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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Contractor selected for Belgian LLW/ILW facility
Brussels-based construction group Besix announced that is has been chosen by the Belgian agency for radioactive waste management ONDRAF/NIRAS for construction of the country’s surface disposal facility for low- and intermediate-level short-lived nuclear waste in Dessel.
P. D. Smith, R. G. Steinke, D. D. Jensen, T. Hama
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 475-482
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31907
Articles are hosted by Taylor and Francis Online.
A model simulating the in-pile release of metallic fission products from a batch of coated fuel particles is based on a solution of the transient Fick’s diffusion equation in a nonhomogeneous medium. It is developed in two stages. First, some representative analytic solutions for a single birth pulse in a single particle are numerically tabulated as functions of nondimensional parameters. Second, the solution for a history of continuously varying source, temperature, and particle failure fraction is obtained by interpolation and superposition. This permits use of the method as an efficient source subroutine in full-core release problems. The large number of physical parameters in the model provides adaptability in correlating and extrapolating experimental results. By using numerical examples, the model was shown to account for the following phenomena: recoil, transient diffusion response, transition from the intact to the failed state, and the effect of various rate-limiting mechanisms on the release.