Influence of noble metal fission products and uranium on the microstructure and corrosion behaviour of D9 stainless steel–zirconium metal waste form alloy

2014 ◽  
Vol 448 (1-3) ◽  
pp. 340-347 ◽  
Author(s):  
Lipika Rani Bairi ◽  
C. Mallika ◽  
U. Kamachi Mudali
Keyword(s):  
Stainless Steel ◽  
Noble Metal ◽  
Corrosion Behaviour ◽  
Fission Products ◽  
Waste Form ◽  
Metal Waste ◽  
Zirconium Metal

Microstructural analysis and corrosion behaviour of D9 stainless steel – Zirconium metal waste form alloys

2010 ◽  
Vol 52 (7) ◽  
pp. 2291-2302 ◽  
Author(s):  
Lipika Rani Bairi ◽  
S. Ningshen ◽  
U. Kamachi Mudali ◽  
Baldev Raj
Keyword(s):  
Stainless Steel ◽  
Corrosion Behaviour ◽  
Microstructural Analysis ◽  
Waste Form ◽  
Metal Waste ◽  
Zirconium Metal

scholarly journals Microstructure and Leaching Characteristics of a Technetium Containing Metal Waste Form

1999 ◽  
Vol 556 ◽  
Author(s):  
S. G. Johnson ◽  
D. D. Keiser ◽  
M. Noy ◽  
T. O'Holleran ◽  
S. M. Frank
Keyword(s):  
Stainless Steel ◽  
National Laboratory ◽  
Argonne National Laboratory ◽  
Fission Products ◽  
Point Of View ◽  
Waste Form ◽  
Nominal Composition ◽  
Spent Fuel ◽  
Waste Forms ◽  
Metal Waste

AbstractArgonne National Laboratory is developing 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, Pd, Rh, Ag. The nominal composition of this waste form is stainless steel/15 wt% zirconium/ 1–4 wt% noble metal fission products. The behavior of technetium is of particular importance from a disposal point of view for this waste form due to its long half life, 2.14E5 years, and its mobility in groundwater. To address these concerns a limited number of spiked metal waste forms were produced containing Tc. These surrogate waste forms were then studied using scanning electron microscopy (SEM) and selected leaching tests.

TEM Analysis of Corrosion Products From a Radioactive Stainless Steel-based Alloy

2000 ◽  
Vol 6 (S2) ◽  
pp. 368-369
Author(s):  
N.L. Dietz ◽  
D.D Keiser
Keyword(s):  
Stainless Steel ◽  
Spent Nuclear Fuel ◽  
National Laboratory ◽  
Argonne National Laboratory ◽  
Fission Products ◽  
Waste Form ◽  
Metallic Sodium ◽  
Geologic Repository ◽  
Tem Analysis ◽  
Waste Forms

Argonne National Laboratory has developed an electrometallurgical treatment process for metallic spent nuclear fuel from the Experimental Breeder Reactor-II. This process stabilizes metallic sodium and separates usable uranium from fission products and transuranic elements that are contained in the fuel. The fission products and other waste constituents are placed into two waste forms: a ceramic waste form that contains the transuranic elements and active fission products such as Cs, Sr, I and the rare earth elements, and a metal alloy waste form composed primarily of stainless steel (SS), from claddings hulls and reactor hardware, and ∼15 wt.% Zr (from the U-Zr and U-Pu-Zr alloy fuels). The metal waste form (MWF) also contains noble metal fission products (Tc, Nb, Ru, Rh, Te, Ag, Pd, Mo) and minor amounts of actinides. Both waste forms are intended for eventual disposal in a geologic repository.

Corrosion issues related to disposal of 316 SS–zirconium metal waste form under simulated repository conditions

2011 ◽  
Vol 46 (2) ◽  
pp. 171-176 ◽  
Author(s):  
Lipika Rani Bairi ◽  
S Ningshen ◽  
U Kamachi Mudali ◽  
Baldev Raj
Keyword(s):  
Waste Form ◽  
Metal Waste ◽  
Zirconium Metal

Corrosion Testing of Stainless Steel-Zirconium:Metal Waste Forms

1999 ◽  
Vol 556 ◽  
Author(s):  
D. P. Abraham ◽  
L. J. Simpson ◽  
M. J. Devries ◽  
S. M. Mcdeavitt
Keyword(s):  
Stainless Steel ◽  
Spent Nuclear Fuel ◽  
Fission Products ◽  
Waste Form ◽  
Waste Forms ◽  
Immersion Corrosion ◽  
Corrosion Studies ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Nuclear Waste Forms

AbstractStainless steel-zirconium (SS-Zr) alloys have been developed as waste forms for the disposal of metallic waste generated during the electrometallurgical treatment of spent nuclear fuel. The waste forms incorporate irradiated cladding hulls, components of the alloy fuel, noble metal fission products, and actinide elements. The baseline waste form is a stainless steel- 15 wt% zirconium (SS-15Zr) alloy. This article presents microstructures and some of the corrosion studies being conducted on the waste form alloys. Electrochemical corrosio n, immersion corrosion, and vapor hydration tests have been performed on various alloy compositions to evaluate corrosion behavior and resistance to selective leaching of simulated fission products. The SS-Zr waste forms immobilize and retain fission products very effectively and show potential for acceptance as high-level nuclear waste forms.

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