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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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Nuclear Technology
Fusion Science and Technology
May 2025
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.
Y. Oyama, S. Yamaguchi, K. Tsuda, C. Konno, Y. Ikeda, H. Maekawa, T. Nakamura, K. Porges, E. Bennett
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1955-1960
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29628
Articles are hosted by Taylor and Francis Online.
Two types of heterogeneous blanket systems were tested to estimate a design margin for neutronic calculations. One system simulates a multi-layered beryllium/lithium-oxide blanket, and the other does water coolant channels in a Li2O blanket. For both systems the tritium production rate (TPR), reaction rate and neutron spectrum were measured. Those measurements were performed by NE213 and Li-glass scintillators, Li-foil and Li2O zonal block scheme for TPR, activation foils for reaction rate and proton recoil proportional counters for spectrum. In addition, gamma-ray heating was measured by spectrum weighting function technique using NE213 scintillator. Precise distribution measurements near the material boundary were performed especially by directly stacking the irradiation samples in the test blanket region to minimize a perturbation for the measurement.