Evaluation of neutron absorbers for the melt-dilute treatment of aluminum-based spent fuel

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Aluminum-based spent nuclear fuel (Al-SNF) from foreign and domestic research reactors is being consolidated at the Savannah River Site (SRS) for ultimate disposal in the Mined Geologic Disposal System (MGDS). Most of the aluminum-based fuel material contains highly enriched uranium (HEU) (greater than 20 percent {sup 235}U), which poses a proliferation risk and challenges the preclusion of criticality events for disposal periods exceeding 10,000 years.

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Vinson, D.W. March 31, 2000.

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Description

Aluminum-based spent nuclear fuel (Al-SNF) from foreign and domestic research reactors is being consolidated at the Savannah River Site (SRS) for ultimate disposal in the Mined Geologic Disposal System (MGDS). Most of the aluminum-based fuel material contains highly enriched uranium (HEU) (greater than 20 percent {sup 235}U), which poses a proliferation risk and challenges the preclusion of criticality events for disposal periods exceeding 10,000 years.

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vp.

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  • American Nuclear Society 2000 Annual Meeting, San Diego, CA (US), 06/04/2000--06/08/2000; Other Information: PBD: 31 Mar 2000

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  • Report No.: WSRC-MS-2000-00181
  • Grant Number: AC09-96SR18500
  • Office of Scientific & Technical Information Report Number: 753550
  • Archival Resource Key: ark:/67531/metadc703626

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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Creation Date

  • March 31, 2000

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • May 5, 2016, 6 p.m.

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Vinson, D.W. Evaluation of neutron absorbers for the melt-dilute treatment of aluminum-based spent fuel, article, March 31, 2000; South Carolina. (digital.library.unt.edu/ark:/67531/metadc703626/: accessed January 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.