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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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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
F. J. Salzano, S. Aronson
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 51-54
Technical Paper | doi.org/10.13182/NSE67-A18666
Articles are hosted by Taylor and Francis Online.
A method is presented for predicting the conditions under which graphite will react with cesium at high temperatures and low cesium pressures to form compounds. The method is based on the available thermodynamic data on cesium-graphite compounds and on an understanding of the nature of the bonding forces in these compounds. An expression is given for the threshold pressure, at any temperature, below which no reaction will occur between cesium and graphite. The structural deterioration and swelling of graphite which occurs when cesium-graphite compounds are formed can be avoided by keeping the cesium pressure below the threshold value. The information on the compatibility of cesium and graphite is of potential use in the design of MHD direct-conversion systems, in high-temperature graphite reactors and in systems that require the availability of cesium vapor at controlled pressures, such as thermionic converters.