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Evaluation of the U.S. Department of Energy's Alternatives for the Removal and Disposition of Molten Salt Reactor Experiment Fluoride Salts (1997) / Chapter Skim
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7 Strategic Alternatives
Pages 65-71

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From page 65...
... Continue to store the MSRE fuel and flush salts in their respective drain tanks, but implement and operate enhancements to control reactive gases, prevent nuclear criticality, and contain radioactive materials. DISPOSAL OF ALL KEY CONTAMINANTS IN TTIE FEDERAL REPOSITORY Alternative 3: Dispose of the Salt, Including Uranium, in the Federal Repository.
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From page 66...
... DISPOSAL OF KEY CONTAMINANTS IN THE SALT RESIDUE IN THE WASTE ISOLATION PILOT PLANT (WIPP) Alternative 4: Transfer the Uranium to the Materials Disposition Program and Dispose of the Salt Resistive in WIPP.
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From page 67...
... Remove the MSRE fuel and flush salts from their drain tanks. Separate the uranium from the salts using fluoride volatility or another process.
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From page 68...
... Remove the MSRE Mel and flush salts from their drain tanks. Separate the uranium from the salts using fluoride volatility or another process.
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From page 69...
... Alternative 7e: Transfer the Uranium to the MDP, Construct a Salt Conversion Facility at ORNT, Convert the Salt Resiciz~es to Glass or Phosphate Waste Forms, and Store at ORAL. RATIONALE FOR REJECTING THE FIRST SIX ALTERNATIVES Alternatives ~ and 2 are not attractive as permanent solutions because the drain tanks lie below the water table (creating a criticality hazard)
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From page 70...
... Waiting for a better definition of the regulatory and technical issues involved in the acceptability of a waste form for ultimate disposal is not, in the panel's judgment, a satisfactory decision at this time, given the known and anticipated hazards of the MSRE. The panel notes that determination of the ultimate geologic waste disposal system is not essential to the selection of a process to be used in the cleanup of the Mel and flush salt tanks, although the process chosen will affect waste disposal costs.
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From page 71...
... It appears feasible to isolate the uranium from the solvent salt and to convert both of these fractions to stabilized materials suitable for safe and secure interim storage on-site. Of the on-site interim storage possibilities, combining the MSRE mixture of 232U and 233U with existing inventories of 233U in the MDP program may be undesirable due to the containment and measurement challenges created by the gaseous daughters of 232U (see Appendix C)
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Key Terms

  • drain tanks
  • interim storage
  • salt residue
  • flush salts
  • msre fuel

  • waste form
  • key contaminants
  • disposition program
  • materials disposition
  • issues involved

  • radioactive materials
  • future disposition
  • msre mel
  • repository alternative
  • development facility

  • radiochemical development
  • metal waste
  • waste storage
  • respective drain
  • ultimate disposal

  • waste forms
  • storage alternative
  • salt medium
  • cleanup project
  • gaseous daughters

  • realistic objective
  • technical process
  • prevent nuclear
  • glass logs
  • pilot plant


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