Selecting a Plutonium Vitrification Process

Conference · Tue Dec 12 00:00:00 EST 1995

OSTI ID:420663

Jouan, Antoine ^[1]

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1. Commissariat a l'Energie Atomique (CEA), Grenoble (France). Centre d'Etudes Nucleaires

Vitrification of plutonium is one means of mitigating its potential danger. This option is technically feasible, even if it is not the solution advocated in France. Two situations are possible, depending on whether or not the glass matrix also contains fission products; concentrations of up to 15% should be achievable for plutonium alone, whereas the upper limit is 3% in the presence of fission products. The French continuous vitrification process appears to be particularly suitable for plutonium vitrification: its capacity is compatible with the required throughout, and the compact dimensions of the process equipment prevent a criticality hazard. Preprocessing of plutonium metal, to convert it to PuO₂ or to a nitric acid solution, may prove advantageous or even necessary depending on whether a dry or wet process is adopted. The process may involve a single step (vitrification of Pu or PuO₂ mixed with glass frit) or may include a prior calcination step - notably if the plutonium is to be incorporated into a fission product glass. It is important to weigh the advantages and drawbacks of all the possible options in terms of feasibility, safety and cost-effectiveness.

• Research Organization: Commissariat a l'Energie Atomique (CEA), Grenoble (France). Centre d'Etudes Nucleaires
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• OSTI ID: 420663
• Report Number(s): CONF-951259, 359-365; ON: DE96011798; TRN: 97:002146
• Resource Relation: Conference: Plutonium Stabilization and Immobilization Workshop, Immobilization Facilities, Washington, DC (United States), 12-14 Dec 1995; Other Information: PBD: May 1996; Related Information: Is Part Of US Department of Energy Plutonium Stabilization and Immobilization Workshop, December 12-14, 1995: Final proceedings; PB: 474 p.
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
PLUTONIUM
VITRIFICATION
STABILIZATION
RADIOACTIVE WASTE PROCESSING
WASTE FORMS
GLASS
CALCINATION
CRITICALITY
FISSION PRODUCTS
PLUTONIUM OXIDES
EVAPORATION
CERAMIC MELTERS
Nuclear Criticality Safety Program (NCSP)
Glass Matrix
Fission Product Glass
Nitric Acid Solution
Criticality Hazard
Minor Actinides
Radioactive Toxicity
Cold Crucible Melting Principle
Mixed Oxide (MOX) Fuel
COGEMA