PNNL-13501 - Pacific Northwest National Laboratory
PNNL-13501 - Pacific Northwest National Laboratory
PNNL-13501 - Pacific Northwest National Laboratory
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erbium coatings were applied to zircaloy-4 sheet. The<br />
erbium coatings were applied in the pure state and also<br />
with Zr overcoats, and a variety of thicknesses and<br />
coating parameters were investigated.<br />
Coated coupons (both Er-only and Zr-overcoated Er)<br />
were paired with other coated and bare zircaloy-4<br />
coupons, and seal-welded to produce feedstock for hot<br />
roll bonding. Prior to welding, the surfaces to be bonded<br />
were sanded with SiC paper and swabbed with B-etch for<br />
several minutes to remove any oxide film. After<br />
preparation, the coupons were rapidly transported to the<br />
weld chamber to prevent oxide formation. Coupons were<br />
hot roll bonded at 800°C at overall thickness reductions of<br />
10% to 20%. The best results were obtained with either<br />
erbium or Zr-overcoated erbium coatings bonded with<br />
bare zircaloy-4 coupons.<br />
Coupons seal-welded in a He atmosphere were prevented<br />
from completely bonding during hot rolling by the He.<br />
Three alternate coupon welding techniques were<br />
investigated. These included: 1) electron beam welding<br />
in vacuum, 2) TIG welding in He with a brazed Cu tube<br />
serving as a vacuum port, and 3) TIG welding in He with<br />
a brazed Cu tube serving as a gas bladder to accommodate<br />
the He during hot rolling. The TIG welding techniques<br />
were unsuccessful because the braze failed during heating<br />
to 800°C prior to hot rolling. Although electron beam<br />
welding is not suitable for large, manfactured<br />
components, it was used for the remainder of the<br />
development work due to resource limitations. The TIG<br />
welding approach would likely work if Zr or zircaloy<br />
tubes were used for the vacuum ports or gas bladders.<br />
Initial efforts to hot roll bond the coupons fabricated by<br />
electron beam welding were unsuccessful. The time<br />
between surface preparation (sanding and B-etch) and<br />
insertion into the vacuum chamber appeared to be<br />
unacceptably long, allowing an oxide layer to form. Later<br />
efforts were successful when the samples were stored in a<br />
dessicator and evacuated to 10 -6 torr within 10 to 15<br />
minutes after sample preparation. These samples<br />
displayed complete bonding across the width of the<br />
coupons, with no evidence of failures.<br />
The final objective of the development effort involved a<br />
demonstration of the formability of the laminates in a<br />
prototypical width (approximately 20 cm). The most<br />
common method for producing boiling water reactor fuel<br />
channels involves forming the zircaloy-4 sheet into a Uchannel,<br />
and butt-welding two U-channels to form a<br />
continuous square duct. Significant effort was expended<br />
to develop a suitable thermomechanical processing<br />
schedule to produce laminated U-channels of prototypic<br />
364 FY 2000 <strong>Laboratory</strong> Directed Research and Development Annual Report<br />
width. Difficulties associated with embrittlement of the<br />
zircaloy-4 by oxidation during hot rolling and annealing<br />
in air occured. To alleviate these problems, the surface<br />
oxide picked up during hot rolling was removed prior to<br />
further processing, and annealing was done in vacuum or<br />
inert gas.<br />
After e-beam welding, the samples were milled on both<br />
faces to produce a prototypic thickness of 0.25 cm. They<br />
were then hot-rolled. The hot rolling was done in air.<br />
The oxide film was mechanically removed prior to<br />
annealing. The samples were then annealed and formed<br />
into U-channels using a mechanical press.<br />
Experimental work on this study is in its final stages. A<br />
prototypic-dimension fuel channel section will be<br />
produced from two U-channels produced using the<br />
process described above. Some of the U-channels will be<br />
hot-rolled and/or annealed at 750°C to evaluate the effect<br />
of a lower working temperature. Ideally, a final<br />
thermomechanical processing schedule will be established<br />
as the starting point for manufacturing scale-up activities<br />
that would be conducted as part of a follow-on program.<br />
Summary and Conclusions<br />
To date, the study has demonstrated the feasibility of<br />
producing Zry/Er/Zry laminate structures consistently and<br />
with reasonably reproducible properties. Laminates and<br />
U-channels have been produced in prototypic thicknesses<br />
and widths for boiling water reactor fuel channel<br />
applications. Significant development work remains to<br />
transform the laboratory-scale process to one more<br />
suitable for high-throughput production. However, most<br />
of the methods used for commercial zircaloy production<br />
appear to be applicable to fabricating square ducts<br />
fabricated from Zry/Er/Zry laminates.<br />
Bibliography<br />
American Society for Testing and Materials. 1979.<br />
Standard specification for zirconium and zirconium alloy<br />
sheet, strip, and plate for nuclear application, ASTM B<br />
352-79. American Society for Testing and Materials,<br />
West Conshohocken, Pennsylvania.<br />
Savitskii EM, VF Terekhova, IV Burov, IA Markova, and<br />
OP Maumkin. 1962. “Rare earth alloys.” USSR<br />
Academy of Sciences, p. 58. Moscow.<br />
Love B and C Kirkpatrick. 1961. “Mechanical properties<br />
of rare earth metals” in Rare Earth Research, Ed. E.V.<br />
Kleber, The Macmillan Company, New York.