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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Adrienne L. Lehnert, Kimberlee J. Kearfott
Nuclear Technology | Volume 188 | Number 1 | October 2014 | Pages 97-111
Technical Paper | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT11-125
Articles are hosted by Taylor and Francis Online.
Fast neutron interrogation for explosives detection has shown potential for the screening of sea-land cargo containers. Simulations were completed investigating the neutron scatter behavior of 14.1-MeV fast neutrons in such screening scenarios. Earlier efforts centered on Monte Carlo (MCNP5) simulations to identify flags or on specific calculations based on photons or neutrons produced as a result of fast neutron interaction that signal the presence of the explosive RDX (C2H6N6O6). Those simulations consisted of simplified target geometry; artificially collimated neutron source; and generalized organic, hydrogenous, or metallic types of cargo materials. In this study, the MCNP5 simulation was expanded to include a more accurate representation of the neutron source, target geometry, detector response, and realistic and varied container contents. The flags found using the earlier simulations were applied to the more realistic scenario models in order to determine the feasibility of the use of flags in a detection algorithm. Additional flags utilizing the simulated detector response were also investigated. The conditions under which specific flags were preferable were also examined. It was found that many flags performed well independent of the cargo type while others, such as those using only neutron backscatter, were more highly dependent on cargo type. Furthermore, many of the best-performing flags were those that did not require stringent neutron spectroscopy and would therefore be feasible with existing technology.