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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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
Inkjet droplets of radioactive material enable quick, precise testing at NIST
Researchers at the National Institute of Standards and Technology have developed a technique called cryogenic decay energy spectrometry capable of detecting single radioactive decay events from tiny material samples and simultaneously identifying the atoms involved. In time, the technology could replace characterization tasks that have taken months and could support rapid, accurate radiopharmaceutical development and used nuclear fuel recycling, according to an article published on July 8 by NIST.
Jorge V. Carvajal, Shawn C. Stafford, Jeffrey L. Arndt, Paul M. Sirianni, Melissa M. Heagy, Emre Tatli (Westinghouse), David M. Carpenter, Yakov Ostrovsky (MIT)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 1000-1012
The development and commercial introduction of advanced nuclear reactor fuel is slowed by the long turnaround time required by the methodology’s cycle of in-core irradiation, cooling, shipping and post irradiation examination (PIE). PIE is complicated and costly due to the high activation of the irradiated fuel. During the development process, which can extend over several years, access to fuel cladding operating data is very limited. Incorporating a real-time, remote, fuel monitoring system into the fuel rod can provide critical information on such parameters as centerline fuel temperature, axial fuel pellet elongation and rod internal pressure that can enable fuel models to be adjusted in real time and accelerate the licensing approval process. By transmitting the information from the integral sensor through the cladding, penetrations into the fuel rod are avoided and the performance of the fuel is not compromised. Data on fuel performance is generated immediately on startup of the instrumented fuel rod and can continue throughout the life of the rod. This data can be used immediately to inform further fuel development activities and can also be used to target PIE activities to enhance their usefulness and reduce costs. This paper will describe the prototype sensor development, operation and results obtained during the irradiation program at the Massachusetts Institute of Technology Reactor (MITR).