SNAP RADIOISOTOPE SPACE PROGRAMS, TASK 2, 3 AND 7, QUARTERLY PROGRESS REPORT NO. 5, OCTOBER 1 THROUGH DECEMBER 31, 1960 [electronic resource]
Nesdps Office Of Nuclear Energy Space And Defense Power Systems.
Saved in:
| Online Access: |
Online Access |
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| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Department of Energy. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
1961.
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| Subjects: |
| Summary: | Nesdps Office Of Nuclear Energy Space And Defense Power Systems. |
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| Abstract: | 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) |
| Item Description: | Published through SciTech Connect. 10/31/1961. "mnd-p-3013-i" Martin Co. Nuclear Div., Baltimore. |
| Physical Description: | Pages: 46 : digital, PDF file. |