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U.S. Department of Energy
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PLUTONIUM FUELS DEVELOPMENT--PLUTONIUM METALLURGY OPERATION QUARTERLY REPORT (FOR) OCTOBER, NOVEMBER, DECEMBER, 1957

Technical Report ·
OSTI ID:4290912

Data are given on the status of irradiation testing of Al--1.56 wt.% Pu and Al--12 wt.% Si--1.56 wt.% Pu alloy capsules in the MTR. Four-rod clusters containing Al--8 wt.% Pu and Al--12 wt.% Si--8 wt. % Pu alloy cores in Zircaloy jackets are being prepared for irradiation in the high-temperature (260 C) KER Loop Facility. Corrosion properties of the Zircaloy tubing and the end cap welds are being evaluated in the out of pile loops. Work is continuing on the development of airpressure injection casting techniques for the fabrication of Al --Pu fuel elements. A development program to determine the feasibility of mechanical pressure injection casting or die casting Al--Pu alloy fuel elements of PRTR size and quality is progressing. Pyrometallurgical techniques are being investigated as a means of reconstituting irradiated Pu fuel materials through concentration of a Pu-bearing phase from the principal alloying elements. A small extrusion press was put into operation to determine the hot and cold extrusion characteristics of Pu and its alloys. Compacted billets of blended mixtures of aluminum powder and UO/sub 2/ were hot extruded bare and also coextruded in aluminum alloy jackets. Radiation effects are being determined on UO/sub 2/ PuO/sub 2/ mixed crystal fuel materials. Corrosion tests are being conducted on Al alloys using U as a stand in for Pu. The problems of heat transfer, corrosion, flow characteristics, and thermal cycling of the 19-rod cluster fuel elements are being studied. (For preceding period see HW-64365.) (W.L.H.)

Research Organization:
General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
DOE Contract Number:
W-31-109-ENG-52
NSA Number:
NSA-13-000197
OSTI ID:
4290912
Report Number(s):
HW-55415
Country of Publication:
United States
Language:
English