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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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ANS Congressional Fellowship applications due
Applications for the Society’s Glenn T. Seaborg Congressional Science and Engineering Fellowship will be closing soon. Congressional Fellows can directly contribute to the federal policymaking process, working in either a U.S. senator’s or representative’s personal office or with a congressional committee. They will be responsible for supplying Congress with their expertise in nuclear science and technology, having a hand in the creation of new laws while gaining a deeper understanding of the legislative process.
F. Zylbersztejn, H. N. Tran, I. Pázsit, P. Filliatre, C. Jammes
Nuclear Science and Engineering | Volume 177 | Number 2 | June 2014 | Pages 203-218
Technical Paper | doi.org/10.13182/NSE13-41
Articles are hosted by Taylor and Francis Online.
The subject of this paper is the calculation of the neutron noise induced by small-amplitude stationary radial variations of the core size (core expansion/compaction, also called core flowering) of a large sodium-cooled fast reactor. The calculations were performed on a realistic model of the European Sodium Fast Reactor (ESFR) core with a thermal output of 3600 MW(thermal), using a multigroup neutron noise simulator. The multigroup cross sections and their fluctuations that represent the core geometry changes for the neutron noise calculations were generated by the code ERANOS. The space and energy dependences of the noise source represented by the core expansion/compaction and the induced neutron noise are calculated and discussed.