Identification of Potential Waste Processing and Waste Form Options for Molten Salt Reactors

Technical Report · Wed Aug 15 00:00:00 EDT 2018

DOI:https://doi.org/10.2172/1543229· OSTI ID:1543229

Riley, Brian J. ^[1]; Mcfarlane, Joanna  ^[2]; DelCul, Guillermo  ^[2]; Vienna, John D. ^[1]; Contescu, Cristian I.  ^[2]; Hay, Laurie M. ^[1]; Savino, A. V. ^[1]; Adkins, Harold E. ^[1]

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1. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

The overall summary of the waste management envelope discussed in this report is represented by the diagram shown in Figure S1. The streams that are included in this discussion include the following from reactor systems in which chlorine-based salts with and without processing and fluorine-based salts with and without processing are being considered: 1) Off-gas streams (e.g., particulates, aerosols, reactive gases, ³H, water, residual halides, N₂, O₂, noble gases); 2) Salt waste streams (e.g., chloride- or fluoride-based); 3) Separated salt streams (e.g., ⁷Li recycle, ³⁷Cl recycle, eutectic salts, fission products); 4) Metal waste streams (e.g., reactor components, plenums); 5) Carbon waste streams (e.g., graphite, SiC); 6) Decommissioning and decontaminating (D&D) waste streams; 7) Operating waste streams

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC05-76RL01830; AC05-00OR22725
• OSTI ID: 1543229
• Report Number(s): ORNL/LTR-2018/907
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES