Americium/curium bushing melter drain tests

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Description

Americium and curium were produced in the past at the Savannah River Site (SRS) for research, medical, and radiological applications. They have been stored in a nitric acid solution in an SRS reprocessing facility for a number of years. Vitrification of the americium/curium (Am/Cm) solution will allow the material to be safely stored or transported to the DOE Oak Ridge Reservation. Oak Ridge is responsible for marketing radionuclides for research and medical applications. The bushing melter technology being used in the Am/Cm vitrification research work is also under consideration for the stabilization of other actinides such as neptunium and plutonium. ... continued below

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11 p.

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Smith, M.E.; Hardy, B.J. & Smith, M.E. July 1, 1997.

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Description

Americium and curium were produced in the past at the Savannah River Site (SRS) for research, medical, and radiological applications. They have been stored in a nitric acid solution in an SRS reprocessing facility for a number of years. Vitrification of the americium/curium (Am/Cm) solution will allow the material to be safely stored or transported to the DOE Oak Ridge Reservation. Oak Ridge is responsible for marketing radionuclides for research and medical applications. The bushing melter technology being used in the Am/Cm vitrification research work is also under consideration for the stabilization of other actinides such as neptunium and plutonium. A series of melter drain tests were conducted at the Savannah River Technology Center to determine the relationship between the drain tube assembly operating variables and the resulting pour initiation times, glass flowrates, drain tube temperatures, and stop pour times. Performance criteria such as ability to start and stop pours in a controlled manner were also evaluated. The tests were also intended to provide support of oil modeling of drain tube performance predictions and thermal modeling of the drain tube and drain tube heater assembly. These drain tests were instrumental in the design of subsequent melter drain tube and drain tube heaters for the Am/Cm bushing melter, and therefore in the success of the Am/Cm vitrification and plutonium immobilization programs.

Physical Description

11 p.

Notes

INIS; OSTI as DE97060224

Source

  • 21. annual actinide separations conference, Charleston, SC (United States), 23-26 Jun 1997

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  • Other: DE97060224
  • Report No.: WSRC-MS--97-0168
  • Report No.: CONF-9706124--2
  • Grant Number: AC09-89SR18035
  • Office of Scientific & Technical Information Report Number: 503495
  • Archival Resource Key: ark:/67531/metadc690741

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  • July 1, 1997

Added to The UNT Digital Library

  • Aug. 14, 2015, 8:43 a.m.

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  • Feb. 9, 2016, 4:38 p.m.

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Smith, M.E.; Hardy, B.J. & Smith, M.E. Americium/curium bushing melter drain tests, article, July 1, 1997; Aiken, South Carolina. (digital.library.unt.edu/ark:/67531/metadc690741/: accessed August 20, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.