Onsite Transfer of Plutonium Solutions with the Upgraded LR-56S Cask

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With the end of the cold war, quantities of plutonium (Pu) solutions remained in the nuclear material production complex at the Savannah River Site (SRS) These solutions, now surplus to the nuclear weapons program, have resulted in significant health, safety, and environmental vulnerabilities at the Site and require stabilization. The site plan for stabilizing the solutions is to transfer the material from H canyon storage to F canyon for processing and disposition. The proposed onsite transfer at SRS raised both regulatory and safety concerns since the material is prohibited for offsite shipment by the U. S. Hazardous Materials, Regulations (HMR). ... continued below

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8 p. p.

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Gromada, R. J. July 1998.

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  • Gromada, R. J. Westinghouse Savannah River Company, AIKEN, SC (United States)

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Description

With the end of the cold war, quantities of plutonium (Pu) solutions remained in the nuclear material production complex at the Savannah River Site (SRS) These solutions, now surplus to the nuclear weapons program, have resulted in significant health, safety, and environmental vulnerabilities at the Site and require stabilization. The site plan for stabilizing the solutions is to transfer the material from H canyon storage to F canyon for processing and disposition. The proposed onsite transfer at SRS raised both regulatory and safety concerns since the material is prohibited for offsite shipment by the U. S. Hazardous Materials, Regulations (HMR). However, an onsite transfer may be approved if it can be demonstrated that proper safety, health, and environmental protection are maintained. The difficulty of performing such a task is the awareness that an onsite transfer of Pu solutions had never been approved in the U. S. To understand the difficulties associated with the planning the transfer, this paper will describe the methodology and compliance process that SRS used to demonstrate that the transfer is safe and that the public is adequately protected. The cask selected for the transfer will be described as well as the process used to confirm that the plutonium solutions are safely contained by the cask design. Additionally, the administrative controls and cask modifications mandated by the content form are also presented.

Physical Description

8 p. p.

Notes

INIS; OSTI as DE98054561

Source

  • 1998 ASME/JSME joint pressure vessel and piping (PVP) conference, San Diego, CA (United States), 26-30 Jul 1998

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  • Other: DE98054561
  • Report No.: WSRC-MS--98-00320
  • Report No.: CONF-980708--
  • Grant Number: AC09-89SR18035
  • Office of Scientific & Technical Information Report Number: 656905
  • Archival Resource Key: ark:/67531/metadc710943

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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.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • July 1998

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • Feb. 10, 2016, 2:21 p.m.

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Gromada, R. J. Onsite Transfer of Plutonium Solutions with the Upgraded LR-56S Cask, article, July 1998; Aiken, South Carolina. (digital.library.unt.edu/ark:/67531/metadc710943/: accessed August 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.