Compact Ignition Tokamak conventional facilities optimization
Creators
- 1. Idaho National Engineering Lab., EG and G Idaho, Inc., P.O. Box 1625, Idaho Falls, ID (USA)
Description
A high-field ignition machine with liquid-nitrogen-cooled copper coils, designated the Compact Ignition Tokamak (CIT), is proposed for the next phase of the United States magnetically confined fusion program. A team of national laboratory, university, and industrial participants completed the conceptual design for the CIT machine, support systems and conventional facilities. Following conceptual design, optimization studies were conducted with the goal of improving machine performance, support systems design, and conventional facilities configuration. This paper deals primarily with the conceptual design configuration of the CIT conventional facilities, the changes that evolved during optimization studies, and the revised changes resulting from functional and operational requirements (F and ORs). The CIT conventional facilities conceptual design is based on two premises: (1) satisfaction of the F and ORs developed in the CIT building and utilities requirements document, and (2) the assumption that the CIT project will be sited at the Princeton Plasma Physics Laboratory (PPPL) in order that maximum utilization can be made of existing Tokamak Fusion Test Reactor (TFTR) buildings and utilities. The optimization studies required reevaluation of the F and ORs and a second look at TFTR buildings and utilities. Some of the high-cost-impact optimization studies are discussed, including the evaluation criteria for a change from the conceptual design baseline configuration. The revised conventional facilities configuration are described and the estimated cost impact is summarized
Additional details
Publishing Information
- Publisher
- IEEE Service Center.
- Imprint Place
- Piscataway, NJ (USA)
- Imprint Title
- Proceedings of the 12th symposium on fusion engineering
- Journal Page Range
- p. 1325-1328.
Conference
- Title
- 12. symposium on fusion engineering.
- Dates
- 12-16 Oct 1987.
- Place
- Monterey, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19097221
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPACT IGNITION TOKAMAK; COOLANTS; COPPER; MAGNET COILS; NITROGEN; OPTIMIZATION; PLASMA CONFINEMENT; REACTOR COOLING SYSTEMS; SPECIFICATIONS; THERMONUCLEAR IGNITION
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONFINEMENT; COOLING SYSTEMS; ELECTRIC COILS; ELECTRICAL EQUIPMENT; ELEMENTS; EQUIPMENT; METALS; NONMETALS; REACTOR COMPONENTS; THERMONUCLEAR DEVICES; TOKAMAK DEVICES; TRANSITION ELEMENTS