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
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.
G. Kamelander, F. Putz
Nuclear Science and Engineering | Volume 74 | Number 1 | April 1980 | Pages 13-22
Technical Paper | doi.org/10.13182/NSE80-A18941
Articles are hosted by Taylor and Francis Online.
The method of overlapping neutron spectra has been developed by Selengut to calculate neutron spectra and reaction rates in weakly absorbing media with temperature discontinuities. A combination of Selengut's method with multicollision probability theory leads to a new thermalization method suitable to a wider field of application, especially to the homogenization of reactor cells. Based on this theory, the code THERMAL has been written. The results of THERMAL have been compared with those of the standard transport code THERMOS. Comparison of the results gave a satisfactory correspondence. Compared to THERMOS, the computing time and the storage capacity requirements of THERMAL are fairly small.
