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Y-I 2 Y-2467-3 Y-12 DEVELOPMENT ORGANIZATION TECHNICAL PROGRESS REPORT Part 3 - Metal Processing Period Ending September 1, 1994

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Page 1: Y-I 2 Y-2467-3 - Digital Library/67531/metadc681618/m2/1/high_res_d/39124.pdfY-I 2 Y-2467-3 Y-12 DEVELOPMENT ORGANIZATION TECHNICAL PROGRESS REPORT ... Oak Ridge Y-12 Plant P.O. Box

Y-I 2 Y-2467-3

Y-12 DEVELOPMENT ORGANIZATION TECHNICAL PROGRESS REPORT

Part 3 - Metal Processing

Period Ending September 1, 1994

Page 2: Y-I 2 Y-2467-3 - Digital Library/67531/metadc681618/m2/1/high_res_d/39124.pdfY-I 2 Y-2467-3 Y-12 DEVELOPMENT ORGANIZATION TECHNICAL PROGRESS REPORT ... Oak Ridge Y-12 Plant P.O. Box

DISC LAlMER

This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or use- fulness of any information, apparatus, product, or process disclosed, or represents that i t s use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manu- facturer, or otherwise, does not necessarily constitute or imply i ts endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those o f the United States Government or any agency thereof. .

Page 3: Y-I 2 Y-2467-3 - Digital Library/67531/metadc681618/m2/1/high_res_d/39124.pdfY-I 2 Y-2467-3 Y-12 DEVELOPMENT ORGANIZATION TECHNICAL PROGRESS REPORT ... Oak Ridge Y-12 Plant P.O. Box

DISCLAIMER

Portions of this document may be illegible in electronic image products. Images are produced from the best available original document.

Page 4: Y-I 2 Y-2467-3 - Digital Library/67531/metadc681618/m2/1/high_res_d/39124.pdfY-I 2 Y-2467-3 Y-12 DEVELOPMENT ORGANIZATION TECHNICAL PROGRESS REPORT ... Oak Ridge Y-12 Plant P.O. Box

Date of Issue: February 8, 1995 Y-2467-3

Y-12 DEVELOPMENT ORGANIZATION TECHNICAL PROGRESS REPORT

Part 3 - Metal Processing

Compiled by W. G. Northcutt, Jr.

Period Ending September 1,1994

Prepared by the Oak Ridge Y-12 Plant

P.O. Box 2009, Oak Ridge, Tennessee 378314169 managed by

MARTIN MARE'ITA ENERGY SYSTEMS, INC. for the

U.S. DEPARTMENT OF ENERGY under contract DE-AC05-840R21400

c

Page 5: Y-I 2 Y-2467-3 - Digital Library/67531/metadc681618/m2/1/high_res_d/39124.pdfY-I 2 Y-2467-3 Y-12 DEVELOPMENT ORGANIZATION TECHNICAL PROGRESS REPORT ... Oak Ridge Y-12 Plant P.O. Box

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Page 6: Y-I 2 Y-2467-3 - Digital Library/67531/metadc681618/m2/1/high_res_d/39124.pdfY-I 2 Y-2467-3 Y-12 DEVELOPMENT ORGANIZATION TECHNICAL PROGRESS REPORT ... Oak Ridge Y-12 Plant P.O. Box

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3

HIGHLIGHTS

ALXJMXNUM--URANIUPJImYCCASTING

The authors melted and cast an aluminum-uranium (AI-U) alloy by vacuum induction melting (VIM) prealloyed buttons made by arc melting. The resulting alloy casting displayed a large compositional gradient from top to bottom. (Page 6)

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Page 8: Y-I 2 Y-2467-3 - Digital Library/67531/metadc681618/m2/1/high_res_d/39124.pdfY-I 2 Y-2467-3 Y-12 DEVELOPMENT ORGANIZATION TECHNICAL PROGRESS REPORT ... Oak Ridge Y-12 Plant P.O. Box

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METAL PROCESSING

ALUMINUM-URANIUM ALLOY CASTING (A. L. DeMint and A. W. Maxey) . . . . 6

Page 9: Y-I 2 Y-2467-3 - Digital Library/67531/metadc681618/m2/1/high_res_d/39124.pdfY-I 2 Y-2467-3 Y-12 DEVELOPMENT ORGANIZATION TECHNICAL PROGRESS REPORT ... Oak Ridge Y-12 Plant P.O. Box

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METAL PROCESSING

A. L. DeMint and A. W. Maxey

Summary

The authors melted and cast an aluminum-uranium ( 4 - U ) alloy by vacuum induction melting (VIM) prealloyed buttons made by arc melting. The resulting alloy casting displayed a large compositional gradient from top to bottom.

