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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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Latest News
IAEA’s nuclear security center offers hands-on training
In the past year and a half, the International Atomic Energy Agency has established the Nuclear Security Training and Demonstration Center (NSTDC) to help countries strengthen their nuclear security regimes. The center, located at the IAEA’s Seibersdorf laboratories outside Vienna, Austria, has been operational since October 2023.
Awais Zahur, Muhammad Rizwan Ali, Deokjung Lee
Nuclear Science and Engineering | Volume 197 | Number 12 | December 2023 | Pages 3175-3192
Technical Note | doi.org/10.1080/00295639.2023.2189888
Articles are hosted by Taylor and Francis Online.
A coupling framework named Multi-Physics CORE (MPCORE) is developed to analyze the multiphysics phenomenon in a nuclear reactor. MPCORE performs two-way coupling between two physics modules. A rod ejection accident (REA) is an important design-basis accident that results in an instantaneous power surge in the case of prompt criticality. Hence, this technical note studies the passive response of a nuclear reactor core in the case of a similar rapid reactivity insertion. Stand-alone calculations by neutronics, thermal-hydraulic (TH), or fuel performance (FP) modules use conservative options for other physics modules. Thus, multiphysics analysis provides a more realistic assessment of actual prospective damage. MPCORE employs an adaptive time-step feature to reduce execution time. Moreover, it performs in-memory transfer of data between different modules. This technical note evaluates the performance of the TH module with cross flow (subchannel) and without cross flow (one-dimensional). For the FP module, the effect of dynamic and static gap heat transfer coefficient models is also quantified. Hence, four combinations with these two TH and FP options are simulated. The following are the safety parameters compared for different models: departure from nucleate boiling ratio, linear power, fuel enthalpy, fuel centerline temperature, cladding outer surface temperature, and coolant temperature.