Numerical analysis of 2D MHD equilibrium with non-inductive plasma current in tokamaks

Tani, K.; Azumi, M.; Devoto, R. S.

doi:10.1016/0021-9991(92)90146-p

Cited by 126 publications

(105 citation statements)

References 12 publications

Supporting

Mentioning

102

Contrasting

Unclassified

Order By: Relevance

“…Earlier we reported [4,5] results of powder metallurgy processed Nb3Sn(Ti) manufactured at an intermediate-scale industrial volumes, using a 7.5 cm OD billet with sufficient material to fabricate a 100 m length of 0.9 mm OD wire for small magnets which were tested up to 20 T. These results showed that a uniform wire (using Sn cores) could be fabricated for long lengths with short sample performance. A small magnet using 50 m of this wire was tested in background fields to 20 T and achieved short sample characteristics.…”

Section: B) Ternary Nb3sn Wire Developmentmentioning

confidence: 86%

“…(iii) The problem of c_effects on the bootstrap current (_), particularly any (positive or negative) c_-contribution to the necessaryseed current has been solved analytically [4] and applied to ITER parameters. First results indicate that depending on Z_/Zeff, there can be a small core region where j_ opposes the bulk plasma bootstrap current jb but overall .j_ contributes _< 10% to j_.…”

Section: Novel Uses Ofmentioning

confidence: 99%

See 1 more Smart Citation

Fusion development and technology

Montgomery¹

1992

View full text Add to dashboard Cite

Section: B) Ternary Nb3sn Wire Developmentmentioning

confidence: 86%

Section: Novel Uses Ofmentioning

confidence: 99%

Fusion development and technology

Montgomery¹

1992

View full text Add to dashboard Cite

“…The RF generator has maximum output power 400 kW at a maximum pulse length 1.5 s. The poloidal field coils (P) shown in Fig. 1 provide the different requirements of magnetic flux linkage: In order to assess the performance of COMPASS-D with the planned NBI and LH systems a number of combined simulations of codes ACCOME (Analyzer for Current drive COnsistent with MHD Equilibrium) [1] and ASTRA (Automated System for TRansport Analysis) [2] were carried out. The simulations proceed in a sequence of iterations between the two codes in order to reach a consistent state between power deposition profiles from ACCOME needed by ASTRA, and temperature profiles from ASTRA needed by ACCOME.…”

Section: Device and Simulation Codesmentioning

confidence: 99%

“…The simulations proceed in a sequence of iterations between the two codes in order to reach a consistent state between power deposition profiles from ACCOME needed by ASTRA, and temperature profiles from ASTRA needed by ACCOME. NBI simulations have been performed using the codes FAFNER [3], [4], NBEAMS [5] and ACCOME [1].…”

Section: Device and Simulation Codesmentioning

confidence: 99%

COMPASS-D magnetic equilibria with lh and NBI current drive

et al. 2006

View full text Add to dashboard Cite

Plasma equilibria are investigated numerically, using the ACCOME and ASTRA codes, on the COMPASS-D tokamak (R0 = 0.56 m, a = 0.17 m, BT = 1.2 T, Ip = 200 kA, k = 1.7, δ x = 0.4) for the planned Neutral Beam Injection (NBI) and Low Hybrid Current Drive (LHCD) systems. The LH system provides PLH = 0.4 MW at n = 2.1 and f LH = 1.3 GHz. The NBI system has two 40 keV deuterium beams in co-or counterdirections with a total power of 0.6 MW. The COMPASS-D tokamak can typically operate in two configurations -single null divertor (SND) and single null divertor with a higher triangularity (SNT). Higher triangularity provides access to higher confinement and improved stability, and leads to larger n up-shifts for better slow LH wave absorption.We investigate the range of densities n = 2 ÷ 6 × 10 19 m −3 . Both the LH and NB driven currents decrease with density. The magnetic shear reverses with off-axis beam incidence. In the given plasma parameter range, typically up to 60 kA of bootstrap current is driven and with NB co-injection up to 80 kA of NB current is driven. LHCD is weak at f = 1.3 GHz and BT = 1.2 T, but at n = 3 × 10 19 m −3 the LH driven current is about 40 kA, so that the required plasma current of 200 kA is supported almost non-inductively.PACS : 52.55.-s

show abstract

“…A number of combined ACCOME [2] and ASTRA [3] simulations were carried out in order to assess the performance of COMPASS with the planned neutral beam (NB and lower hybrid (LH) systems (for more details see [4]). …”

Section: Plasma Performancementioning

confidence: 99%

Reinstallation of the COMPASS-D tokamak in IPP ASCR

et al. 2006

View full text Add to dashboard Cite

The COMPASS-D tokamak, originally operated by UKAEA at Culham, UK, will be reinstalled at the Institute of Plasma Physics (IPP) AS CR. The COMPASS device was designed as a flexible tokamak in the 1980s mainly to explore the MHD physics. Its operation (with D-shaped vessel) began at the Culham Laboratory of the Association EURATOM/ UKAEA in 1992.The COMPASS-D tokamak will have the following unique features after putting in operation on IPP Prague. It will be the smallest tokamak with a clear H-mode and ITERrelevant geometry. ITER-relevant plasma conditions will be achieved by installation of two neutral beam injection systems (2 × 300 kW), enabling co-and counter-injections. Redeployment of the existing LH system (400 kW) is also envisaged. A comprehensive set of diagnostics focused mainly on the edge plasma will be installed.The scientific programme proposed for the COMPASS-D tokamak installed in IPP Prague will benefit from these unique features of COMPASS-D and consist of two main scientific projects, both highly relevant to ITER -Edge plasma physics (H-mode studies) and Wave-plasma interaction studies.The COMPASS-D tokamak will offer an important research potential as a small, flexible and low-cost facility with ITER-relevant geometry.

show abstract

Numerical analysis of 2D MHD equilibrium with non-inductive plasma current in tokamaks

Cited by 126 publications

References 12 publications

Fusion development and technology

Fusion development and technology

COMPASS-D magnetic equilibria with lh and NBI current drive

Reinstallation of the COMPASS-D tokamak in IPP ASCR

Contact Info

Product

Resources

About