Introduction

The Y-12 Plant Laboratory requested a series of AI-U alloys to serve as standards for assaying shipments that would be received from the Westinghouse Savannah River Company site. The alloys ranged from pure aluminum to -63 wt % aluminum in uranium and were required to contain precise amounts of uranium and aluminum. Since the "real" alloys were to contain enriched uranium, the casting method was tested on depleted uranium. The alloy with the highest uranium content (37%) was chosen to prove out the system.

Standard metal casting operations that involve pouring the metal always generate a skull (material left behind in the crucible) and therefore were not used because of the precise weight requirement. Powder metallurgy processes produce parts as homogeneous as the starting powders can be blended, and losses are insignificant; however, the need for enriched uranium restricted the fabricating operations to arc melting and induction melting.

Uranium and aluminum form several intermetallic compounds, the most refractory of which melts at 1620°C (UAl,: -19 wt % aluminum). In comelting pure aluminum and uranium, one would expect to pass through all of these phases until the metal becomes homogeneous. If the comelting is carried out below 1620"C, formation of UAl, would delay the homogenization of the alloy. The mold washes used for induction melting uranium begin to break down at 1450°C; therefore, they would not be an effective barrier against carbon at the temperature required for good mixing.

The authors chose arc melting as the means for prealloying the material because much higher temperatures are achieved with arc melting, and the molten pool is contained by a solid film of the material being melted in a chilled copper cup. The prealloyed "buttons" could then be used as the charge for induction melting.

Presentation of Expe rimental Work

To test the process for fabricating the alloys, the authors made one casting of roughly 37 wt % uranium. They comelted the uranium and aluminum in an arc furnace in 400-g batches. They melted each batch, or button, two to three times and turned it over between melts to encourage better mixing of the two metals. They then loaded the buttons into a closed-bottom, graphite crucible, heated it to 1200"C, and allowed it to solidify. (This composition should melt at - 1080°C).

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Results and Discussion

The authors sampled the resulting casting €or uranium to check homogeneity. The sampling revealed that the top of the casting contained 23.5 wt % uranium, and the bottom (an average of two samples) contained 42.4 wt % uranium.

Although each button contained 36.5% uranium, these analyses show that the solidified casting was inhomogeneous. If the buttons were homogenous, the segregation occurred during induction melting, and this method may not be feasible for making AI-U alloys. If the buttons were not homogeneous, perhaps arc melting the buttons more times would have helped. Bottom pouring the AI-U melt into a mold for faster cooling could also help prevent segregation.

Future Work

When the original problem was re-examined, the authors decided that the incoming alloy could be sampled extensively and used as standard material, eliminating the need for casting fresh alloy. No future work is planned.

References

None.

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METRIC CONVERSIONS

PRESSURE

psi MPa

3000+ 20. o

2000-

-: 10.0

- 8.0 - -

10002

30+ 0.20

20+

>o. 10 c - < -0.08

10-L-

VOLUME

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- 10.001

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0.20-j: :: 3000

O . l O +

0.107: -- 0.085

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I: 10,000 200~~8000 .-

-

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Distriiution

Allied Signal - Kansas City Division

Hofinann, J. W.

Department of Energy - Albuquerque

Nonnuclear Technology Branch, WQD Nuclear Technology Branch, WQD

Department of Energy - Oak Ridge

Carpenter, P. A. Spence, R. J.

EG&G - Mound Applied Technologies

Records Management

EG&G - Rocky Flats Plant

Manager, Document Control-CCDM

Lawrence Livermore National Laboratory

Clough, R. E. Colmenares, C. A. Hanafee, J. E. Kolb, J. R. Makowiecki, D. M. Technical Information Division Wood, D. H.

Los Alamos National Laboratory

Casey, H. Hanson, E. M. McAfee, J. M. Report Library Salazar, L. Shafer, B. P. Stretz, L. A.

Oak Ridge Y-12 Plant

Ammons, A. M. Bird, E. L. Bowers, G. L.

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Lee, A. KDOE-OSTI (2) Morrow, M. K. Northcutt, W. G., Jr. Richey, M. W. Stout, J. D. Y-12 Central Files (Y-12RC) 9202 File Point

Sandia National Laboratories - California

Bohrer, D. J. Cull, E. T. Johnson, H. R. Lindner, D. L. Technical Library Wright, J. B.

Sandia National Laboratories - New Mexico

Davis, M. J. Eckelmeyer, K H. Ledman, J. L. Romig, A. D. Zanner, E J.

Westinghouse - Savannah River Plant

Knight, J. R.