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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
B. Chinaglia and D. Monti, C. Fedrighini and A. M. Moncassoli
Nuclear Science and Engineering | Volume 27 | Number 2 | February 1967 | Pages 308-317
Technical Paper | doi.org/10.13182/NSE67-A18270
Articles are hosted by Taylor and Francis Online.
Fast-, epithermal-, and thermal-neutron penetration has been measured in the ETNA facility (plane fission neutron source) for some simple shield configurations (all water or a composite of water, iron, and water slabs with iron thickness of 6.2, 10, and 19.6 cm)., Experimental results are presented as thermal fluxes or activation-detector reaction rates for the water-only configuration and as the ratios of the reaction rates observed in the other configurations to those obtained with water only. These results are compared to calculations performed with a multigroup-removal diffusion code (MAC-RAD) and a semi-empirical diffusion code (FOG-S) to test their ability to predict the influence of an iron slab on the neutron spectrum and the neutron attenuation.