Saltstone: cement-based waste form for disposal of Savannah River Plant low-level radioactive salt waste
Description
Defense waste processing at the Savannah River Plant will include decontamination and disposal of approximately 400 million liters of waste containing NaNO3, NaOH, Na2SO4, and NaNO2. After decontamination, the salt solution is classified as low-level waste. A cement-based waste form, saltstone, has been designed for disposal of Savannah River Plant low-level radioactive salt waste. Bulk properties of this material have been tailored with respect to salt leach rate, permeability, and compressive strength. Microstructure and mineralogy of leached and unleached specimens were characterized by SEM and x-ray diffraction analyses. The disposal system for the DWPF salt waste includes reconstitution of the crystallized salt as a solution containing 32 wt % solids. This solution will be decontaminated to remove 137Cs and 90Sr and then stabilized in a cement-based waste form. Laboratory and field tests indicate that this stabilization process greatly reduces the mobility of all of the waste constitutents in the surface and near surface environment. Engineered trenches for subsurface burial of the saltstone have been designed to ensure compatibility between the waste form and the environment. The total disposal system, saltstone-trench- surrounding soil, has been designed to contain radionuclides, Cr, and Hg by both physical encapsulation and chemical fixation mechanisms. Physical encapsulation of the salts is the mechanism employed for controlling N and OH releases. In this way, final disposal of the SRP low-level waste can be achieved and the quality of the ground water at the perimeter of the disposal site meets EPA drinking water standards
Additional details
Publishing Information
- Imprint Title
- Fifth DOE environmental protection information meeting: proceedings. Volume 2
- Journal Page Range
- p. 419-435.
- Report number
- CONF-841187--Vol.2
Conference
- Title
- 5. DOE environmental protection information meeting.
- Dates
- 6-8 Nov 1984.
- Place
- Albuquerque, NM (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18029037
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S58: GEOSCIENCES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CESIUM 137; DECONTAMINATION; GROUND DISPOSAL; GROUND WATER; LEACHING; LOW-LEVEL RADIOACTIVE WASTES; PHYSICAL PROPERTIES; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE PROCESSING; SAVANNAH RIVER PLANT; STRONTIUM 90; WATER POLLUTION; X-RAY DIFFRACTION
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CESIUM ISOTOPES; CLEANING; COHERENT SCATTERING; DIFFRACTION; DISSOLUTION; EVEN-EVEN NUCLEI; HYDROGEN COMPOUNDS; INTERMEDIATE MASS NUCLEI; ISOTOPES; MANAGEMENT; MATERIALS; NATIONAL ORGANIZATIONS; NUCLEI; ODD-EVEN NUCLEI; OXYGEN COMPOUNDS; POLAR SOLVENTS; POLLUTION; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; RADIOISOTOPES; SCATTERING; SEPARATION PROCESSES; SOLVENTS; STRONTIUM ISOTOPES; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WASTE DISPOSAL; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; WATER; YEARS LIVING RADIOISOTOPES