Long-term high-level-waste technology. Composite quarterly technical report, April-June 1982
- comp.
This composite quarterly technical report summarizes work performed at participating sites to immobilize high-level radioactive wastes. ENICO is preparing a document to recommend strategy for the long-term management of high-level wastes generated at ICPP. Post-closure risks are compared for a borosilicate reference waste form and an alternative waste form for defense high-level waste at SRP. A Liquid Solidification Study at Hanford showed that solidification and disposal of non-TRU Hanford defense residual liquors into single-shell tanks is technically feasible and economically advantageous over double-shell tank disposal. In-tank drying and consolidation of wet synthetic salt is being demonstrated at Rockwell Hanford Operation (RHO) with a microwave drying system. Four-month corrosion tests of Hanford double-shell slurry on carbon-steel tanks were concluded. A series of experiments were completed that qualified the use of neutron activation analysis and radioactive tracers for measuring leach rates from simulated waste glasses. Glass frits 127 and 532 are being investigated for vitrification of new blends of ICPP calcined waste which have high sodium contents. The composition of the borosilicate glass waste form for SRP has been optimized. Development and evaluation of tailored cementitious waste hosts for Hanford TRU waste sludges is under way. SYNROC C samples containing both PW-4b- and PW-7a-type wastes were prepared and tested at LLNL. Static leach tests were completed at Rockwell Energy Systems Group (RES) on the RSC-S29 ceramic waste form for SRP defense waste. A ceramic waste form was designed at RES specifically for acid waste streams from processing of reactor fuel. Development work on the Large-Scale Glass Melter continued at SRL. Studies of the potential for steam explosions in the Defense Waste Processing Facility melter are under way at SRL.
- Research Organization:
- Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab.
- DOE Contract Number:
- AC09-76SR00001
- OSTI ID:
- 6900521
- Report Number(s):
- DP-82-157-2; ON: DE83003830
- Resource Relation:
- Other Information: Portions of document are illegible. Printed copy available until stock is exhausted
- Country of Publication:
- United States
- Language:
- English
Similar Records
Long-term high-level waste technology. Composite quarterly technical report: April-June 1981
Borosilicate glass as a matrix for immobilization of SRP high-level waste
Related Subjects
36 MATERIALS SCIENCE
CARBON STEELS
CORROSION
RADIOACTIVE WASTE PROCESSING
HIGH-LEVEL RADIOACTIVE WASTES
RESEARCH PROGRAMS
SOLIDIFICATION
BOROSILICATE GLASS
CALCINED WASTES
CERAMIC MELTERS
LEACHING
SYNROC PROCESS
VITRIFICATION
ALLOYS
CHEMICAL REACTIONS
DISSOLUTION
ELECTRIC FURNACES
FURNACES
GLASS
IRON ALLOYS
IRON BASE ALLOYS
MANAGEMENT
MATERIALS
PHASE TRANSFORMATIONS
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
SEPARATION PROCESSES
STEELS
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
052001* - Nuclear Fuels- Waste Processing
360105 - Metals & Alloys- Corrosion & Erosion