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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Nuclear Science and Engineering
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April 2025
Latest News
Penn State and Westinghouse make eVinci microreactor plan official
Penn State and Westinghouse Electric Company are working together to site a new research reactor on Penn State’s University Park, Pa., campus: Westinghouse’s eVinci, a HALEU TRISO-fueled sodium heat-pipe reactor. Penn State has announced that it submitted a letter of intent to host and operate an eVinci reactor to the Nuclear Regulatory Commission on February 28 and plans to engage with the NRC on specific siting decisions. Penn State already boasts the Breazeale reactor, which began operating in 1955 as the first licensed research reactor at a university in the United States. At 70, the Breazeale reactor is still in operation.
Donald G. Gardner
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 487-492
doi.org/10.13182/NSE59-A15506
Articles are hosted by Taylor and Francis Online.
Assuming a uniform distribution of ThO2 slurry particles suspended in an aqueous medium, the probability of a recoil fission fragment escaping the parent slurry particle and then coming to rest within another slurry particle has been estimated. The results indicate that for the slurry particle diameters and volume concentrations that may be expected in certain homogeneous reactor systems only a small percentage of the fission fragments will end their range within slurry particles. The theoretical predictions compare favorably with experimental results from a U-0 aqueous slurry system.