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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
F. L. Yaggee, G. M. Dragel
Nuclear Technology | Volume 27 | Number 2 | October 1975 | Pages 292-300
Technical Paper | Instrument | doi.org/10.13182/NT75-A24297
Articles are hosted by Taylor and Francis Online.
An ultrasonic trepanning technique for use in the radial sampling of small-diameter ceramic fuel pellets takes an initial sample in the form of a small-diameter solid cylinder from the center of the pellet. Subsequent samples are thin-wall concentric hollow cylinders. Radial samples 1.56 to 6.80 mm in diameter and 5.35 to 6.80 mm long have been obtained from 93% dense UO2 pellets and 91% dense mixed-oxide (UO2-PuO2) fuel pellets. Cylindrical samples with wall thicknesses of 0.25 to 0.44 mm can be obtained without difficulty. Diameters and wall thicknesses of individual samples and concentricity between samples can be held within ±0.01 mm, at a sample cutting rate of 0.02 mm/sec. The technique has been adapted to existing ultrasonic grinding equipment located in a shielded glove-box facility, which had been used for less precise ultrasonic drilling operations. The technique is currently being used to obtain radial samples from fresh (unirradiated) mixed-oxide fuel pellets that have been subjected to low-burnup exposure in the transient test reactor (TREAT). The individual samples taken from each pellet undergo burnup analysis using standard gamma-counting techniques. The gamma emitters are the 140Ba-140La daughters formed during the radioactive decay of the activated fuel pellets. The analytical results, expressed as fiss/(g sec), obtained for discrete radial locations provide the necessary information on the radial power distribution within the individual pellet.