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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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
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.
Gary A. Hughes, Sudarshan K. Loyalka, Gerald A. Schlapper+
Nuclear Technology | Volume 60 | Number 3 | March 1983 | Pages 379-394
Technical Paper | LWR Control Materials—I and II / Nuclear Safety | doi.org/10.13182/NT83-A33125
Articles are hosted by Taylor and Francis Online.
The RELAP4 computer program has been used to study loss-of-flow and loss-of-coolant transients for the University of Missouri Research Reactor (MURR). Simple experimental tests have been conducted to provide RELAP4 model parameters. The computer results have provided an understanding of MURR behavior under accident conditions, and may also be useful in understanding the low pressure/low temperature range of transients at other reactors.
