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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Ariz. governor vetoes “fast track” bill for nuclear
Gov. Katie Hobbs put the brakes on legislation that would have eliminated some of Arizona’s regulations and oversight of small modular reactors, technology that is largely under consideration by data centers and heavy industrial power users.
G. R. Odette, T. O. Ziebold
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 72-81
Technical Paper | doi.org/10.13182/NSE72-A22528
Articles are hosted by Taylor and Francis Online.
An experiment was performed to measure the energy-dependent damage function for the neutron irradiation induced increase in the lower yield strength of iron. Small tensile test specimens were exposed at low temperatures (<100°C) to 1017 - 1018 n/cm2 (E > 1 MeV) in seven reactor spectra while a high degree of consistency among all other variables known to be significant was maintained. The neutron flux spectra in all locations were measured using the multiple foil activation technique and the SAND-II code for the data analysis. The mechanical property and flux spectral data were then analyzed using SAND-II to unfold the damage functions. Estimates of errors induced in the solution by the iterative unfolding procedure were made considering possible contributions from both the lack of mathematical solution uniqueness and data error propagation.