Ignition Experiment in a Single-Turn-Coil Tokamak

Carrera, R.; Gully, J.H.; Hertel, Nolan E.; Hopf, James E.; Hsieh, Kuo-Ta; Montalvo, E.; Ordonez, C. A.; Parish, T.A.; Rosenbluth, M. N.; Walls, W.A.; Weldon, W.F.; Werst, M.D.; Woodson, H.H.

doi:10.13182/fst89-a39734

Cited by 4 publications

(1 citation statement)

References 2 publications

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“…Plasma coupling is, then, very strong so that the energy requirements for current induction are reduced and plasma control is facilitated. Because of the simplicity and compactness of the device and because of the new magnet and power supply tokamak technologies to be employed, initial estimates suggest a relatively low cost for the construction of this experiment [28].…”

Section: Ignitex Devicementioning

confidence: 99%

Fusion ignition experiment

Carrera¹,

Montalvo²

1990

Nucl. Fusion

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A fusion ignition experiment (IGNITEX) is described, the original concept for which was proposed by Rosenbluth, Weldon and Woodson. In this concept, a single-turn-coil tokamak device produces a self-sustained fusion reaction of the type T (d, n) α. The basic idea is to employ a very high magnetic field and a very high plasma current to heat the plasma ohmically to thermonuclear temperatures and then to produce a stable ignited plasma. The experiment will permit the scientific study of a new regime of physics: alpha heated ignited plasmas.

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Section: Ignitex Devicementioning

confidence: 99%

Fusion ignition experiment

Carrera¹,

Montalvo²

1990

Nucl. Fusion

Self Cite

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Impurity release, disruption effects, and thermomechanical stress analysis of the first wall system for the IGNITEX experiment

Ordonez

Carrera

Edmonds

et al.

IEEE Thirteenth Symposium on Fusion Engineering

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A first wall design and analysis for the proposed IGNI-TEX ignition experiment is presented. The design of the first wall system emphasizes the following aspects: 1) plasma cleanness; 2) simplicity of design; 3) minimum complexity of remote maintenance systems and operation; 4) minimum cost. A limiterless first wall is considered which consists of an amorphous carbon film applied to a beryllium substrate. The beryllium is applied to the vacuum vessel by plasma jet spraying. Based on the limiterless geometry, impurity release during operation is estimated. Discharges are simulated with the PROCTR one dimensional plasma transport code. Sputterin and helium ash recycling are considered as main mechanisms of; impurity release from the first wall. A new sputtering yield calculation for carbon surfaces is presented based on Monte Carlo studies (TRIM two dimensional ion implantation code). Disruption effects are simulated with the code DISRUP which accounts for vaporshielding effects. Evaluations of wall erosion under various disruptive scenarios are presented. Thermomechanical stresses are calculated using the finite elements program ABAQUS. First wall system preconditioning between experimental pulses is outlined.

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