GLASS FORMULATION DEVELOPMENT TO SUPPORT MELTER TESTING TO DEMONSTRATE ENHANCED HIGH LEVEL WASTE THROUGHPUT
Description
The U.S. Department of Energy (DOE) is currently processing high-level waste (HLW) through a Joule-heated melter (JHM) at the Savannah River Site (SRS) and plans to vitrify HLW and Low activity waste (LAW) at the Hanford Site. Over the past few years at the DWPF, work has concentrated on increasing waste throughput. These efforts are continuing with an emphasis on high alumina content feeds. High alumina feeds have presented specific challenges for the JHM technology regarding the ability to increase waste loading yet still maintain product quality and adequate throughput. Alternatively, vitrification technology innovations are also being investigated as a means to increase waste throughput. The Cold Crucible Induction Melter (CCIM) technology affords the opportunity for higher vitrification process temperatures as compared to the current reference JHM technology. Higher process temperatures may allow for higher waste loading and higher melt rate. Glass formulation testing to support melter demonstration testing was recently completed. This testing was specifically aimed at high alumina concentration wastes. Glass composition property models were utilized as a guide for formulation development. Both CCIM and JHM testing will be conducted so glass formulation testing was targeted at both technologies with a goal to significantly increase waste loading without compromising product quality
Availability note (English)
Available from http://sti.srs.gov/fulltext/WSRC-STI-2007-00236.pdf; PURL: https://www.osti.gov/servlets/purl/914554-cwO8vW/Additional details
Identifiers
Publishing Information
- Imprint Pagination
- vp.
- Report number
- WSRC-STI--2007-00236
Conference
- Title
- Scientific Basis for Nuclear Waste Management - Materials Research Society
- Dates
- 16-21 Sep 2007
- Place
- Sheffield (United Kingdom)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 39075470
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CRUCIBLES; GLASS; INDUCTION; MANAGEMENT; PROCESSING; RADIOACTIVE WASTES; SAVANNAH RIVER; TESTING; VITRIFICATION; WASTES
- Descriptors DEC
- MATERIALS; RADIOACTIVE MATERIALS; RIVERS; SURFACE WATERS; WASTES
Optional Information
- Contract/Grant/Project number
- AC09-96SR18500
- Funding organization
- US Department of Energy (United States)