The ARIES-RS tokamak is a conceptual, D-T-burning 1000 MWe power plant
. As with earlier ARIES design studies, the final design of ARIES-RS w
as obtained in a self-consistent manner using the best available physi
cs and engineering models. Detailed analyses of individual systems tog
ether with system interfaces and interactions were incorporated into t
he ARIES systems code in order to assure self-consistency and to optim
ize towards the lowest cost system. The ARIES-RS design operates with
a reversed-shear plasma and employs a moderate aspect ratio (A = 4.0).
The plasma current is relatively low (I-p = 11.32 MA) and bootstrap c
urrent fraction is high (f(BC) = 0.88). Consequently, the auxiliary po
wer required for RF current drive is relatively low(similar to 80 MW).
At the same time, the average toroidal beta is high (beta = 5%), prov
iding power densities near practical engineering limits (the peak neut
ron wall loading is 5.7 MW m(-2)). The toroidal-field (TF) coil system
is designed with relatively 'conventional' materials (Nb3Sn and NbTi
conductor with 316SS structures), and is operated at a design limit of
similar to 16 T at the coil in order to optimize the design point. Th
e ARIES-RS design uses a self-cooled lithium blanket with vanadium all
oy as the structural material. The V-alloy has low activation, low aft
erheat, high temperature capability and can handle high heat flux. A s
elf-cooled liquid lithium blanket is simple, and with the development
of an insulating coating, has low operating pressure. Also, this blank
et gives excellent neutronics performance. Detailed analysis has been
performed to minimize the cost and maximize the performance of the bla
nket and shield. One of the distinctive features of this design is the
integration of the first wall, blanket, parts of the shield, divertor
and stability shells into an integral unit within each sector, The ma
intenance scheme consists of horizontal removal of entire sectors. Pri
or to the initiation of the ARIES-RS study, a set of top-level require
ments and goals for fusion demonstration and commercial power plants w
as evolved in collaboration with representatives from US electric util
ities and from industry. The degree to which ARIES-RS reached these re
quirements and goals and the necessary trade-offs are described and th
e high-leverage areas and key R&D items are presented. (C) 1997 Elsevi
er Science S.A.