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Helium heater design for the helium direct cycle component test facilityThe paper describes a helium heater to be used to conduct non-nuclear demonstration tests of the complete power conversion loop for a direct-cycle gas-cooled nuclear reactor power plant. Requirements for the heater include: heating the helium to a 1500 F temperature, operating at a 1000 psia helium pressure, providing a thermal response capability and helium volume similar to that of the nuclear reactor, and a total heater system helium pressure drop of not more than 15 psi. The unique compact heater system design proposed consists of 18 heater modules; air preheaters, compressors, and compressor drive systems; an integral control system; piping; and auxiliary equipment. The heater modules incorporate the dual-concentric-tube 'Variflux' heat exchanger design which provides a controlled heat flux along the entire length of the tube element. The heater design as proposed will meet all system requirements. The heater uses pressurized combustion (50 psia) to provide intensive heat transfer, and to minimize furnace volume and heat storage mass.
Document ID
19750061590
Document Type
Conference Paper
Authors
Larson, V. R.
Gunn, S. V.
Lee, J. C. (Rockwell International Corp. Rocketdyne Div., Canoga Park, Calif., United States)
Date Acquired
August 8, 2013
Publication Date
September 1, 1975
Subject Category
GROUND SUPPORT SYSTEMS AND FACILITIES (SPACE)
Report/Patent Number
AIAA PAPER 75-1262
Funding Number(s)
CONTRACT_GRANT: NAS3-19579
CONTRACT_GRANT: NAS3-18549
Distribution Limits
Public
Copyright
Other