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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
Chao Tian, Lifeng Sun, Chao Fang
Nuclear Science and Engineering | Volume 175 | Number 2 | October 2013 | Pages 204-211
Technical Paper | doi.org/10.13182/NSE12-51
Articles are hosted by Taylor and Francis Online.
In this paper, we discuss our study of the fission product diffusion process in TRISO fuel particles used in pebble bed high-temperature reactors (HTRs). Different from the previous numerical solution, the analytical solution of this diffusion process by variables separation was derived. It was also accessible to obtain the analytical expressions of the fission product concentration distribution C(t), the corresponding release fractions F(t), and the ratio of release and productive amounts R(t)/B(t) of fission products. Furthermore, to reduce the rounding errors, parameters mentioned in the diffusion equations were nondimensionalized, which made the result fairly reliable and credible. Since the analytical solutions are exact, many unnecessary assumptions and approximations in Booth's model are avoided. On the basis of HTR-10 design benchmark, the C(t), F(t), and R(t)/B(t) of 137Cs and 134Cs in TRISO fuel particles were calculated and then compared with the finite element solutions. The results show that analytical solutions are effective and consistent with the physical picture.