REDUCTION CAPACITY OF SALTSTONE AND SALTSTONE COMPONENTS

Roberts, K. ; Kaplan, D.

关键词: AR FACILITIES;    REDUCING AGENTS;    SLAGS;    FLY ASH;    NEPTUNIUM;    PLUTONIUM;    PORTLAND CEMENT;    TECHNETIUM;    REDUCTION;    RADIOACTIVE WASTE DISPOSAL;   

DOI  :  10.2172/969345
RP-ID  :  SRNL-STI-2009-00637
PID  :  OSTI ID: 969345
Others  :  TRN: US1000277

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

The duration that saltstone retains its ability to immobilize some key radionuclides, such as technetium (Tc), plutonium (Pu), and neptunium (Np), depends on its capacity to maintain a low redox status (or low oxidation state). The reduction capacity is a measure of the mass of reductants present in the saltstone; the reductants are the active ingredients that immobilize Tc, Pu, and Np. Once reductants are exhausted, the saltstone loses its ability to immobilize these radionuclides. The reduction capacity values reported here are based on the Ce(IV)/Fe(II) system. The Portland cement (198 {micro}eq/g) and especially the fly ash (299 {micro}eq/g) had a measurable amount of reduction capacity, but the blast furnace slag (820 {micro}eq/g) not surprisingly accounted for most of the reduction capacity. The blast furnace slag contains ferrous iron and sulfides which are strong reducing and precipitating species for a large number of solids. Three saltstone samples containing 45% slag or one sample containing 90% slag had essentially the same reduction capacity as pure slag. There appears to be some critical concentration between 10% and 45% slag in the Saltstone formulation that is needed to create the maximum reduction capacity. Values from this work supported those previously reported, namely that the reduction capacity of SRS saltstone is about 820 {micro}eq/g; this value is recommended for estimating the longevity that the Saltstone Disposal Facility will retain its ability to immobilize radionuclides.