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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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
Oklo completes end-to-end demonstration of advanced fuel recycling
Oklo Inc. has announced that it has completed the first end-to-end demonstration of its advanced fuel recycling process as part of an ongoing $5 million project in collaboration with Argonne and Idaho National Laboratories. Oklo’s goal: scaling up its fuel recycling capabilities to deploy a commercial-scale recycling facility that would increase advanced reactor fuel supplies and enhance fuel cost effectiveness for its planned sodium fast reactors.
T. M. Krishnamoorthy, S. N. Joshi, G. R. Doshi, R. N. Nair
Nuclear Technology | Volume 104 | Number 3 | December 1993 | Pages 351-357
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34896
Articles are hosted by Taylor and Francis Online.
Leach characteristics of some typical nuclides such as cesium, strontium, cobalt, I−, and CO3−2 from ordinary portland cement waste forms have been studied using the ISO test method and radiotracers of the respective nuclides, i.e., 134Cs, 85Sr, 60Co, 131I, and 14C. The leach studies suggest a rapid release of radioactivity in the beginning (fast component) followed by slow release for long periods of time (slow component). A mathematical model has been simulated to describe the leaching kinetics of these nuclides from the cement matrix. The effective diffusion coefficient Deff is computed from the two componental diffusion coefficients, and the retardation factor (α) for a nuclide is evaluated from a knowledge of the radioactivity distribution in the aqueous and solid phase at equilibrium. The product αDeff for all the nuclides studied has been found to be approximately constant and is equal to the intrinsic diffusion coefficient in the cement matrix. The net fractional release of different radionuclides from cement waste form showed a decreasing pattern, i.e., 134Cs > 131I > 85Sr > 14Cr > 60Co indicating the largest diffusion coefficient for cesium as 10−2 cm2/day and the least for 14C as 3 × 10−8 cm2/day.