Published April 2003 | Version v1
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Advanced fusion reactor

  • 1. National Inst. for Fusion Science, Toki, Gifu (Japan)

Description

The main subjects on fusion research are now on D-T fueled fusion, mainly due to its high fusion reaction rate. However, many issues are still remained on the wall loading by the 14 MeV neutrons. In the case of D-D fueled fusion, the neutron wall loading is still remained, though the technology related to tritium breeding is not needed. The p-6Li and p-11B fueled fusions are not estimated to be the next generation candidate until the innovated plasma confinement technologies come in useful to achieve the high performance plasma parameters. The fusion reactor of D-3He fuels has merits on the smaller neutron wall loading and tritium handling. However, there are difficulties on achieving the high temperature plasma more than 100 keV. Furthermore the high beta plasma is needed to decrease synchrotron radiation loss. In addition, the efficiency of the direct energy conversion from protons coming out from fusion reaction is one of the key parameters in keeping overall power balance. Therefore, open magnetic filed lines should surround the plasma column. In this paper, we outlined the design of the commercial base reactor (ARTEMIS) of 1 GW electric output power configured by D-3He fueled FRC (Field Reversed Configuration). The ARTEMIS needs 64 kg of 3He per a year. On the other hand, 1 million tons of 3He is estimated to be in the moon. The 3He of about 1023 kg are to exist in gaseous planets such as Jupiter and Saturn. (Y. Tanaka)

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Part of:
Theoretical study for ICRF sustained LHD type p-11B reactor

Additional details

Publishing Information

Imprint Title
Theoretical study for ICRF sustained LHD type p-"1"1B reactor
Imprint Pagination
40 p.
Journal Page Range
p. 7-14
Report number
NIFS-PROC--53

Conference

Title
Workshop on 'Theoretical study for ICRF sustained LHD type p-"1"1B reactor'
Dates
25 Jul 2002
Place
Toki, Gifu (Japan)

Optional Information

Notes
3 refs., 8 figs., 1 tab.