Published February 2006 | Version v1
Journal article

Concept of core and divertor plasma for fusion DEMO plant at JAERI

  • 1. Japan Atomic Energy Research Institute, Naka, Ibaraki 311-0193 (Japan)
  • 2. AITEL Corp., Shinsugita, Isogo, Yokohama 235-8523 (Japan)
  • 3. Total Support Systems Corp., Tokai, Naka, Ibaraki 319-1116 (Japan)

Description

Fusion DEMO plant design at JAERI directs toward compactness and economy of the reactor with a fusion output at 3 GW level. The smaller size of the center solenoid (CS) has a large impact on reducing the reactor size and weight. Three candidates for CS, namely '-less', 'slim' and 'full' CS, are considered according to the role of CS coil that is plasma ramp up and plasma shaping. From points of views of technical feasibility, obtained triangularity (δ x) and weight of the reactor, the slim-CS is selected as the candidate for DEMO at JAERI. For slim-CS, high δ x (≥0.43), which is enough to suppress giant ELMs, is obtained, and highly radiative outer divertor is required in steady state power handling. The consistent equilibrium was found to satisfy the divertor requirements and radial build. During the plasma current ramp up phase, the acceleration voltage of neutral beam injection (NBI) has to be changed more than two times. In order to inject sufficient power during the low-energy beam injection, the present technology must be replaced by a new constant-current, variable-voltage technology

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2005.09.074;
PII
S0920-3796(05)00657-5;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
81
Journal Issue
8-14
Journal Page Range
p. 1277-1284
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
7. international symposium on fusion nuclear technology
Acronym
ISFNT-7
Dates
22-27 May 2005
Place
Tokyo (Japan)

Optional Information

Copyright
Copyright (c) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.