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Conceptual design of fusion experimental reactor (FER/ITER). Ion cyclotron wave system

Technical Report:

Abstract

Conceptual design of the Ion Cyclotron Wave (ICW) system for FER and Japanese contribution to the conceptual design of the ITER ICW system are presented. A frequency range of the FER ICW system is 50-85 MHz, which covers 2{omega}{sub cT} heating, current drive by transit time magnetic pumping (TTMP) and 2{omega}{sub cD} heating. Physics analyses show that the FER and the ITER ICW systems are suitable for the central ion heating and the burn control. The launching systems of the FER ICW system and the ITER high frequency ICW system are characterized by in-port plug and ridged-waveguide-fed 5x4 phased loop array. Merits of those systems are (1) a ceramic support is not necessary inside the cryostat and (2) remote maintenance of the front end part of the launcher is relatively easy. Overall structure of the launching system is consistent with radiation shielding, cooling, pumping, tritium safety and remote maintenance. The launcher has injection capability of 20 MW in the frequency range of 50-85 MHz with the separatrix-antenna distance of 15 cm and steep scrape-off density profile of H-mode. The shape of the ridged waveguide is optimized to provide desired frequency range and power handling capability with a finite element method.  More>>
Authors:
Kimura, Haruyuki; Saigusa, Mikio; [1]  Saitoh, Yasushi [2] 
  1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
  2. and others
Publication Date:
Jun 01, 1991
Product Type:
Technical Report
Report Number:
JAERI-M-91-094
Reference Number:
SCA: 700460; PA: JPN-91:011140; SN: 92000630556
Resource Relation:
Other Information: PBD: Jun 1991
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ITER TOKAMAK; ION CYCLOTRON-RESONANCE; JXFR TOKAMAK; ICR HEATING; TRANSIT-TIME MAGNETIC PUMPING; NON-INDUCTIVE CURRENT DRIVE; WAVEGUIDES; 700460; HEATING AND FUELING SYSTEMS; FUELS
OSTI ID:
10108989
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
English
Other Identifying Numbers:
Other: ON: DE92750949; TRN: JP9111140
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
99 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Kimura, Haruyuki, Saigusa, Mikio, and Saitoh, Yasushi. Conceptual design of fusion experimental reactor (FER/ITER). Ion cyclotron wave system. Japan: N. p., 1991. Web.
Kimura, Haruyuki, Saigusa, Mikio, & Saitoh, Yasushi. Conceptual design of fusion experimental reactor (FER/ITER). Ion cyclotron wave system. Japan.
Kimura, Haruyuki, Saigusa, Mikio, and Saitoh, Yasushi. 1991. "Conceptual design of fusion experimental reactor (FER/ITER). Ion cyclotron wave system." Japan.
@misc{etde_10108989,
title = {Conceptual design of fusion experimental reactor (FER/ITER). Ion cyclotron wave system}
author = {Kimura, Haruyuki, Saigusa, Mikio, and Saitoh, Yasushi}
abstractNote = {Conceptual design of the Ion Cyclotron Wave (ICW) system for FER and Japanese contribution to the conceptual design of the ITER ICW system are presented. A frequency range of the FER ICW system is 50-85 MHz, which covers 2{omega}{sub cT} heating, current drive by transit time magnetic pumping (TTMP) and 2{omega}{sub cD} heating. Physics analyses show that the FER and the ITER ICW systems are suitable for the central ion heating and the burn control. The launching systems of the FER ICW system and the ITER high frequency ICW system are characterized by in-port plug and ridged-waveguide-fed 5x4 phased loop array. Merits of those systems are (1) a ceramic support is not necessary inside the cryostat and (2) remote maintenance of the front end part of the launcher is relatively easy. Overall structure of the launching system is consistent with radiation shielding, cooling, pumping, tritium safety and remote maintenance. The launcher has injection capability of 20 MW in the frequency range of 50-85 MHz with the separatrix-antenna distance of 15 cm and steep scrape-off density profile of H-mode. The shape of the ridged waveguide is optimized to provide desired frequency range and power handling capability with a finite element method. Matching between the current strap and the ridged waveguide is satisfactorily good. Thermal analysis of the Faraday shield shows that high electric conductivity low Z material such as beryllium should be chosen for a protection tile of the Faraday shield. Thick Faraday shield is necessary to tolerate electromagnetic force during disruptions. R and D needs for the ITER/FER ICW systems are identified and gain from JT-60/60U ICRF experiments and operations are indicated in connection with them. (author).}
place = {Japan}
year = {1991}
month = {Jun}
}