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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
S. Benck, I. Slypen, J.-P. Meulders, V. Corcalciuc, M. B. Chadwick
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 86-95
Technical Paper | doi.org/10.13182/NSE02-A2246
Articles are hosted by Taylor and Francis Online.
Double-differential cross sections (spectra) for light charged particle (proton, deuteron, triton, and alpha) emission in fast neutron-induced reactions on aluminum are reported for eight incident neutron energies between 25 and 55 MeV, augmenting previous results at 63 MeV. Angular distributions were measured at 15 laboratory angles between 20 and 160 deg. Procedures for data taking and data reduction are presented. Deduced energy-differential and total production cross sections are also reported. Experimental cross sections are compared to existing experimental proton-induced data and to nuclear model calculations that include preequilibrium and compound nucleus decay mechanisms. These calculations formed the basis of a recent set of higher-energy ENDF/B-VI data evaluations (the LA150 Library), and therefore, the present measurements facilitate a testing of the accuracy of these evaluated cross sections. This is important for accelerator-driven-systems design, where radiation transport simulation codes require accurate nuclear data to guide engineering design. Comparisons between the experimental data and the calculated values indicate that while proton, triton, and alpha-particle emission are modeled fairly accurately, deuteron emission is only poorly described, and further improvements to the nuclear reaction models for preequilibrium cluster emission are needed.