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Title: Study of melted Synroc doped with simulated high-level waste

Book ·
OSTI ID:572084
;  [1]; ; ; ;  [2]
  1. SIA Radon, Moscow (Russian Federation)
  2. Inst. of Geology of Ore Deposits, Moscow (Russian Federation)

Preparation and characterization of inductively-melted Synroc containing 20 wt% simulated plant Mayak reprocessing waste were performed. The sample bulk composition was as follows, (in wt.%): 55.4 TiO{sub 2}, 15.8 ZrO{sub 2}; 7.5 CaO; 7.4 BaO; 4.3 Al{sub 2}O{sub 3}; 2.0 MnO; 1.8 SiO{sub 2}; 0.7 Na{sub 2}O; 1.9 K{sub 2}O; 0.5 Ce{sub 2}O{sub 3}; 1.0 UO{sub 2}; 0.9 NiO; 0.6 Cr{sub 2}O{sub 3}, and 0.2 FeO. The sample was produced by melting in air at 1,550--1,600 C under barometric pressure. It is composed of a few crystalline phases and a minor glass phase. Most of the phases (hollandite, zirconolite, perovskite and rutile) are similar to the analogous phases found in the other Synroc formulations. An additional phase with average composition, wt.%: 59.8 TiO{sub 2}; 15.6 CaO; 7.0 UO{sub 2}; 5.6 ZrO{sub 2}; 4.7 MnO; 4.1 Ce{sub 2}O{sub 3}, and 1.8 Al{sub 2}O{sub 3} was found. Some elements (Ba, Si, Ni, K, Na, Fe) were present in the phase in negligible quantities. Its formula (Ca{sub 2.65}U{sub 0.3}Ce{sub 0.2})(Ti{sub 7.3}Mn{sub 0.6}Zr{sub 0.4}Al{sub 0.3})O{sub 20.0} is rather close to a rare mineral uhligite--Ca{sub 3}(Ti,Zr,Al){sub 9}O{sub 20}. Another possible counterpart of the phase is murataite-like mineral previously described in tailored ceramic designed for Savannah River Plant wastes fixation. This phase as well as zirconolite are the major host for U in the sample. Preliminary data on the material leachability in water at 350 C and 50 MPa have been obtained. Uranium contents in the solution were about 1 ppb and close to the uranium dioxide solubility in deionized water under the same P-T conditions.

OSTI ID:
572084
Report Number(s):
CONF-961202-; TRN: 98:003713
Resource Relation:
Conference: 1996 Fall meeting of the Materials Research Society (MRS), Boston, MA (United States), 2-6 Dec 1996; Other Information: PBD: 1997; Related Information: Is Part Of Scientific basis for nuclear waste management XX; Gray, W.J. [ed.] [Pacific Northwest National Lab., Richland, WA (United States)]; Triay, I.R. [ed.] [Los Alamos National Lab., NM (United States)]; PB: 1389 p.; Materials Research Society symposium proceedings, Volume 465
Country of Publication:
United States
Language:
English