Published May 3, 2018 | Version v1
Report

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)

Part of:
26. IAEA Fusion Energy Conference. Programme, Abstracts and Conference Material

Additional details

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