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

PROGRAM FOR THE DEVELOPMENT OF PLUTONIUM RECYCLE FOR USE IN LIGHT WATER MODERATED REACTORS. Quarterly Report No. 10, July 1-September 30, 1963

Technical Report ·
OSTI ID:4124974
The densitometry procedure (for measurement of alpha autoradiographs of fuel pellets) was modified to eliminate the need for a second emulsion. The existence of a problem of latent image fading and non-reciprocity of the highresolution emulsion was recognized. A tentative procedure was worked out to correct these emulsion difficulties. The number of hot spots per pellet has not changed appreciably. The largest spot seen was irregular with an estimated volume equivalent to that of a sphere of 35 mil diameter with a PuO/sub 2/ concentration of 60%. Applying the same scale factor between logged exposure and Ce-- Cs analysis of the first VBWR fuel sample, a corrected exposure of 4416 Mwd/ t was obtained. Further debugging of EPITHERMOS, the epithermal extension of the BNL THERMOS, code, is in progress. A flux wire exposure is being prepared to map the thermal neutron spectrum in the neighborhood of the test pins in the program fuel element. (auth)
Research Organization:
General Electric Co. Vallecitos Atomic Lab., San Jose, Calif.
NSA Number:
NSA-18-004762
OSTI ID:
4124974
Report Number(s):
GEAP-4385; EURAEC-886
Country of Publication:
United States
Language:
English