PERFORMANCE, SENSITIVITY AND OPTIMIZATION STUDIES FOR THE ITER OUTLINE DESIGN

摘要

Design basis, performance estimates and sensitivity studies for the ITER Outline Design are presented. Parameters of the Outline Design derive from requirements of the primary ITER mission objective of ignition and extended burn in DT plasmas, from present understanding of expected plasma performance and from performance of superconducting magnet and nuclear shielding systems. Major departures from the ITER CDA design: lower plasma eleongation κ_(95) = 1.55, a single-null divertor and constant tension toroidal field (TF) magnet shape follow from considerations of optimal use of in-TF volume and provision of reliable vertical control. Design variants with higher elongation (up to κ_(95) = 1.7) fail to offer appreciable costperformance improvement. Design variations with fewer coils (20 rather than 24) allow better access to neutral beam injection current drive and in-vessel component maintenance, but entail either increased TF coil size or loss of plasma performance and vertical control reliability.