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U.S. Department of Energy
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TECHNICAL PROGRESS REPORT FOR THE PERIOD JULY THROUGH SEPTEMBER 1953

Technical Report ·
OSTI ID:4328476
Bend tests have revealed that beryllium sheet can be made by cross rolling of extruded powder flats which has high ductility in two directions in the plane of the sheet. Direct experiment has shown that nitrogen will penetrate much into a bed of hot beryllium powder than does carbon monoxide. Extensive thermal cycling tests have shown that the growth per cycle is smallest at the front end of an alpha extruded bar of uraniuun and increases uniformly toward the back end. The coarse grains sometimes produced by alpha extrusion occur first at the leading end of the bar and at the surface. The coarse grains ahow much less cycling growth than the fine grains. Corrosion testing of epsilon uraniumsilicon alloy is in progress. Zirconium appears to scavenge carbon and nitrogen from molten uranium through flotation of carbides and nitrides. Zirconium is relatively resistant to molten U-Cr alloy. A fairly successful radiator casting was made with zirconium tubes which were in contact with U- Cr at 1000 deg C for five minutes. An extensive report on recrystallization of crystal bar zirconium as a function of percentage reduction and of annealing temperature for different lengths of time is given, Zirconium cladding of graphite by dipping in molten zirconium has given some promising results. It has been shown that the corrosion resistance of Bureau of Mines zirconium is reduced by quenching from temperatures in the vicinity of the alpha-beta transformation. Chromium from the Bureau of Mines was extruded at 1900 deg F. All tests to date have shown that it is brittle at room temperature. (auth)
Research Organization:
Massachusetts Inst. of Tech., Cambridge. Metallurgical Project
NSA Number:
NSA-12-001991
OSTI ID:
4328476
Report Number(s):
MIT-1114
Country of Publication:
United States
Language:
English