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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
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.
V. Kumar, Nagendra Singh Raghaw, H. S. Palsania
Nuclear Science and Engineering | Volume 172 | Number 2 | October 2012 | Pages 151-163
Technical Paper | doi.org/10.13182/NSE11-41
Articles are hosted by Taylor and Francis Online.
A Monte Carlo code is developed in Visual Basic 6.0 for the study of radiation damage of pure metals irradiated by a neutron spectrum. At energies <10 MeV, development of cascades of elastic interactions of both primary neutrons and secondary recoiled atoms is incorporated. In a collision, kinetic energy given to an atom below or above the threshold displacement energy Ed (eV) is calculated along with the displacements. Displacements, defect production efficiency η, and damage energy Tdam are estimated to relate to the physical changes in the irradiated metal and to estimate the displacements per atom. The code is validated by determining the defect density on the surface of irradiated thin nickel foil and comparing with the hill-hock density of displaced atoms, using atomic force microscopy. In the case of irradiation of a niobium sample, stress-strain and I-V characteristics are measured before and after the irradiation by neutrons from an Am-Be source, and both stress and electrical resistance are shown to be enhanced after the irradiation.