POWER REACTOR FUELS REPROCESSING. PROGRESS REPORT ON CORROSION STUDIES

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Work is reported on corrosion studies of candidate materials of construction for equipment for the dissolution of Zircaloy cladding in NH/sub 4/F- NH/sub 4/NO/sub 3/ solutions, the total dissolution of suainless steel clad fuels in HNO/sub 3/-HF solutions, and the dissolution of stainless steel cladding in dilute H/sub 2/SO/sub 4/. A single material of construction which could be used for a processing complex which would handle all of the low-enrichment fuels concerned was searched for. In the Zirflex Process (NH/sub 4/F-NH/sub 4/NO/sub 3/ ) the 300 series stainless steels, vacuum-melted Hastelloy-F, Carpenter 20, Nio- nel, Haynes 25, and Incoloy 804 ... continued below

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Pages: 57

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Maness, R.F. August 26, 1959.

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  • Hanford Atomic Products Operation
    Publisher Info: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
    Place of Publication: Richland, Washington

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Description

Work is reported on corrosion studies of candidate materials of construction for equipment for the dissolution of Zircaloy cladding in NH/sub 4/F- NH/sub 4/NO/sub 3/ solutions, the total dissolution of suainless steel clad fuels in HNO/sub 3/-HF solutions, and the dissolution of stainless steel cladding in dilute H/sub 2/SO/sub 4/. A single material of construction which could be used for a processing complex which would handle all of the low-enrichment fuels concerned was searched for. In the Zirflex Process (NH/sub 4/F-NH/sub 4/NO/sub 3/ ) the 300 series stainless steels, vacuum-melted Hastelloy-F, Carpenter 20, Nio- nel, Haynes 25, and Incoloy 804 have satisfactory corrosion resistance to solutions involved in the dissolution of Zr or Zircaloy claddings. Satisfactory dissolution rates for 304-L stainless steel cladding are obtained in the Niflex Process (1MHNC/sub 3/-2MHF) solutions. The minimum practical fluoride to stainless steel ratio is about five. Among many materials studied, vacuum-melted HastelloyF offers the best corrosion resistance to HNO/sub 3/-HF solutions encountered during decladding. In the Sulfex Process (H/sub 2/SO/sub 4/) dissolution rates for both annealed 304-L and 347 stainless steel in 3 to 3 M H/ sub 2/SO/sub 4/ are from 5 to 10 mils per hour. Vacuum-melted Hastelloy-F and Ni- o-nel show adequate corrosion resistance to the H/sub 2/SO/sub 4/-stainless steel solutions concerned in H/sub 2/SO/sub 4/ decladding. Ouring U or UO/sub 2/ core dissolution in HNO/sub 3/ following decladding, some sulfate (sulfex decladding) or (fluoride zirflex decladding) will be present due to incomplete rinsing or to the presence of solids (UF/sub 4/). Residual sulfate in the concentration range has no significant effect on the corrosion of 304-L stainless steel or vacuum- melted Hastelloy-F by HNC/sub 3/. Fluoride present will increase the corrosion potential but can be effectively complexed by Al. Corrosion rates of 304-L, vacuum-melted Hastelloy-F, and Ni-o-nel in HNO/sub 3/ solutions are not markedly increased by low concentration (0.1 to 0.3M) of ferric nitrate. However, at higher concentrations ( approximately 1 M) corrosion of an intergranular nature is severe. (W. L. H.)

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Pages: 57

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  • Other Information: Orig. Receipt Date: 31-DEC-60

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  • Report No.: HW-61662
  • Grant Number: AT(45-1)-1350
  • DOI: 10.2172/4195211 | External Link
  • Office of Scientific & Technical Information Report Number: 4195211
  • Archival Resource Key: ark:/67531/metadc875561

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  • August 26, 1959

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  • Sept. 21, 2016, 2:29 a.m.

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  • Feb. 20, 2017, 4:15 p.m.

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Maness, R.F. POWER REACTOR FUELS REPROCESSING. PROGRESS REPORT ON CORROSION STUDIES, report, August 26, 1959; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc875561/: accessed September 22, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.