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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
From remediation to production: The DOE’s Cleanup to Clean Energy initiative
On July 28, 2023, the Department of Energy launched its Cleanup to Clean Energy initiative, an effort to repurpose underutilized DOE-owned property—portions of which were previously used in the nation’s nuclear weapons program—into the sites of clean-energy generation.
Su-Jong Yoon, Chang-Yong Jin, Min-Hwan Kim, Goon-Cherl Park
Nuclear Technology | Volume 175 | Number 2 | August 2011 | Pages 419-434
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT11-A12313
Articles are hosted by Taylor and Francis Online.
An accurate prediction of core bypass flow is of great importance in the design of very high temperature reactor (VHTR) cores in terms of the fuel thermal margin and safety. In the present study, a unit-cell experiment and computational fluid dynamics (CFD) analysis were carried out to evaluate the amount and distribution of core bypass flow. This study examined the effects of the inlet mass flow rate, block combinations, and thickness of the bypass gap. The prediction capability of the CFD code FLUENT was validated by the unit-cell experimental result. The analysis was extended to the entire core region. In this simulation, a quarter core was simulated using the nonconformal grid method to reduce the computational cost and time. The accuracy and applicability of the nonconformal grid method were assessed from the experimental results and comparative simulation. In conclusion, the flow distribution in the VHTR core was evaluated by the CFD core model with low error and computational cost.