SNAP RADIOISOTOPE SPACE PROGRAMS, TASK 2, 3 AND 7, QUARTERLY PROGRESS REPORT NO. 5, OCTOBER 1 THROUGH DECEMBER 31, 1960

Technical Report · Tue Oct 31 04:00:00 EST 1961

DOI:https://doi.org/10.2172/4064004· OSTI ID:4064004

Functional testing was completed on the ground handling equipment for transporting the Ce/sup 144/ heat source container and loading the SNAP 1A generator. Mercury shield fill and drain tests for the generator system and the collar shield were conducted. Heat-transfer tests of the isotope heat source shipping cask were conducted. Simulated rocket-launch environmental tests of vibration, acceleration, and shock were completed on the G-2 generator. Analysis of the environmental test data was initiated. Final dssign studies for the G-3 generator were completed, and a thermoelectric module concept was selected for use in the isotope-fueled generator. Development tests of thermoelectric modules in a module tester were initiated. Voltage breakdown tests were conducted on a porcelain enamel spray coat. The matenial was evaluated for application to the G- 3 generator inner skin as a possible second discrete barrier against hot junction electrical shorts. SNAP 3 generator 3M-1G10 completed 322 days of life test operation, and the power input was terminated after the generator was operated under a full range of external loads to obtain performance characteristics. Electrical power output after 322 days at steady-state heat source and external load conditions was 1.92 watts, for an over-all efficiency of 2.9%. Tear-down inspection of the generator conformed previous indications of incrsased internal electrical resistance and thermal conductivity, which account for the gradual reduction in generator performance from the start-of-life electrical output of 3.45 watts and 5.2% over-all efficiency. The SNAP 3 3M-1G5 generator was successfully fueled with Po/sup 210/. Maximum electrical power output was 4 watts at an over-all efficiency of 5.2%. Radiological safety studies for space power were initiated. (For preceding period see MND-P-3012-I.) (auth)

• Research Organization: Martin Co. Nuclear Div., Baltimore
• Sponsoring Organization: USDOE
• DOE Contract Number: AT(30-3)-217
• NSA Number: NSA-15-012653
• OSTI ID: 4064004
• Report Number(s): MND-P-3013-I
• Country of Publication: United States
• Language: English

Related Subjects

BREAKDOWN
CERAMICS
CERIUM 144
COATING
DIELECTRICS
ELECTRIC CONDUCTIVITY
FUELS
GENERAL AND MISCELLANEOUS
GENERATORS
HEAT TRANSFER
MERCURY
NESDPS Office of Nuclear Energy Space and Defense Power Systems
POLONIUM 210
PORCELAIN
POWER
PRODUCTION
PROPULSION
RADIOISOTOPES
REMOTE HANDLING
SAFETY
SHIELDING
SNAP SYSTEMS
SPACE VEHICLES
TESTING
THERMAL CONDUCTIVITY
VESSELS