EURATOM PROGRAM "Improved Zirconium Alloys" Page: 3
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0.25, l, 3. (each) Cu, Fe. Si. Cr. W. Mo
Ta, A*. Bi, Te, Ce, Co.
Ni, Pb, Pt. Pd, Rh. Ag. Au
Some of these alloy additions might be undesirable because of neutron cap-
ture cross section or cost considerations but have been prepared for the
fundamental knowledge of corrosion behavior. Only one ternary series has
been prepared, and it is a ramification of the Soviet work reported at the
1958 Geneva Conference. The system under study is the following:
Zr-25Nb-l(Sn, Sb. Cr, V, Fe, Cu. Pd)
A particularly good grade of sponge zirconium was obtained
for this program; the as-melted hardness of the zirconium is 105 VPN.
A method of specimen fabrication is being employed which
prevents contamination and oxidation of the alloys. While this fabrication
procedure would be considered impractical on a production basis, for a
research program with a large number of different compositions to be
fabricated it is highly acceptable. Briefly, alloys are prepared by noncon-
sumable arc melting, and the resulting 100-gram button ingot as jacketed
in a welded mild steel container. The ingot assembly is rolled at 1 550*F
with a 10 per cent reduction per pass. After seven passes, the ingot is
annealed for two hours at 1550*F, after which rolling is continued at the
same temperature. Prior to the final two roll passes, the temperature is
dropped below the transformation (to 1350'F in most cases) and rolling is
finished. This procedure results in a 0.110 inch elliptical sheet from
which corrosion and tensile specimens are fabricated. The sheet is homo-
geneous. and has an equiaxed microstructure of stable transformation prod-
In production of a corrosion specimen, the steel jacket is
stripped off, small coupons are cut, and 0.030 inch of metal is milled off
of each surface to insure removal of the diffused iron layer. The milled
coupons are then lapped to provide a smooth surface, and pickling follows
to remove cold-worked metal and provide a bright, metallographic -type
finish. Three-liter, static autoclaves are used for corrosion testing; the
temperature is controlled at 680*F for the pressurized water evaluations.
A standardized procedure is followed in weighing and measuring specimens,
and the water used has a pH of 7 and a resistivity of 800, 000 ohm-cm.
Only a limited amount of preliminary data has been obtained,
and these data were discussed under work for the month of September (III).
At this writing, 26 corrosion specimens are being tested in 680'F water
for a duration of seven days.
From the onset of this program, it was apparent that in order
to plan a development program effectively and efficiently, knowledge of pres-
ent work on zirconium alloy development must be brought up to date. The
ARMOUR 1 S St A#CM FOUNDATION OF ILLINOIS IN STllUTI OF TICMNOLOGT
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Weinstein, Daniel. & Van Thyne, R. J. EURATOM PROGRAM "Improved Zirconium Alloys", report, October 5, 1960; Chicago, Illinois. (https://digital.library.unt.edu/ark:/67531/metadc502437/m1/3/: accessed June 24, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.