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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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 issues subsequent license renewal to Monticello plant
The Nuclear Regulatory Commission has renewed for a second time the operating license for Unit 1 of Minnesota’s Monticello nuclear power plant.
Eduardo Gallego, Alfredo Lorente, Héctor René Vega-Carrillo
Nuclear Technology | Volume 168 | Number 2 | November 2009 | Pages 399-404
Shielding | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Radiation Protection | doi.org/10.13182/NT09-A9216
Articles are hosted by Taylor and Francis Online.
We present the testing of a high-density magnetite concrete [commercially available under the name Hormirad™, developed by the Spanish company Construcciones Tecnicas de Radioterapia, S.L. (CT-RAD)] as neutron shielding material. The purpose of this work was to characterize the material behavior against neutrons, as well as to test different mixings including boron compounds in an effort to improve neutron shielding efficiency. Hormirad™ slabs of different thicknesses were exposed to a 241Am-Be neutron source under controlled conditions. The original mix, which includes a high fraction of magnetite, was then modified by adding different proportions of anhydrous borax (Na2B4O7). Looking for a comparison, the same experiment was repeated with slabs of ordinary concrete (HA-25) used to shield medical accelerator facilities. In parallel to the experiments, Monte Carlo calculations were performed with MCNP5, with some differences found with regard to the experiments, attributable to uncertainties in the elemental composition of the samples tested. Tenth-value layers have been determined for the different types of concrete tested for the 241Am-Be neutron source. The results show an advantageous behavior of the Hormirad™ when comparing it with ordinary concrete. Although borated concretes show a small improvement in neutron attenuation when they are compared with Hormirad™ alone, the resulting reduction in density and structural properties makes them less practical.