Properties of radioactive wastes and waste containers. Status report, October 1980-September 1981
Licensing of near surface low-level radioactive waste disposal sites and waste forms/containers requires the ability to predict the dispersibility of radionuclides from waste forms and waste containers disposed in burial sites. Basic concerns in licensing radioactive waste forms and containers are their dimensional stability and the potential for migration of the radionuclides enclosed therein in a near- and long-term predictable fashion. To assess these concerns, a data base is needed for evaluating the acceptability of solidified low-level radioactive waste packages for disposal. Furthermore, the need to develop test procedures and methodologies exists to enable the prediction of long-term performance of waste forms based on short-term laboratory tests. The objectives of the research program at BNL are to provide an improved understanding of phenomena, testing methodology and data. This improves the NRC's capability to predict low-level waste isolation performance, and to provide a better technical basis for regulatory standards. The areas addressed to meet these objectives during the 1981 fiscal year were: leachability and compressive strength of boric acid waste in Portland III cement. The tracers used for the study were /sup 137/Cs, /sup 85/Sr, and /sup 60/Co; leachability of /sup 137/Cs, /sup 85/Sr, and /sup 60/Co from organic ion exchange resin/Portland III and Lumnite cements; displacement of /sup 137/Cs, /sup 85/Sr, and /sup 60/Co from organic ion exchange resins upon mixing with Portland II and Lumnite cements; leachability of organic ion exchange resins/Bitumen composites using resins in the H/sup +/, Na/sup +/, Cs/sup +/, Sr/sup +2/, and SO/sub 4//sup -2/ forms, and /sup 137/Cs and /sup 85/Sr tracers; correlation of /sup 137/Cs leachability from small-scale (laboratory) samples to large-scale waste forms; and hydrostatic testing of DOT 17H drums. 32 refs., 61 figs., 33 tabs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5054574
- Report Number(s):
- NUREG/CR-2617; BNL-NUREG-51515; ON: TI86000977
- Country of Publication:
- United States
- Language:
- English
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ALKALI METAL ISOTOPES
ALKALINE EARTH ISOTOPES
ALLOYS
BENCH-SCALE EXPERIMENTS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BITUMENS
BORIC ACID
BUILDING MATERIALS
CARBON STEELS
CEMENTS
CESIUM 137
CESIUM ISOTOPES
COBALT 60
COBALT ISOTOPES
COMPOSITE MATERIALS
COMPRESSION STRENGTH
CONTAINERS
DATA
DAYS LIVING RADIOISOTOPES
DISSOLUTION
ELECTRON CAPTURE RADIOISOTOPES
EVEN-ODD NUCLEI
EXPERIMENTAL DATA
HOURS LIVING RADIOISOTOPES
HYDROGEN COMPOUNDS
INFORMATION
INORGANIC ACIDS
INTERMEDIATE MASS NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
ION EXCHANGE MATERIALS
IRON ALLOYS
IRON BASE ALLOYS
ISOMERIC TRANSITION ISOTOPES
ISOTOPE APPLICATIONS
ISOTOPES
LEACHING
LOW-LEVEL RADIOACTIVE WASTES
MANAGEMENT
MATERIALS
MECHANICAL PROPERTIES
MINUTES LIVING RADIOISOTOPES
NUCLEI
NUMERICAL DATA
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
ORGANIC COMPOUNDS
ORGANIC POLYMERS
OTHER ORGANIC COMPOUNDS
PACKAGING
PETROCHEMICALS
PETROLEUM PRODUCTS
POLYMERS
PORTLAND CEMENT
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTES
RADIOISOTOPES
RESINS
SEPARATION PROCESSES
SOLID WASTES
STEELS
STRONTIUM 85
STRONTIUM ISOTOPES
TAR
TESTING
TRACER TECHNIQUES
WASTE DISPOSAL
WASTE FORMS
WASTE MANAGEMENT
WASTES
YEARS LIVING RADIOISOTOPES