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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Latest News
X-energy, Dow apply to build an advanced reactor project in Texas
Dow and X-energy announced today that they have submitted a construction permit application to the Nuclear Regulatory Commission for a proposed advanced nuclear project in Seadrift, Texas. The project could begin construction later this decade, but only if Dow confirms “the ability to deliver the project while achieving its financial return targets.”
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.