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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Xinyu Zhao, Eugene Shwageraus (Univ of Cambridge)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 198-205
GeN-FOAM is a multi-physics solver based on the OpenFOAM library developed at PSI/EPFL, Switzerland for transient analyses of fast reactors. The current version of GeN-FOAM can simulate a wide range of transients with flexible spatial resolution. One of the main limitations of the current version, however, is relatively simple fuel temperature calculation model. Also, the effects of fuel structural and dimensional changes as a function of temperature, composition and burnup are currently not considered. This work first presents the integration of an advanced fuel performance modelling tool TRANSURANUS developed at Joint Research Centre (JRC)-Karlsruhe into the GeN-Foam solver. The new coupled tool is referred to as the GeN-transFoam. The original GeN-Foam doesn't have burnup calculation capability which makes it very inconvenient to simulate a reactor at the end of cycle, especially when an accurate fuel behaviour prediction is expected. The paper reports a simple way to implement the burnup calculation, given the configuration of the GeN-Foam solver. The GeNtransFoam solver with account for burnup effects is used to analysis the European Sodium Fast Reactor (ESFR) at the end of cycle (EOC) in steady state condition. The neutronics calculation results are compared with results provided by Monte Carlo calculation. In the end, the burnup calculation in the code is discussed.