ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Latest News
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
T. Sampat Sridhar, Ahmad G. Solomah
Nuclear Technology | Volume 85 | Number 1 | April 1989 | Pages 89-97
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT89-A34230
Articles are hosted by Taylor and Francis Online.
A process has been developed to immobilize the uranium-rich high-level radioactive waste generated from the reprocessing of CANDU spent fuel using the amine process. The calcination technology developed in the Process Development Section at the Whiteshell Nuclear Research Establishment has been used to demonstrate this process. Simulated liquid waste and SYN-ROC additives were denitrated thermochemically in a continuous operation using the Whiteshell Roto-Spray Calciner. Technically dense (≥95% theoretical density) samples of SYNROC-FA crystalline ceramic waste form containing ∼50 wt% simulated amine process waste were prepared by pressureless sintering at 1250°C under reducing atmosphere (N2-5 vol% H2) conditions. X-ray diffraction and grain microanalyses using an electron probe microanalyzer and an energy dispersive X-ray analyzer revealed the existence of a pyrochlore-structured phase CaU(Ti3+, Ti4+)2O7, perovskite (Ca,U)(Ti3+,Ti4+)O3, barium-hollandite Ba1.14(Al3+, Ti3+)2.27Ti5.71O16, and uraninite (U,Ca,Ti)O2. Leach tests (modified MCC-1) carried out in a simulated Canadian shield groundwater at 90°C for 120 days revealed that barium was the only ion released into the leachants, with an initial leach rate of 2x 10-1 g · m-2. day-1 measured after a 3-day period. The leach rate dropped to 6 x 10-3 g.m-2.day-1 after 120 days of leaching. The concentrations of uranium and other simulated fission products in the leachants were below the detection limits of inductively coupled plasma spectrometry and atomic absorption techniques. The leach rates of uranium and titanium were estimated to be <6 x 10-5 and 3 x 10-5 g·m-2.day-1, respectively.
