Exploration of one-dimensional plasma current density profile for K-DEMO steady-state operation
- 1. Seoul National University, Seoul 151-742 (Korea, Republic of)
- 2. National Fusion Research Institute, Daejeon (Korea, Republic of)
Description
Highlights: • One-dimensional current density and its optimization for the K-DEMO are explored. • Plasma current density profile is calculated with an integrated simulation code. • The impact of self and external heating profiles is considered self-consistently. • Current density is identified as a reference profile by minimizing heating power. - Abstract: Concept study for Korean demonstration fusion reactor (K-DEMO) is in progress, and basic design parameters are proposed by targeting high magnetic field operation with ITER-sized machine. High magnetic field operation is a favorable approach to enlarge relative plasma performance without increasing normalized beta or plasma current. Exploration of one-dimensional current density profile and its optimization process for the K-DEMO steady-state operation are reported in this paper. Numerical analysis is conducted with an integrated plasma simulation code package incorporating a transport code with equilibrium and current drive modules. Operation regimes are addressed with zero-dimensional system analysis. One-dimensional plasma current density profile is calculated based on equilibrium, bootstrap current analysis, and thermal transport analysis. The impact of self and external heating profiles on those parameters is considered self-consistently, where thermal power balance and 100% non-inductive current drive are the main constraints during the whole exploration procedure. Current and pressure profiles are identified as a reference steady-state profile by minimizing the external heating power with desired fusion power.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2016.02.011Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2016.02.011;
- PII
- S0920-3796(16)30090-4;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 109-111
- Journal Issue
- Part A
- Journal Page Range
- p. 724-728
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 12. international symposium on fusion nuclear technology
- Acronym
- ISFNT-12
- Dates
- 14-18 Sep 2015
- Place
- Jeju Island (Korea, Republic of)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48067812
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOOTSTRAP CURRENT; CURRENT DENSITY; DEMONSTRATION PLANTS; HEATING; ITER TOKAMAK; LIMITING VALUES; MAGNETIC FIELDS; NON-INDUCTIVE CURRENT DRIVE; NUMERICAL ANALYSIS; ONE-DIMENSIONAL CALCULATIONS; OPTIMIZATION; PLASMA SIMULATION; STEADY-STATE CONDITIONS; SYSTEMS ANALYSIS; TRANSPORT THEORY
- Descriptors DEC
- CLOSED PLASMA DEVICES; CURRENTS; ELECTRIC CURRENTS; MATHEMATICS; SIMULATION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.