ITER helium ash accumulation

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6570796

Hogan, J T; Hillis, D L; Galambos, J; Uckan, N A ^[1]; Dippel, K H; Finken, K H ^[2]; Hulse, R A; Budny, R V ^[3]

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1. Oak Ridge National Lab., TN (USA)
2. Forschungszentrum Juelich GmbH (Germany, F.R.). Inst. fuer Plasmaphysik
3. Princeton Univ., NJ (USA). Plasma Physics Lab.

Many studies have shown the importance of the ratio {upsilon}{sub He}/{upsilon}{sub E} in determining the level of He ash accumulation in future reactor systems. Results of the first tokamak He removal experiments have been analysed, and a first estimate of the ratio {upsilon}{sub He}/{upsilon}{sub E} to be expected for future reactor systems has been made. The experiments were carried out for neutral beam heated plasmas in the TEXTOR tokamak, at KFA/Julich. Helium was injected both as a short puff and continuously, and subsequently extracted with the Advanced Limiter Test-II pump limiter. The rate at which the He density decays has been determined with absolutely calibrated charge exchange spectroscopy, and compared with theoretical models, using the Multiple Impurity Species Transport (MIST) code. An analysis of energy confinement has been made with PPPL TRANSP code, to distinguish beam from thermal confinement, especially for low density cases. The ALT-II pump limiter system is found to exhaust the He with maximum exhaust efficiency (8 pumps) of {approximately}8%. We find 1<{upsilon}{sub He}/{upsilon}{sub E}<3.3 for the database of cases analysed to date. Analysis with the ITER TETRA systems code shows that these values would be adequate to achieve the required He concentration with the present ITER divertor He extraction system.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6570796
• Report Number(s): CONF-901007-18; ON: DE91001487; TRN: 91-000096
• Resource Relation: Conference: 9. topical meeting on technology of fusion energy, Oak Brook, IL (USA), 7-11 Oct 1990
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
HELIUM ASH
BUILDUP
BEAM INJECTION HEATING
DIFFUSION
DIVERTORS
ITER TOKAMAK
PUMPED LIMITERS
CHARGED PARTICLES
CLOSED PLASMA DEVICES
HEATING
HELIUM IONS
IONS
LIMITERS
PLASMA HEATING
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
700201* - Fusion Power Plant Technology- Blanket Engineering
700101 - Fusion Energy- Plasma Research- Confinement
Heating
&amp; Production