Carbon Steel and Magnesium Oxide Dissolution for H-Canyon Process Applications

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Description

H Area Operations is planning to process plutonium-contaminated uranium metal scrap in its efforts to de-inventory excess nuclear materials. The Savannah River Technology Center (SRTC) performed flowsheet development to support the decision to process the scrap in H-Canyon using 2M nitric acid (HNO3) / 0.025M potassium fluoride (KF) and 2 g/L boron. The scrap will be charged to the H-Canyon dissolver via a stainless steel charging bundle with a carbon steel end cap that must dissolve in an appropriate time frame. Experimental work was performed with a range of potential materials to be used to fabricate the bundle end cap. ... continued below

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PIERCE, RA April 12, 2004.

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Description

H Area Operations is planning to process plutonium-contaminated uranium metal scrap in its efforts to de-inventory excess nuclear materials. The Savannah River Technology Center (SRTC) performed flowsheet development to support the decision to process the scrap in H-Canyon using 2M nitric acid (HNO3) / 0.025M potassium fluoride (KF) and 2 g/L boron. The scrap will be charged to the H-Canyon dissolver via a stainless steel charging bundle with a carbon steel end cap that must dissolve in an appropriate time frame. Experimental work was performed with a range of potential materials to be used to fabricate the bundle end cap. Testing was conducted with samples of metal plate, wire, cans, rods, and rivets to assess their dissolution characteristics in 2M HNO3/ 0.025M KF and 2 g/L boron. Experiments also measured the amount of hydrogen gas generated during carbon steel dissolution using the above dissolver solution. Each material type and its associated dissolution characteristic relate to specific bundle end cap designs being considered. Supplemental studies were conducted to evaluate the behavior and effect of magnesium oxide (MgO) sand on dissolution of uranium metal in 2M HNO3/ 0.025M KF and 2 g/L boron. The potential exists for a small quantity of MgO to be introduced into the dissolution flowsheet due to the use of MgO sand to extinguish uranium metal fires.

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  • Other Information: PBD: 12 Apr 2004

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  • Report No.: WSRC-TR-2004-00035
  • Grant Number: AC09-96SR18500
  • DOI: 10.2172/822944 | External Link
  • Office of Scientific & Technical Information Report Number: 822944
  • Archival Resource Key: ark:/67531/metadc779051

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  • April 12, 2004

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  • Dec. 3, 2015, 9:30 a.m.

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  • May 5, 2016, 3:41 p.m.

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PIERCE, RA. Carbon Steel and Magnesium Oxide Dissolution for H-Canyon Process Applications, report, April 12, 2004; South Carolina. (digital.library.unt.edu/ark:/67531/metadc779051/: accessed September 22, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.