Evaluation of the TiO2 Limit for DWPF Glass

LORIER, TROY

Savannah River Site (S.C.)

关键词: 12 Management Of Radioactive Wastes, And Non-Radioactive Wastes From Nuclear Facilities;    Waste Forms;    Titanium Oxides;    Radioactive Waste Processing;    Solubility;   

DOI  :  10.2172/822650
RP-ID  :  WSRC-TR-2003-00396
RP-ID  :  AC09-96SR18500
RP-ID  :  822650

美国|英语

来源: UNT Digital Library

【 摘 要 】

The titanium dioxide (TiO2) solubility limit for Defense Waste Processing Facility (DWPF) glasses evaluated in this report. Based on the analyses of existing data, the solubility limit can be raised from 1 wt percent to 2 wt percent. This work has been prepared to address technical issues discussed in Technical Task Request SPTTR-2003-00004 (Lilliston, 2003) and in accordance with the Task Technical and Quality Assurance Plan (Lorier, 2003).