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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Toshikazu Takeda, Kazuo Azekura, Tadahiro Ohnishi
Nuclear Science and Engineering | Volume 62 | Number 4 | April 1977 | Pages 709-715
Technical Paper | doi.org/10.13182/NSE77-A15211
Articles are hosted by Taylor and Francis Online.
An improved response matrix method has been proposed to effectively take into account the anisotropy of neutron angular distributions. The method utilizes a relation between the P0 and P1 components of a neutron angular distribution instead of calculating them independently. Hence the number of unknowns as well as computing time can be kept about the same as in the conventional response matrix method which adopts an isotropic approximation of a neutron angular distribution. The proposed method has been evaluated by applying it to one-dimensional slab and two-dimensional hexagonal systems. The results are quite promising: In comparison with the reference SN calculation, the difference of the neutron multiplication factor and power distribution is within 0.1% Δk/k and 2%, respectively, and furthermore, the computing time is reduced to below one-third.