ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
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.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Raymond R. Edwards
Nuclear Technology | Volume 4 | Number 4 | April 1968 | Pages 245-259
Technical Paper and Note | doi.org/10.13182/NT68-A26322
Articles are hosted by Taylor and Francis Online.
Implementation of safeguards against diversion of special nuclear materials from peaceful uses to weapons often requires nondestructive assay of fuel materials at various stages in the fuel cycle to obtain information on fissile material burnup, detailed fuel history, and content of 235U, 239Pu, and 233U. Past, current, and proposed efforts to elicit the required information have included direct gamma-ray spectrometry of fuel materials (by means of scintillation and, more recently, solid-state detectors); indirect gamma-ray spectrometry (magnetic analysis of external conversion electron spectra, Compton spectrometry by semiconductor detection pulse-height analysis); x-ray emission spectrometry; activation analysis of stable (or very long-lived) fission products; use of external monitors for neutron flux and/or fission and breeding rates; fast/slow neutron-fission counters; neutron transmission measurements; fission-neutron counting and spectrometry (prompt and delayed); photonuclear response measurements; and calorimetry. The various methods are described and compared for accuracy and precision, for the kind of information elicited, and for probable cost and portability of equipment required.