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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
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.