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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
Alan Atkinson, Allan K. Nickerson
Nuclear Technology | Volume 81 | Number 1 | April 1988 | Pages 100-113
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT88-A34082
Articles are hosted by Taylor and Francis Online.
Diffusion and sorption in cementitious materials are important factors influencing radionuclide migration in radioactive waste disposal. Four different experimental techniques have been used to study these processes for Cs+, Sr2+, and I− ions in Sulphate Resisting Portland Cement paste saturated with water. The results of different experimental methods are compared and their relative merits discussed. The observations can be rationalized only by taking into account departures from the usual simple description of transport in porous media. These are that the cement pore structure has fast and slow diffusivity networks, that all ions do not have the same diffusibility, and that some ions (in this case I−) have nonlinear sorption isotherms. When these factors are taken into account, the present observations are also found to be compatible with the results of other studies. The most appropriate values of characteristic parameters for diffusion and sorption in this system are deduced.