Conceptual design of a poloidal field coil system and operation scenario for an inductively operated day-long pulsed tokamak reactor
- 1. Tokyo Univ. (Japan). Dept. of Quantum Eng. and Syst. Sci.
- 2. National Institute for Fusion Science, 464-01 Nagoya (Japan)
- 3. Toshiba Research and Development Center, 210 Kawasaki (Japan)
Description
The conceptual design of a poloidal field coil system and operation scenario for an inductively operated day-long pulsed tokamak (IDLT) reactor are discussed. Much attention is paid to the start-up and shut-down phase, because a shorter dwell time is preferable in the pulsed reactor. A plasma current ramp-up time of 100s is achievable with a power supply of 1.4GW. Including the current ramp-down time and recharging periods, it is found that a dwell time of 5-10min is feasible for IDLT reactor operation. The average hysteresis loss of the central solenoid coil is about 5kW during the current ramp-up phase, and is acceptable for the superconducting coils. Plasma performance is analyzed with a 1.5-dimensional transport code, where a Bohm type transport model is employed. It is found that ignition can be initiated with an auxiliary heating power of 40MW with the H factor of approximately 2, and can be sustained for a helium recycling coefficient less than RHe=0.99. For IDLT reference operation with RHe=0.95 and peaking parameter CV=1.0, it is found that the helium accumulation fraction is 9.8%, the ratio of helium effective particle confinement time τ*p to energy confinement time τE is 7.8, and the bootstrap current fraction is 40%. During the shut-down phase, the decrease in plasma density is slower than the decrease in fusion power, and an auxiliary heating power of 20MW is required to avoid density-limit disruption. (orig.)
Additional details
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 29
- Journal Page Range
- p. 69-77.
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 3. international symposium on fusion nuclear technology (ISFNT-3).
- Dates
- 26 Jun - 1 Jul 1994.
- Place
- Los Angeles, CA (United States).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 27024557
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUXILIARY HEATING; CONFINEMENT; CONFINEMENT TIME; ENERGY LOSSES; HELIUM; HYSTERESIS; OPERATION; PERFORMANCE; POWER SUPPLIES; SOLENOIDS; SUPERCONDUCTING COILS; SUPERCONDUCTING MAGNETS; THERMONUCLEAR IGNITION; TOKAMAK DEVICES
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELECTRIC COILS; ELECTRICAL EQUIPMENT; ELECTROMAGNETS; ELECTRONIC EQUIPMENT; ELEMENTS; EQUIPMENT; HEATING; MAGNETS; NONMETALS; RARE GASES; SUPERCONDUCTING DEVICES; THERMONUCLEAR DEVICES