Hostname: page-component-586b7cd67f-rcrh6 Total loading time: 0 Render date: 2024-11-25T17:57:25.704Z Has data issue: false hasContentIssue false
  • English
  • Français

Leaching Characteristics of the Metal Waste Form From the Electrometallurgical Treatment Process: Product Consistency Testing

Published online by Cambridge University Press:  10 February 2011

S. G. Johnson ,
D. D. Keiser ,
S. M. Frank ,
T. DiSanto ,
A. R. Warren  and
M. Noy
S. G. Johnson
Affiliation:
Argonne National Laboratory-West P.O. 2528 Idaho Falls, ID 83403
D. D. Keiser
Affiliation:
Argonne National Laboratory-West P.O. 2528 Idaho Falls, ID 83403
S. M. Frank
Affiliation:
Argonne National Laboratory-West P.O. 2528 Idaho Falls, ID 83403
T. DiSanto
Affiliation:
Argonne National Laboratory-West P.O. 2528 Idaho Falls, ID 83403
A. R. Warren
Affiliation:
Argonne National Laboratory-West P.O. 2528 Idaho Falls, ID 83403
M. Noy
Affiliation:
Argonne National Laboratory-West P.O. 2528 Idaho Falls, ID 83403
Get access

Abstract

Argonne National Laboratory has developed an electrometallurgical treatment for spent fuel from the experimental breeder reactor II. A product of this treatment process is a metal waste form that incorporates the stainless steel cladding hulls, zirconium from the fuel and the fission products that are noble to the process, i.e., Tc, Ru, Nb, Pd, Rh, and Ag. The nominal composition of this waste form is stainless steel/15 wt% zirconium/1-4 wt% noble metal fission products /1-2 wt % U. Leaching results are presented from crushed sample immersion tests on simulated metal waste form samples. The test results will be presented and their relevance for waste form product consistency testing discussed.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 608: Symposium QQ – Scientific Basis for Nuclear Waste Management XXIII , 1999 , 589
Copyright
Copyright © Materials Research Society 2000

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

[I] McDeavitt, S. M., Abraham, D. P., Park, J. Y., J. Nucl. Mat., 257, 21 (1998).Google Scholar
[2] Keiser, D. D., Westphal, B. W., ANS Proceedings “Third Topical Meeting DOE Spent Nuclear Fuel and Fissile Materials Management”, Charleston, SC, 668 (1998).Google Scholar
[3] Office of Civilian Radioactive Waste Management, Waste Acceptance System Requirements Document, E00000000-008i 1-1708-00001, rev. 2 (1996).Google Scholar
[4] Marra, J. C., Marra, S. L., Bibler, N. E., ANS Proceedings “Third Topical Meeting DOE Spent Nuclear Fuel and Fissile Materials Management”, Charleston, SC, 731 (1998).Google Scholar
[5] C1220-97, "Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses: The Product Consistency Test (PCT)", ASTM, Philadelphia (1999).Google Scholar
[6] Johnson, S. G., Keiser, D. D., Noy, M., O'Holleran, T. P., Frank, S. M., MRS proceeding Sci. Basis Waste Mang. 1998, in press (1999).Google Scholar