ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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February 2025
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January 2025
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Latest News
Survey says . . . Emotional intelligence important in nuclear industry
The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
Karl Richter, Jean Gueugnon, Gerard Kramer, Carlo Sari, Paul Werner
Nuclear Technology | Volume 70 | Number 3 | September 1985 | Pages 401-407
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A15966
Articles are hosted by Taylor and Francis Online.
For fabrication of MX-type (M = actinides; X = carbon and/or nitrogen) advanced fuels, for example, uranium-plutonium carbides for the fast breeder, the carbothermic reduction process of oxides, with subsequent crushing and ballmilling of the reaction product, pressing, and sintering has been generally adopted. A new fabrication procedure, the direct pressing (DP) method, based on the carbothermic reduction process, is presented, however, without intermediate comminution. The fuel is directly processed to pellets. MX powder handling and dust generation within the working area are avoided. The principle and advantages of the new fabrication procedure are reported. The feasibility of the DP method has been demonstrated in laboratory scale on (U,Pu)C fuel pellet preparation. Fuel data compared with the conventional method are given.