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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.
Y. L. Yuan, R. P. Gardner, K. Verghese
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 97-109
Technical Paper | Analyse | doi.org/10.13182/NT87-A33956
Articles are hosted by Taylor and Francis Online.
A Monte Carlo simulation model has been developed to predict the unscattered gamma-ray intensities of an in situ neutron capture prompt gamma-ray analysis system for assaying the elemental concentrations of material that move on a conveyor belt. The model incorporates all pertinent neutron and photon interactions for the assay of coal and all variance reduction techniques necessary to make every history a success. Prompt gamma-ray intensities from all elements of interest over a range of elemental compositions of the sample matrix are calculated in one execution of the program. The calculated results are verified with experimental results on a coal sample in a test configuration that is spiked with variable amounts of sulfur and titanium as two sample elements of interest. The model is expected to be very useful for the optimum design and calibration of on-line neutron capture prompt gamma-ray analysis systems operating in the conveyor belt geometry.