ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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.
M. T. A-Moneim
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 452-463
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32581
Articles are hosted by Taylor and Francis Online.
Experimental verification of the piping code ICEPEL has led to a modification of the elbow hydrodynamic model so that agreement in predicting uniform pressure across the elbow cross section is obtained. A rupture disk model is incorporated and used in modeling the MARK-IICB loop of the TREAT reactor to assess its structural adequacy during a postulated accident that results from fuel-sodium interaction. The analysis showed the loop remained elastic. A nonreflecting boundary is incorporated and can be used in elastically deforming regions of piping systems to allow for refined modeling of portions of interest without having to model the whole system.