Long pulse neutral beam system for the Tokamak Physics Experiment

Grisham, L.; Bowen, O.N.; Dahlgren, F.; Kamperschroer, J.; Newman, R.; O'Connor, T.; Ramakrishnan, S.; Rossi, G.; Stevenson, T. N.; Halle, A. von; Wright, Kathryn

doi:10.1016/0920-3796(94)00209-p

Cited by 7 publications

(7 citation statements)

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“…The TSC [33] and PEST-II [34] codes are used in these calculations, for the baseline case producing W L = 1 MW m −2 , at a density n e = 0.69 × 10 20 m −3 and E NB = 110 kV D 0 . TFTR-type positive ion beam system, upgraded to steady state operation [35], is assumed.…”

Section: Estimates Of Steady State Conditions In Ctfmentioning

confidence: 99%

A component test facility based on the spherical tokamak

Peng

Fogarty

Burgess

et al. 2005

Plasma Phys. Control. Fusion

135

124

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Recent experiments (Synakowski et al 2004 Nucl. Fusion 43 1648, Lloyd et al 2004. Fusion 46 B477) on the Spherical Tokamak (or Spherical Torus, ST) (Peng 2000 Phys. Plasmas 7 1681) have discovered robust plasma conditions, easing shaping, stability limits, energy confinement, self-driven current and sustainment. This progress has encouraged an update of the plasma conditions and engineering of a Component Test Facility (CTF), (Cheng 1998 Fusion Eng. Des. 38 219) which is a very valuable step in the development of practical fusion energy. The testing conditions in a CTF are characterized by high fusion neutron fluxes n ≈ 8.8 × 10 13 n s −1 cm −2 ('wall loading' W L ≈ 2 MW m −2 ), over size-scale >10 5 cm 2 and depth-scale >50 cm, delivering >3 accumulated displacement per atom per year ('neutron fluence' > 0.3 MW yr −1 m −2 ) (Abdou et al 1999 Fusion Technol. 29 1). Such conditions are estimated to be achievable in a CTF with R 0 = 1.2 m, A = 1.5, elongation ∼3, I p ∼ 12 MA, B T ∼ 2.5 T, producing a driven fusion burn using 47 MW of combined neutral beam and RF heating power. A design concept that allows straight-line access via remote handling to all activated fusion core components is developed and presented. The ST CTF will test the lifetime of single-turn, copper alloy centre leg for the toroidal field coil without an induction solenoid and neutron shielding and require physics data on solenoid-free plasma current initiation, ramp-up to and sustainment at multiple megaampere

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Section: Estimates Of Steady State Conditions In Ctfmentioning

confidence: 99%

A component test facility based on the spherical tokamak

Peng

Fogarty

Burgess

et al. 2005

Plasma Phys. Control. Fusion

135

124

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“…Princeton studies have long determined the needed modifications to the TFTR neutral beams and concluded that systems could be capable of reaching 1000 s pulses with a high degree of confidence. 34 Physics challenges include demonstration of performance at full plasma parameters, T e in particular. Scaling based on existing achievements would generate 0.3 MW/m 2 of neutron flux.…”

Section: Fusion-relevant Irradiation Sourcesmentioning

confidence: 99%

Fusion Nuclear Science Pathways Assessment

Kessel¹

2012

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This paper reviews US R&D requirements for magnets to be used in a post-ITER fusion machine that would have a nuclear mission. The state of the art of magnets is presented, followed by potential magnet options in the near (< 10 years) and middle term (> 10 years), followed by a description of the different components and system integration issues. The characteristics of an R&D program for investigate these issues is described, followed by a description of the present US facilities.

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“…The relatively moderate E NB determined in Section 5 suggests that present-day positive-ion (35) and negative-ion (46) (47) NBI techniques need to be extended to steady state operations. However, the engineering science knowledge base for the water-cooled, single-turn, normal conducting center leg of the TF coil is needed and uniquely important to CTF.…”

Section: Engineering Science Basementioning

confidence: 99%

“…The modest plasma density in this case also allowed 〈T i 〉/〈T e 〉 > 2, leading to an apparent enhancement of H 98 to ≥ 1.5 without changing H 98e and H 98i . The required E NB of ≤ 160 kV will permit the use of the TFTR-type positive-ion NBI system (35) . The modest density further leads to a substantial level of beam-plasma fusion fraction in the range of 30-40%.…”

Section: Choices Of Ctf Parametersmentioning

confidence: 99%

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Spherical Tokamak Plasma Science and Fusion Energy Component Testing

et al. 2005

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＊＊＊＊＊ Non-memberRecent progress (1) in plasma science of the Spherical Tokamak (or Spherical Torus, ST) (2) has indicated relatively robust plasma conditions in a broad number of topical area including strong shaping, stability limits, energy confinement, self-driven current, and sustainment. This progress has enabled an extensive update of the plasma science and fusion engineering conditions of a Component Test Facility (CTF), which is potentially a necessary step in the development of practical fusion energy. The chamber systems testing conditions in a CTF are characterized by high fusion neutron fluxes Γ n > 4.4×10 13 n/s/cm 2 , over sizescale > 10 5 cm 2 and depth-scale > 50 cm, delivering > 3 accumulated displacement per atom (dpa) per year (4) . Such chamber conditions are calculated to be achievable in a CTF with R 0 = 1.2 m, A = 1.5, elongation ~ 3, I p ~ 9 MA, B T ~ 2.5 T, producing a driven fusion burn using 36 MW of combined neutral beam and RF power. The ST CTF will test the life time of single-turn, copper alloy center leg for the toroidal field coil without an induction solenoid and neutron shielding, and require physics data on solenoid-free plasma current initiation, ramp-up, and sustainment to multiple MA level. A new systems code that combines the key required plasma and engineering science conditions of CTF has been prepared and utilized as part of this study. The results show high potential for a family of relatively low cost CTF devices to suit a range of fusion engineering science test missions.

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Long pulse neutral beam system for the Tokamak Physics Experiment

Cited by 7 publications

References 1 publication

A component test facility based on the spherical tokamak

A component test facility based on the spherical tokamak

Fusion Nuclear Science Pathways Assessment

Spherical Tokamak Plasma Science and Fusion Energy Component Testing

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