD and shown to be better than that in the normal configuration using six poloidal coils. Reduction of poloidal coils is favorable in designing an LHD-type helical reactor FFHR-d1, from both points of view of cost reduction and realization of large maintenance ports. In the experiment, no clear difference between the two configurations was recognized in the relation between the central density and the central pressure. Meanwhile, a factor C exp used in the direct profile extrapolation (DPE) method is smaller in the vertically elongated configuration, where C exp is proportional to the reactor size, R reactor , at a given reactor magnetic field, B reactor , i.e., R reactor ∝ C exp B reactor −4/3 . The difference in C exp between the two configurations is enhanced to > 10 % as the plasma beta increases. This might be due to the larger plasma volume and/or the mitigated Shafranov shift in the vertically elongated configuration.

show abstract

Section: Resultssupporting

confidence: 91%

Assessment of Plasma Performance in a Magnetic Configuration with Reduced Poloidal Coils for a Helical DEMO Reactor FFHR-d1

Miyazawa

Goto

Sakamoto

et al. 2012

Plasma and Fusion Research

View full text Add to dashboard Cite

show abstract

“…In particular, they have concluded that τ E th ∝ <A> 0.16±0.06 [14]. For comparison, the current ITER scaling (ITER98pby2) is that τ E th ∝ <A> 0.…”

Section: Isotope Effects In Confinement and Transportmentioning

confidence: 98%

“…JET has concentrated their confinement studies on H-mode plasmas both ELM free as well as with ELMs [14]. This is of particular relevance to ITER, since ELMy H-mode operation is the proposed baseline-operating scenario.…”

Section: Isotope Effects In Confinement and Transportmentioning

confidence: 99%

“…Theoretically, transport is usually believed to be governed by small-scale turbulent processes determined by local plasma physics parameters, which would imply gyro-Bohm scaling and a weak adverse scaling with mass, τ E th ∝ <A> -0.2 [14]. This scaling would have a favorable scaling with device size.…”

Section: Isotope Effects In Confinement and Transportmentioning

confidence: 99%

“…19 . To develop an understanding of the source for the weak isotope scaling, Cordey et al [14] studied the scaling of the pedestal compared to the core. Many transport models are sensitive to the edge conditions and the question here is the favorable isotope scaling associated with changes in the pedestal or the core.…”

Section: Isotope Effects In Confinement and Transportmentioning

confidence: 99%

See 2 more Smart Citations

Review of D-T Experiments Relevant to Burning Plasma Issues

Hawryluk¹

2001

View full text Add to dashboard Cite

Progress in the performance of tokamak devices has enabled not only the production of significant bursts of fusion energy from deuterium-tritium (D-T) plasmas in the Tokamak Fusion Test Reactor (TFTR) and the Joint European Torus (JET) but, more importantly, the initial study of the physics of burning magnetically confined plasmas. TFTR and JET, in conjunction with the worldwide fusion effort, have studied a broad range of topics including magnetohydrodynamic stability, transport, wave-particle interactions, the confinement of energetic particles, and plasma boundary interactions. D-T experiments differ in three principal ways from previous experiments: isotope effects associated with the use of deuterium-tritium fuel, the presence of fusion-generated alpha particles, and technology issues associated with tritium handling and increased activation. The effect of deuteriumtritium fuel and the presence of alpha particles is reviewed and placed in the perspective of the much larger worldwide database using deuterium fuel and theoretical understanding.Both devices have contributed substantially to addressing the scientific and technical issues associated with burning plasmas. However, future burning plasma experiments will operate with larger ratios of alpha heating power to auxiliary power and will be able to access additional alpha-particle physics issues. The scientific opportunities for extending our understanding of burning plasmas beyond that provided by current experiments is described.

show abstract

Energiewandlung — Methoden der Strom- und Wärmeerzeugung

Rebhan

2002

Energiehandbuch

View full text Add to dashboard Cite

Plasma confinement in JET H mode plasmas with H, D, DT and T isotopes

Cited by 99 publications

References 10 publications

Assessment of Plasma Performance in a Magnetic Configuration with Reduced Poloidal Coils for a Helical DEMO Reactor FFHR-d1

Assessment of Plasma Performance in a Magnetic Configuration with Reduced Poloidal Coils for a Helical DEMO Reactor FFHR-d1

Review of D-T Experiments Relevant to Burning Plasma Issues

Energiewandlung — Methoden der Strom- und Wärmeerzeugung

Contact Info

Product

Resources

About