Alpha Heating in ITER L-mode and H-mode Plasma
There are many uses of predictions of ITER plasma performance. One is assessing requirements of different plasma regimes. For instance, what current drive and control are needed for steady state. The heating, current drive, and torque systems planned for initial DT operation are negative ion neutral beam injection (NB), ion cyclotron resonance (IC), and electron cyclotron resonance (EC). Which combinations of heating are optimal. What are benefits of the torques, current drive, and fueling using NB. What are the shine-through power and optimum voltage for the NB? What are optimal locations and aiming of the EC launchers? Another application is nuclear licensing (e.g. System integrity, how many neutrons).
- Research Organization:
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Sponsoring Organization:
- USDOE Office of Science (SC)
- DOE Contract Number:
- DE-ACO2-09CH11466
- OSTI ID:
- 1028185
- Report Number(s):
- PPPL-4636; TRN: US1105417
- Resource Relation:
- Conference: EPS Strasbourg, France (June 2011)
- Country of Publication:
- United States
- Language:
- English
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