INTERIM STORAGE AND LONG TERM DISPOSAL OF RESEARCH REACTOR SPENT FUEL

Vinson, D

Title: INTERIM STORAGE AND LONG TERM DISPOSAL OF RESEARCH REACTOR SPENT FUEL

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Abstract

Aluminum clad research reactor spent nuclear fuel (SNF) is currently being consolidated in wet storage basins (pools). Approximately 20 metric tons (heavy metal) of aluminum-based spent nuclear fuel (Al-SNF) is being consolidated for treatment, packaging, interim storage, and preparation for ultimate disposal in a geologic repository. The storage and disposal of Al-SNF are subject to requirements that provide for safety and acceptable radionuclide release. The options studied for interim storage of SNF include wet storage and dry storage. Two options have also been studied to develop the technical basis for the qualification and repository disposal of aluminum spent fuel. The two options studied include Direct Disposal and Melt-Dilute treatment. The implementation of these options present relative benefits and challenges. Both the Direct Disposal and the Melt-Dilute treatment options have been developed and their technical viability assessed. Adaptation of the melt-dilute technology for the treatment of spent fuel offers the benefits of converting the spent fuel into a proliferation resistant form and/or significantly reducing the volume of the spent fuel. A Mobile Melt-Dilute system concept has emerged to realize these benefits and a prototype system developed. The application of the melt-dilute technology for the treatment of legacy nuclear materials has beenmore »« less

Authors:: Vinson, D

Publication Date:: Tue Aug 22 00:00:00 EDT 2006

Research Org.:: Savannah River Site (SRS), Aiken, SC (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 891687

Report Number(s):: WSRC-STI-2006-00104
TRN: US0605472

DOE Contract Number:: DE-AC09-96SR18500

Resource Type:: Conference

Resource Relation:: Conference: NA

Country of Publication:: United States

Language:: English

Subject:: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ALUMINIUM; DRY STORAGE; IMPLEMENTATION; METRICS; NUCLEAR FUELS; PACKAGING; PROLIFERATION; RADIOISOTOPES; RESEARCH REACTORS; SAFETY; SPENT FUELS; STORAGE; VIABILITY; WASTE STORAGE; WET STORAGE

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                    Vinson, D. INTERIM STORAGE AND LONG TERM DISPOSAL OF RESEARCH REACTOR SPENT FUEL.  United States: N. p., 2006. 
        Web.

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                    Vinson, D. INTERIM STORAGE AND LONG TERM DISPOSAL OF RESEARCH REACTOR SPENT FUEL.  United States.

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                    Vinson, D. 2006.  
        "INTERIM STORAGE AND LONG TERM DISPOSAL OF RESEARCH REACTOR SPENT FUEL".  United States.  https://www.osti.gov/servlets/purl/891687.

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@article{osti_891687,

  title        = {INTERIM STORAGE AND LONG TERM DISPOSAL OF RESEARCH REACTOR SPENT FUEL},

  author       = {Vinson, D},

  abstractNote = {Aluminum clad research reactor spent nuclear fuel (SNF) is currently being consolidated in wet storage basins (pools). Approximately 20 metric tons (heavy metal) of aluminum-based spent nuclear fuel (Al-SNF) is being consolidated for treatment, packaging, interim storage, and preparation for ultimate disposal in a geologic repository. The storage and disposal of Al-SNF are subject to requirements that provide for safety and acceptable radionuclide release. The options studied for interim storage of SNF include wet storage and dry storage. Two options have also been studied to develop the technical basis for the qualification and repository disposal of aluminum spent fuel. The two options studied include Direct Disposal and Melt-Dilute treatment. The implementation of these options present relative benefits and challenges. Both the Direct Disposal and the Melt-Dilute treatment options have been developed and their technical viability assessed. Adaptation of the melt-dilute technology for the treatment of spent fuel offers the benefits of converting the spent fuel into a proliferation resistant form and/or significantly reducing the volume of the spent fuel. A Mobile Melt-Dilute system concept has emerged to realize these benefits and a prototype system developed. The application of the melt-dilute technology for the treatment of legacy nuclear materials has been evaluated and also offers the promise for the safe disposal of these materials.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/891687},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Tue Aug 22 00:00:00 EDT 2006},

  month        = {Tue Aug 22 00:00:00 EDT 2006}

}

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