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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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
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May 2025
Latest News
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
Don M. Parkin, Donald G. Schweitzer
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 108-114
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16279
Articles are hosted by Taylor and Francis Online.
Multifilamentary composite wires of Nb Ti and Nb3Sn have been irradiated at 60 ± 5°C with fast neutrons to fluences of 6 × 1019 n/cm2. Measurements of the superconducting critical current, Ic , as a function of transverse field show that the NbTi wires are only moderately affected by neutron irradiation. At a fluence of 6 × 1019 n/cm2, Ic (40 kG) is 82% of the unirradiated value. The Nb3Sn composites undergo a catastrophic reduction in Ic with an apparent threshold at a fluence of 2 to 3 × 1018 n/cm2. Between 2 to 3 × 1018 and 1.1 × 1019 n/cm2, Ic (40 kG) has been reduced to 4% of the unirradiated value. At a fluence of 6×1019 n/cm2, the upper critical field of Nb3Sn has been reduced from 240 kG to 9 ± 0.5 kG. The corresponding Tc has been decreased from 16.4 to 6°K. Annealing of Nb3Sn samples irradiated to 1.1 × 1019 n/cm2 produces only 19% recovery in Ic after h at 400°C.
