Interaction layers between metal alloy fuel and stainless steel cladding in irradiated fuel elements

Journal Article · Mon Dec 01 04:00:00 EST 1997 · Transactions of the American Nuclear Society

OSTI ID:552447

Cohen, A B ^[1]; Keiser, Jr, D D ^[2]

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1. Argonne National Lab., IL (United States)
2. Argonne National Lab.-West, Idaho Falls, ID (United States)

Argonne National Laboratory (ANL) is developing an electrometallurgical treatment process for spent nuclear fuels. Initial demonstration of the process is being conducted on Experimental Breeder Reactor (EBR)-II-irradiated metal fuel elements that contain either U-10 Zr or U-x Pu-10 Zr (x {le} 26) fuel in either tempered martensite (HT9) or austenitic stainless steel (Type 316 stainless steel or 139) cladding. Chopped fuel segments are placed in an anode basket, and an electric current is applied to remove the uranium, actinides, and fission products from the cladding; the uranium is deposited on a stainless steel cathode. The remaining cladding {open_quotes}hulls,{close_quotes} zirconium, and other noble metal constituents are subsequently melted and solidified as a metal waste form that will eventually be stored in a geologic repository. During irradiation of metal fuel elements, the fuel swells and physically contacts the cladding. As a result, interdiffusion of fuel and cladding constituents occurs, and interaction layers form on the inner surface of the cladding. The actinides and fission products that end up in phases in the cladding may remain an integral part of the cladding hull during reprocessing, instead of being removed with the actinides, and may eventually be a part of the metal waste form. To qualify a waste form for disposal, one must identify the chemical and radiological components of that waste form. The purpose of this paper is to review past experimental results to provide data for understanding the constituents in the fuel/cladding interaction layers that eventually may be found in the metal waste form.

• OSTI ID: 552447
• Report Number(s): CONF-971125--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 77; ISSN TANSAO; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
CLADDING
ELECTRIC CURRENTS
FISSION PRODUCTS
LAYERS
PLUTONIUM
REPROCESSING
SEPARATION PROCESSES
SPENT FUELS
STAINLESS STEEL-316
SWELLING
URANIUM
WASTE FORMS
ZIRCONIUM ALLOYS