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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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ANS announces 2025 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Lisa Marshall has named this season’s recipients, who will receive recognition at the upcoming Annual Conference in Chicago during the Special Session on Tuesday, June 17.
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.