Preliminary design of the CIT (Compact Ignition Tokamak) cryostat
For the Compact Ignition Tokamak (CIT) to achieve the performance goals set forth, the toroidal field (TF) and poloidal field (PF) coil systems must operate in a cryogenic temperature regime. The cryostat has been designed to provide and maintain this environment. The preliminary design activity is addressing the design issues and interfaces necessary to provide a cryogenic vessel that will maintain a maximum temperature differential of 8{degree}C between the outer vessel wall and the ambient test cell conditions; operate in a pressure range of +5 psig to {minus}2 psig; accommodate numerous penetrations, including cooling, diagnostic, and gravity support items; and maintain a maximum leak rate of gaseous nitrogen at 1 l/s at 1 atm. Conceptually, the cryostat consists of thermal insulation sandwiched between an inner primary stainless steel pressure vessel and a thin outer stainless steel wall. Design activities have concentrated on determining the size and shape of the primary vessel wall and selecting the best candidate thermal insulation materials for future irradiation testing. The following shapes of the upper and lower cryostat structure were analyzed: a standard ASME torispherical domed top and bottom; a nonstandard domed top and bottom; and a 2{degree} sloped conical top and bottom contour. Screening of candidate insulation materials was based on lowest thermal conductivity over the range of temperatures anticipated in the CIT environment; low material cost and apparent ease of assembly; and survivability of material in the CIT irradiation environment. This paper presents the configuration development of the cryostat used to maintain the cryogenic temperature environment for CIT. 3 refs., 3 figs., 3 tabs.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5550252
- Report Number(s):
- CONF-891007-85; ON: DE90002710
- Country of Publication:
- United States
- Language:
- English
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700204* -- Fusion Power Plant Technology-- Cooling Systems
CLOSED PLASMA DEVICES
COMPACT IGNITION TOKAMAK
CONTROL EQUIPMENT
CRYOSTATS
DESIGN
EQUIPMENT
MATERIALS
ORGANIC COMPOUNDS
ORGANIC POLYMERS
PETROCHEMICALS
PETROLEUM PRODUCTS
PHYSICAL PROPERTIES
PLASTICS
POLYAMIDES
POLYMERS
POLYURETHANES
SHIELDS
SYNTHETIC MATERIALS
THERMAL CONDUCTIVITY
THERMAL INSULATION
THERMAL SHIELDS
THERMODYNAMIC PROPERTIES
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
THERMOSTATS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS