TPX heating and cooling system

Conference · Sun Dec 31 04:00:00 EST 1995

OSTI ID:465014

Kungl, D J; Knutson, D S ^[1]; Costello, J; Stoenescu, S; Yemin, L ^[2]

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1. Princeton Plasma Physics Lab., NJ (United States)
2. Raytheon Engineers and Constructors Inc., Princeton, NJ (United States)

TPX, while having primarily super-conducting coils that do not require water cooling, still has very significant water cooling requirements for the plasma heating systems, vacuum vessel, plasma facing components, diagnostics, and ancillary equipment. This is accentuated by the 1000-second pulse requirement. Two major design changes, which have significantly affected the TPX Heating and Cooling System, have been made since the conceptual design review in March of 1993. This paper will discuss these changes and review the current status of the conceptual design. The first change involves replacing the vacuum vessel neutron shielding configuration of lead/glass composite tile by a much simpler and more reliable borated water shield. The second change reduces the operating temperature of the vacuum vessel from 150 C to {ge}50 C. With this temperature reduction, all in-vessel components and the vessel will be supplied by coolant at a common {ge}50 C inlet temperature. In all, six different heating and cooling supply requirements (temperature, pressure, water quality) for the various TPX components must be met. This paper will detail these requirements and provide an overview of the Heating and Cooling System design while focusing on the ramifications of the TPX changes described above.

• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 465014
• Report Number(s): CONF-950905--; ISBN 0-7803-2969-4
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DESIGN
MODIFICATIONS
SHIELDS
SPECIFICATIONS
THERMONUCLEAR REACTOR COOLING SYSTEMS
TPX DEVICE
VACUUM SYSTEMS