Testability of the S-prime thermionic power system

Journal Article · Fri Jan 20 00:00:00 EST 1995 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.47168· OSTI ID:90424

Determan, W R ^[1]; Kolesnikov, V P; Mezheritsky, G S; Poupko, V Y; Prilezhaeva, I N; Ryzhkov, A N; Zrodnikov, A V ^[2]

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1. Rockwell International Corporation, Rocketdyne Division, 6633 Canoga Avenue, Canoga Park, California 91303-7922 (United States)
2. Institute of Physics and Power Engineering (IPPE), Obninsk, Kaluga Region (Russian Federation)

The Thermionic Space Nuclear System Design and Technology Demonstration (TI-SNPS) program requires a low-risk, compact space nuclear power with a 5- to 40-kWe scalability, high conversion efficiency and the potential for long life. The 40-kWe S-PRIME system uses conventional materials in a known operating environment and the multicell thermionic fuel element (TFE) technology database to produce a low-risk approach to meeting the TI-SNPS flight system requirements. This design approach limits the risks to four key areas: TFE performance and lifetime, TFE testability demonstration, hydrogen control, and radiator heat pipe performance. These areas require critical component testing reduce risks within the development program (Mills {ital et} {ital al}. 1993). A TFE testability critical component demonstration was one of the six demonstrations scheduled in the S-PRIME Phase I Program. Multicell TFE testing techniques were pioneered in the countries of the former Soviet Union. The Institute of Physics and Power Engineering (IPPE) in Obninsk, Russia, a key S-PRIME subcontractor, was tasked with reviewing this database and recommending the best technical approach for acceptance testing individual S-PRIME TFEs and a network of TFEs in a reactor core assembly. IPPE developed (PPTE). Using the PPTF as a starting point, a 10-step process is defined for acceptance testing the overall S-PRIME power system, starting from the manufacturing process line for the individual TFEs to a final assembly and shipment of the power system to the launch site and its integration/checkout with the payload. {copyright} 1995 {ital American} {ital Institute} {ital of} {ital Physics}

• DOE Contract Number: AC03-92SF19138
• OSTI ID: 90424
• Report Number(s): CONF-950110-; ISSN 0094-243X; TRN: 95:018051
• Journal Information: AIP Conference Proceedings, Vol. 324, Issue 1; Conference: 12. symposium on space nuclear power and propulsion, Albuquerque, NM (United States), 8-12 Jan 1995; Other Information: PBD: 20 Jan 1995
• Country of Publication: United States
• Language: English

Related Subjects

21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
30 DIRECT ENERGY CONVERSION
THERMIONIC FUEL ELEMENTS
TESTING
CONTROL
HEAT PIPES
HYDROGEN
PERFORMANCE
PLANNING
POWER RANGE 01-10 KW
POWER RANGE 10-100 KW
REACTORS
TEST FACILITIES
THERMIONIC CONVERTERS
NESDPS Office of Nuclear Energy Space and Defense Power Systems