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

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 ofmore » 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)« less

Publication Date:
Research Org.:
Martin Co. Nuclear Div., Baltimore
Sponsoring Org.:
USDOE
OSTI Identifier:
4064004
Report Number(s):
MND-P-3013-I
NSA Number:
NSA-15-012653
DOE Contract Number:  
AT(30-3)-217
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-61
Country of Publication:
United States
Language:
English
Subject:
GENERAL AND MISCELLANEOUS; BREAKDOWN; CERAMICS; CERIUM 144; COATING; DIELECTRICS; ELECTRIC CONDUCTIVITY; FUELS; GENERATORS; HEAT TRANSFER; MERCURY; POLONIUM 210; PORCELAIN; POWER; PRODUCTION; PROPULSION; RADIOISOTOPES; REMOTE HANDLING; SAFETY; SHIELDING; SNAP SYSTEMS; SPACE VEHICLES; TESTING; THERMAL CONDUCTIVITY; VESSELS; NESDPS Office of Nuclear Energy Space and Defense Power Systems

Citation Formats

None. SNAP RADIOISOTOPE SPACE PROGRAMS, TASK 2, 3 AND 7, QUARTERLY PROGRESS REPORT NO. 5, OCTOBER 1 THROUGH DECEMBER 31, 1960. United States: N. p., 1961. Web. doi:10.2172/4064004.
None. SNAP RADIOISOTOPE SPACE PROGRAMS, TASK 2, 3 AND 7, QUARTERLY PROGRESS REPORT NO. 5, OCTOBER 1 THROUGH DECEMBER 31, 1960. United States. doi:10.2172/4064004.
None. Tue . "SNAP RADIOISOTOPE SPACE PROGRAMS, TASK 2, 3 AND 7, QUARTERLY PROGRESS REPORT NO. 5, OCTOBER 1 THROUGH DECEMBER 31, 1960". United States. doi:10.2172/4064004. https://www.osti.gov/servlets/purl/4064004.
@article{osti_4064004,
title = {SNAP RADIOISOTOPE SPACE PROGRAMS, TASK 2, 3 AND 7, QUARTERLY PROGRESS REPORT NO. 5, OCTOBER 1 THROUGH DECEMBER 31, 1960},
author = {None},
abstractNote = {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)},
doi = {10.2172/4064004},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1961},
month = {10}
}