Published August 17, 2007 | Version v1
Report

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

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)