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U.S. Department of Energy
Office of Scientific and Technical Information

ORGANIC MODERATED REACTOR EXPERIMENT QUARTERLY PROGRESS REPORT FOR JANUARY-MARCH 1957

Technical Report ·
OSTI ID:4333113

An analysis was made of differences between batch and individual blending in the manufacture af OMRE fuel plates. The analysis of variance is presented. The variation of uranium density and stainless steel density as a function ef oxide content is plotted. Experimental heat transfer and fouling runs with unirradiated Santowax-R were completed, and results are given. A drop calorimeter was designed for the determination of the heat capacity ef organic coolants at temperature up to 900 deg F. Gas compositions were determined for the decomposition gases from the following materials circulated in the organic in- pile loops isopropyl diphenyl, diphenyl, Santowax R, and Santowax OM. The effect of radiation decomposition on the melting point of Santowax OM was determined. The carbon and hydrogen content of irradiated coolants is being determined in order to determine the change in moderating properties ef the coolant due to decomposition. The variation of the density of isopropyl dipheryl as a function of temperature with high-boiler residue content as a parameter is graphically illustrated. The density is seen to incresse about 5% over the temperature range 280 to 800 deg F as the residue content increases from 0 to 27%. An analysis ef dipheryl, utilizing neutron-induced activity to determine contamination, was completed for the OMRE reactor coolant charge. Gross gamma activity and concentration in parts per million of the major contaminants are reported. (For preceding period see NAA-SR-1850.) (M.H.R.)

Research Organization:
Atomics International Div., North American Aviation, Inc., Canoga Park, Calif.
NSA Number:
NSA-12-011001
OSTI ID:
4333113
Report Number(s):
NAA-SR-2150
Country of Publication:
United States
Language:
English