ANP HTREs FULFILL TEST GOALS

Journal Article · Sun Jan 01 04:00:00 EST 1961 · Nucleonics (U.S.) Ceased publication

OSTI ID:4120083

Thornton, G; Blumberg, B

Performance results from the Heat Transfer Reactor Experiment (HTBE) test series have measured up to or exceeded expectations. The series has involved three reactor systems (HTRE-l, HTRE-2, and HTRE-3) and two reactor concepts (water-moderated and ZrH-moderated). HTRE-l achieved a number of full- power runs which demonstrated conclusively the feasibility of operating a jet engine on nuclear power, and easily passed a 100-hr endurance test at fuel temperatures to l850 deg F, operating a single J-47 jet engine at power levels of 18.5 Mw. The HTRE-2 consisted of a mechanical modification of HTRE-l to serve as a test facility for advanced fuel and moderator sections. The HTRE-3 system differed from HTRE-l and -2 in that it had a solid ZrH-moderator and an air- cooled core structure, where the others were water-cooled and moderated. The HTRE-3 system was tested with parallel J-47 engines at 32.4 Mw. Since the HTRE-3 core was designed for air flow of 850 lb/sec and the requirements of the jets were 123 lb/ sec, it is seen that when coupled to an engine system of greater capacity the BTRE-3 could conceivably develop a correspondingly higher power level. The design concepts and operational charaeteristics of the three reactor systems are described. Specifies are given on the performance of HTRE-3. Design, mechanical, nuclear, and thermodynamic data are included for HTRE-l. (B.O.G.)

• Research Organization: General Electric Co., Cincinnati
• NSA Number: NSA-15-007098
• OSTI ID: 4120083
• Journal Information: Nucleonics (U.S.) Ceased publication, Journal Name: Nucleonics (U.S.) Ceased publication Vol. Vol: 19, No. 1; ISSN NUCLA
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

AIR
AIRCRAFT
FUELS
GAS COOLANT
GAS FLOW
HEAT TRANSFER
HTRE-1
HTRE-2
HTRE-3
MEASURED VALUES
MODERATORS
PERFORMANCE
PROPULSION
REACTOR TECHNOLOGY
REACTORS
SOLIDS
TEMPERATURE
TESTING
THERMODYNAMICS
WATER COOLANT
WATER MODERATOR
ZIRCONIUM HYDRIDES