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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
X-energy, Dow apply to build an advanced reactor project in Texas
Dow and X-energy announced today that they have submitted a construction permit application to the Nuclear Regulatory Commission for a proposed advanced nuclear project in Seadrift, Texas. The project could begin construction later this decade, but only if Dow confirms “the ability to deliver the project while achieving its financial return targets.”
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.
