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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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Beyond borders
Lisa Marshallpresident@ans.org
Global partnerships advance the nuclear enterprise, demonstrating commitment to energy security, supply chain buildout, and economic and human development. Collaborations remain imperative, keeping these things in mind:
Approximately half of the 400-GW reactor fleet will be retiring by 2040.1
The forecasted need for new nuclear is 300–600 GW by 2050.
There is a need to counter the build-own-operate model.2
Appropriate funding and financing mechanisms are needed.
Host country regulatory oversight is paramount.
By 2050, there will be 4 million nuclear professionals supporting the industry.3
Daisuke Kawasaki, Joonhong Ahn, Paul L. Chambré, William G. Halsey
Nuclear Technology | Volume 148 | Number 2 | November 2004 | Pages 181-193
Technical Paper | High-Level Radioactive Waste Disposal | doi.org/10.13182/NT04-A3558
Articles are hosted by Taylor and Francis Online.
Results are presented of an analytical study of mass release of a long-lived radionuclide from multiple waste canisters placed in a water-saturated repository in a two-dimensional array configuration. The radionuclide is assumed to be released congruently with the dissolution of the waste matrix. The concentration and release rate of the radionuclide from the downstream side of the repository region are numerically calculated to observe the effects of canister multiplicity and the leach time of the waste form. Peak values of the concentration and the release rate have been analytically formulated.For numerical illustration, the case of a Japanese repository concept is considered, where canisters containing vitrified wastes are placed in a water-saturated granitic rock. For the illustration, the nuclide 135Cs is chosen, which is characterized by a long half-life and high mobility in the assumed geologic media.The peak exit concentration becomes independent of the number of waste canisters in the flow direction if the number is sufficiently great. This peak value is a theoretical upper bound of the exit concentration, regardless of the number of canisters or the waste matrix leach time. The model is suitable for assisting in the design of a repository since the effects of the canister array configuration are reflected by the peak exit concentration and the peak release rate.