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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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DOE-EM awards $37.5M to Vanderbilt University for nuclear cleanup support
The Department of Energy’s Office of Environmental Management announced on January 16 that it has awarded a noncompetitive financial assistance agreement worth $37.5 million to Vanderbilt University in Nashville, Tenn., to aid the department’s mission of cleaning up legacy nuclear waste.
D. G. Jacobs
Nuclear Science and Engineering | Volume 12 | Number 2 | February 1962 | Pages 285-292
Technical Paper | doi.org/10.13182/NSE62-A26069
Articles are hosted by Taylor and Francis Online.
Although direct disposal to the ground has provided an effective means for the disposal of low- and intermediate-level waste streams, there is concern regarding the lack of control of the radionuclides once the wastes have been discharged to the ground. The use of a mineral-filled column is regarded as an inexpensive, yet efficient, alternative method for waste decontamination. For this purpose the cesium-exchange properties of various grades of commercially available vermiculite were investigated and compared to other natural ion-exchange materials. Elucidation of the reaction mechanism has led to improvement of the cesium-sorptive properties, either by potassium treatment or heat treatment of the vermiculite or by addition of potassium to the waste stream. Studies of the kinetics and the thermodynamics of the exchange reaction permit extrapolation of the data for consideration of the extended use of vermiculite columns for decontaminating other waste streams. Data obtained from bench-scale and field-scale (10-ft long, 2-in. i.d.) column studies compare closely with those obtained by slurry studies. The breakthrough curves obtained were sufficiently steep to indicate that the partial cesium-sorptive capacity of a vermiculite column would be completely utilized if two columns were operated in series. A column 10 ft long and 10 ft in diameter filled with Na-treated vermiculite is estimated to be capable of decontaminating more than 5 × 105 gal of ORNL intermediate-level waste. Larger volumes of waste streams having lower concentrations of stable salts could be decontamined with respect to cesium and strontium.