Plutonium immobilization in glass and ceramics

Conference · Wed May 01 04:00:00 EDT 1996

OSTI ID:420659

Knecht, D A ^[1]; Murphy, W M ^[2]

---

1. Lockheed Martin Idaho Technologies, Idaho Falls (United States)
2. Southwest Research Institute, San Antonio, TX (United States)

The Materials Research Society Nineteenth Annual Symposium on the Scientific Basis for Nuclear Waste Management was held in Boston on November 27 to December 1, 1995. Over 150 papers were presented at the Symposium dealing with all aspects of nuclear waste management and disposal. Fourteen oral sessions and on poster session included a Plenary session on surplus plutonium dispositioning and waste forms. The proceedings, to be published in April, 1996, will provide a highly respected, referred compilation of the state of scientific development in the field of nuclear waste management. This paper provides a brief overview of the selected Symposium papers that are applicable to plutonium immobilization and plutonium waste form performance. Waste forms that were described at the Symposium cover most of the candidate Pu immobilization options under consideration, including borosilicate glass with a melting temperature of 1150 {degrees}C, a higher temperature (1450 {degrees}C) lanthanide glass, single phase ceramics, multi-phase ceramics, and multi-phase crystal-glass composites (glass-ceramics or slags). These Symposium papers selected for this overview provide the current status of the technology in these areas and give references to the relevant literature.

• Research Organization: USDOE, Washington, DC (United States)
• OSTI ID: 420659
• Report Number(s): CONF-951259--; ON: DE96011798
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
BOROSILICATE GLASS
CERAMICS
LEACHING
MELTING
PERFORMANCE
PLUTONIUM
SLAGS
STABILIZATION
WASTE FORMS