Fusion engineering design center
Creators
Description
The principal focus of the FEDC resources during 1986 was the CIT project. The baseline design established for the CIT included elements derived from the preconceptual design for the FEDC version of Ignitor. The Design Center provided the systems engineering and design integration of the CIT project and led the preparation of the cost estimate and back-up documentation. In cooperation with ORNL, the Design Center had lead responsibility for several major systems, including shielding, structure, ex-vessel remote maintenance, and vacuum pumping. Analytic support was provided in the areas of magnet structure, cooldown systems for the toroidal field and ohmic heating coils, and the poloidal field coil systems. In a collaboration with Japan, an analysis of the toroidal field coils was performed. Overall systems studies were carried out with the FEDC Tokamak Systems Code. Activities in support of the mirror fusion program were concluded with the final configuration and systems design of the MINIMARS program in mid-1986. The Design Center continued to lead the engineering activities for the International Tokamak Reactor (INTOR) program. Interest in this work increased because of the potential for an expanded international program, based on initiatives development in the US-USSR summit process. The Design Center also provides the primary point of interaction between the US and the teams working on the Next European Torus in Europe and the Japanese Fusion Engineering Reactor (FER). As part of a US-Japan exchange agreement, a staff member from the Design Center completed an assignment to work with the FER team in Japan
Additional details
Publishing Information
- Imprint Title
- Fusion Energy Division annual progress report period ending December 31, 1986
- Journal Page Range
- p. 275-316.
- Report number
- ORNL--6332
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19070421
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- COMPACT IGNITION TOKAMAK; COST; ICR HEATING; INTOR TOKAMAK; MAGNET COILS; MAINTENANCE; PINCH DEVICES; PLASMA CONFINEMENT; PROGRESS REPORT; RESEARCH PROGRAMS; SHIELDING; SPECIFICATIONS; SYSTEMS ANALYSIS; THERMONUCLEAR DEVICES; THERMONUCLEAR IGNITION; TIBER-X TOKAMAK
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONFINEMENT; ELECTRIC COILS; ELECTRICAL EQUIPMENT; EQUIPMENT; HEATING; HIGH-FREQUENCY HEATING; PLASMA HEATING; TOKAMAK DEVICES