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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
Gokul Vasudevamurthy, Travis W. Knight, Thad M. Adams, Elwyn Roberts
Nuclear Technology | Volume 173 | Number 2 | February 2011 | Pages 200-209
Technical Paper | Materials for Nuclear Fuels | doi.org/10.13182/NT11-A11549
Articles are hosted by Taylor and Francis Online.
Dispersed fuel composites consisting of uranium carbide particles (microspheres) in a zirconium carbide (inert) matrix were fabricated and characterized. Advanced fuels including refractory inert matrix fuels are being considered for gas fast reactors, which can accommodate a variety of feed materials including recycled transuranics that include minor actinides for incineration and high-level waste reduction. The particles for this effort were fabricated by employing a custom built rotating electrode machine. This process employed a uranium carbide electrode manufactured by combustion synthesis of uranium hydride and graphite powders. Two process parameters, namely, arc intensity and rotational speed, were varied to assess their effects on the size of the particles produced. The particles were characterized for microstructure, density, and composition (homogeneity). These particles were mixed with pure zirconium and graphite powders in different matrix to particle volumetric ratios of 90/10, 80/20, and 70/30 and inductively heated to 1850°C to initiate combustion synthesis to produce composites of zirconium carbide with the embedded uranium carbide particles. The aim was to limit process temperature and in particular process time, bearing in mind the possible future extensions of these processes to minor actinide-bearing fuels and also to avoid any changes in the structural integrity of the particles and large-scale diffusion of uranium into the matrix. The composites were characterized for microstructure, phase composition, density, and porosity distribution. The results are presented.