Development of ITER Nonactivation Phase Operation Scenarios
- 1. International Thermonuclear Experimental Reactor (ITER), Cadarache Centre, 13108 Saint-Paul-lès-Durance (France)
Description
Full text: Nonactivation phase H/He operations in ITER will be important for commissioning of tokamak systems, such as diagnostics, heating and current drive (HCD) systems, coils and plasma control systems, and for validation of techniques necessary for establishing feasible operations. The assessment of feasible HCD schemes at various toroidal fields (2.65–5.3 T) has revealed that the previously applied assumptions need to be refined for the ITER nonactive phase H/He operations. A study on the ranges of plasma density and profile shape using the JINTRAC suite of codes has indicated that the hydrogen pellet fuelling system should be carefully utilized in He operation to optimize IC power absorption, neutral beam shine-through density limit and H-mode access. The EPED estimation of the edge pedestal parameters has been extended to various H operation conditions, and the combined EPED and SOLPS estimation has provided a good guidance for modelling the edge pedestal in H/He operations. The availability of ITER HCD schemes, ranges of achievable plasma density and profile shape, and estimation of the edge pedestal parameters for H/He plasmas have been combined with the previous modelling efforts on studying the H-mode access and flat-top duration within the coil system constraints. Feasible ITER nonactivation phase H/He operation scenarios have been developed by performing integrated time-dependent tokamak discharge simulations using CORSICA. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- 26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material
- Imprint Pagination
- 935 p.
- Journal Page Range
- p. 543
- Report number
- IAEA-CN--234
Conference
- Title
- 26. IAEA Fusion Energy Conference
- Acronym
- FEC 2016
- Dates
- 17-22 Oct 2016
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50009286
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMMISSIONING; CONTROL SYSTEMS; H-MODE PLASMA CONFINEMENT; ITER TOKAMAK; PLASMA DENSITY; SIMULATION
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONFINEMENT; MAGNETIC CONFINEMENT; PLASMA CONFINEMENT; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Notes
- Abstract only
- Secondary number(s)
- IAEA-CN--234-0495