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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.

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