Published October 16, 2018 | Version v1
Report

Modelling Third Field Operation in the ITER Prefusion Power Operation Phase

  • 1. International Thermonuclear Experimental Reactor (ITER), Cadarache Centre, 13108 St. Paul lez Durance (France)

Description

Full text: The ITER low activation phase consists of H and He plasmas, split into prefusion power operation phases 1 and 2 (PFPO-1 and PFPO-2). The PFPO-1 phase will include 20 MW of electron cyclotron resonance heating (ECRH) and possibly 10 MW of ion cyclotron radio frequency heating (ICRH), while the PFPO-2 phase will include the full heating and current drive (H&CD) capabilities, i.e., 73MWof H&CD power. The L-H power threshold displays a density optimum for ITER q95 = 3 operation at n/nG ∼ 0.4 , where nG is the Greenwald density. At half field for n/nG ∼ 0.4 in PFPO-1, H-mode access is predicted to be unlikely in PFPO-1 in H and marginal in He. Accessing H-mode allows the determination of the heating power required to operate ITER in H-mode and to commission/demonstrate ELM control schemes, both of which are key to the research plan. Hence, operating 5 MA/1.8 T (q95 = 3) plasmas is foreseen, since it makes the H-mode access more likely in PFPO-1. Scenarios have been developed for both PFPO-1 and PFPO-2 phases. H-mode scenarios at 1.8 T and low density are developed according to the limited power installed in PFPO-1, providing the density upper limit, and to the fact that low density and dominant ECRH can lead to low edge ion power flow preventing H-mode access. Hence it is important to qualify which key elements can be addressed in such plasmas to determine whether the required resources to implement the 1.8 T research programme are worthwhile. Integrated simulations of ITER 5 MA/1.8 T plasmas have been carried out with various 1.5D transport integrated modelling suites of codes by the ITPA topical group on integrated operation scenarios (ITPA-IOS) in collaboration with the IO and with support from the ITPA Transport and Confinement and Energetic Particles groups. The present contribution reports the results of self-consistent transport and H&CD analyses to assess the efficiency of EC and IC heating in 5 MA/1.8 T plasmas in L and H-modes. With a view to study H-modes at 1.8 T in PFPO-2, the possibility to heat these plasmas with NBI has been assessed as well. These issues are assessed by the application of a range of integrated modelling suites, used in association with either simplified H&CD models or more sophisticated codes for ECRH, ICRH and NBI modelling. (author)

Part of:
27th IAEA Fusion Energy Conference. Programme and Book of Abstracts

Additional details

Publishing Information

Imprint Title
27th IAEA Fusion Energy Conference. Programme and Book of Abstracts
Imprint Pagination
844 p.
Journal Page Range
p. 430-431
Report number
IAEA-CN--258

Conference

Title
27. IAEA Fusion Energy Conference
Acronym
FEC 2018
Dates
22-27 Oct 2018
Place
Ahmedabad (India)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
50055489
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ECR HEATING; EDGE LOCALIZED MODES; ELECTRON CYCLOTRON-RESONANCE; H-MODE PLASMA CONFINEMENT; ICR HEATING; ITER TOKAMAK; SIMULATION
Descriptors DEC
CLOSED PLASMA DEVICES; CONFINEMENT; CYCLOTRON RESONANCE; HEATING; HIGH-FREQUENCY HEATING; INSTABILITY; MAGNETIC CONFINEMENT; PLASMA CONFINEMENT; PLASMA HEATING; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; RESONANCE; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Secondary number(s)
IAEA-CN--258-253