Geochemical engineering of low-level radioactive waste in cementitious environments

Journal Article · Sun Dec 31 04:00:00 EST 1995 · Waste Management

DOI:https://doi.org/10.1016/0956-053X(95)00028-X· OSTI ID:153540

Brady, P V; Kozak, M W ^[1]

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1. Sandia National Lab., Albuquerque, NM (United States)

Significantly reduced releases of radionuclides from low-level radioactive waste disposal facilities may be achieved by passively engineering the geochemical environment in and immediately adjacent to shallow land burial sites. Mineral growth and adsorption onto cementitious waste forms, casks, and backfills is calculated to minimize the transport of {sup 234,238}U, {sup 241}Pu, {sup 241}Am, {sup 232}Th, {sup 59, 63}Ni and {sup 14}C. Reductive adsorption of Tc to Fe(II)-rich minerals may be engineered by emplacing a fine-grained mafic (basalt, serpentinite, scrap iron) blanket of aggregate below and around the LLRW repository. {sup 90}Sr and {sup 137}Cs transport into the biosphere may also be retarded due to adsorption on cementitious material, through scavenging by the Fe-oxyhydroxide weathering products of the mafic blanket, and by dilution.

• OSTI ID: 153540
• Journal Information: Waste Management, Journal Name: Waste Management Journal Issue: 4 Vol. 15; ISSN WAMAE2; ISSN 0956-053X
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
ADSORPTION
AMERICIUM 241
CARBON 14
CEMENTS
CESIUM 137
DESIGN
ENVIRONMENTAL TRANSPORT
GEOCHEMISTRY
GROUND DISPOSAL
LOW-LEVEL RADIOACTIVE WASTES
NICKEL 59
NICKEL 63
OPTIMIZATION
PLUTONIUM 241
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE FACILITIES
SORPTIVE PROPERTIES
STRONTIUM 90
TECHNETIUM
THORIUM 232
URANIUM 234
URANIUM 238