Benchmarking of the NBI block in ASTRA code versus the OFMC calculations
Creators
- 1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
Description
The description of the Neutral Beam Injection block in the 1.5D ASTRA code is presented including the neutral beam absorption, first orbit analysis and fast ion slowing down. Benchmarking in the ASTRA code is carried out using the OFMC calculations for the JT60-U experimental parameters. The benchmarking reveals that the NBI solver of the ASTRA code provides satisfactory accuracy of the absorbed power and generated current calculations. Taking account of ripple losses and the multistep atomic processes for the high energy NBI enables calculation of both the transversal NBI in the rippled field and the tangential negative beam injection in the JT60-U experiments. The fast and self-consistent treatment of all plasma parameters in a MHD equilibrium makes the ASTRA code extremely convenient for the experimental data analysis and plasma transport simulations in the JT60-U experiments. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
28052091.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 19 p.
- Report number
- JAERI-Data/Code--97-014
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 28052091
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- A CODES; BEAM INJECTION HEATING; CHARGED-PARTICLE TRANSPORT; COMPUTERIZED SIMULATION; FOKKER-PLANCK EQUATION; JT-60U TOKAMAK; NEUTRAL ATOM BEAM INJECTION; O CODES; PLASMA; TRAPPING
- Descriptors DEC
- BEAM INJECTION; CLOSED PLASMA DEVICES; COMPUTER CODES; DIFFERENTIAL EQUATIONS; EQUATIONS; HEATING; PARTIAL DIFFERENTIAL EQUATIONS; PLASMA HEATING; RADIATION TRANSPORT; SIMULATION; THERMONUCLEAR DEVICES; TOKAMAK DEVICES