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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
DOE awards $153M Paducah services contract to North Wind Dynamics
The Department of Energy’s Office of Environmental Management announced it has awarded a contract worth nearly $153 million to North Wind Dynamics for infrastructure support services at the DOE’s Paducah Site in Kentucky. According to DOE-EM, the company, a small business based in Idaho Falls, Idaho, was chosen based on “key personnel, organization, and management approach, past performance, and value to taxpayers.”
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.