| Autor: |
Vedeneev, A. I., Abramov, I. A., Lebedev, S. E., Kazakovsky, N. T., Pimanikhin, S. A., Saksagansky, G. L., Sten’gach, A. V., Shirnin, P. V., Viniar, I. V. |
| Zdroj: |
Fusion Science and Technology; August 2005, Vol. 48 Issue: 1 p43-46, 4p |
| Abstrakt: |
First experimental results of a tritium pellet injector steady-state operation is presented. The tritium injector TPI-1 was developed at the PELIN Laboratory and put in operation in Russian Federal Nuclear Center. It is a part of an experimental closed circuit for simulation of ITER fuel cycle. Results of several continuous extrusions of solid rod made of various hydrogen isotopes are presented. Transverse dimensions of an extruded ice rod with rectangular cross-section were ~ 3 × 4·mm. The greatest extrusion velocity came to 15 mm/s for hydrogen and 9 mm/s for D-T mixture; tritium content in fuel mixture did not exceed 11%; pellet velocity ran up to 500 m/s at repetitive mode. An optimal mode of D-T ice extrusion was determined. |
| Databáze: |
Supplemental Index |
| Externí odkaz: |
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