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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
J. V. Siebers, P. M. DeLuca, Jr., D. W. Pearson, R. E. Prael
Nuclear Science and Engineering | Volume 122 | Number 2 | February 1996 | Pages 258-266
Technical Paper | doi.org/10.13182/NSE96-A24160
Articles are hosted by Taylor and Francis Online.
Shielding related calculations were performed for 230-MeV protons incident upon a stopping-length iron target using the LAHET code system (LCS). Secondary neutrons and photons, produced by proton interactions with the target nuclei, were transported through a spherical concrete shield in which absorbed dose and dose equivalent tallies were produced and attenuation parameters deduced. Comparing calculated results with measurements performed with a similar target, beam, and shielding geometry, the dose equivalent production term is double the measured value. The LCS overestimates measured attenuation values at 0, 22, and 45 deg while correctly predicting the attenuation length at 90 deg. Comparisons of LCS results with HETC calculations and analytical methods indicates that LCS better estimates the attenuation length and dose equivalent production.