ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
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.
George O. Hayner, Todd L. Hardt
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 191-195
Technical Paper | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT89-A27646
Articles are hosted by Taylor and Francis Online.
Laboratory examination of debris recovered from the upper tubesheet of the Three Mile Island Unit 2 Bloop steam generator was performed as part of a series of technical evaluations of postaccident core damage. The analysis of a sample of loose, gravel-like debris is of special interest since it is believed to have been transported from the core region during the core damage sequence between 174 and 192 min to the upper tubesheet when reactor coolant pump B was restarted. The characterization of five size fractions and ten of the largest particles was accomplished by destructive (chemical, radiochemical, metallography, and scanning electron microscopy/energy dispersive spectrometry) and nondestructive (photographic examination and density) methods of analysis. The results of this examination provided direct information on the extent of core damage when restart occurred.