Overview of advanced technologies for stabilization of {sup 238}Pu-contaminated waste

Journal Article · Thu Jan 15 04:00:00 EST 1998 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.54754· OSTI ID:21179664

Ramsey, Kevin B; Foltyn, Elizabeth M; Heslop, J Mark ^[1]

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1. Los Alamos National Laboratory, P.O. Box 1663, MS-E502, Los Alamos, New Mexico 87545 (United States)

This paper presents an overview of potential technologies for stabilization of {sup 238}Pu-contaminated waste. Los Alamos National Laboratory (LANL) has processed {sup 238}PuO{sub 2} fuel into heat sources for space and terrestrial uses for the past several decades. The 88-year half-life of {sup 238}Pu and thermal power of approximately 0.6 watts/gram make this isotope ideal for missions requiring many years of dependable service in inaccessible locations. However, the same characteristic which makes {sup 238}Pu attractive for heat source applications, the high Curie content (17 Ci/gram versus 0.06 Ci/gram for {sup 239}Pu), makes disposal of {sup 238}Pu-contaminated waste difficult. Specifically, the thermal load limit on drums destined for transport to the Waste Isolation Pilot Plant (WIPP), 0.23 gram per drum for combustible waste, is impossible to meet for nearly all {sup 238}Pu-contaminated glovebox waste. Use of advanced waste treatment technologies including Molten Salt Oxidation (MSO) and aqueous chemical separation will eliminate the combustible matrix from {sup 238}Pu-contaminated waste and recover kilogram quantities of {sup 238}PuO{sub 2} from the waste stream. A conceptual design of these advanced waste treatment technologies will be presented.

• OSTI ID: 21179664
• Journal Information: AIP Conference Proceedings, Journal Name: AIP Conference Proceedings Journal Issue: 1 Vol. 420; ISSN APCPCS; ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
DESIGN
LANL
MOLTEN SALTS
NESDPS Office of Nuclear Energy Space and Defense Power Systems
OXIDATION
PLUTONIUM 238
PLUTONIUM 239
PLUTONIUM COMPOUNDS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
RADIOISOTOPE HEAT SOURCES
THERMOELECTRIC GENERATORS
WIPP