ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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!
Latest Magazine Issues
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
Fusion Science and Technology
Latest News
ANS joins others in seeking to discuss SNF/HLW impasse
The American Nuclear Society joined seven other organizations to send a letter to Energy Secretary Christopher Wright on July 8, asking to meet with him to discuss “the restoration of a highly functioning program to meet DOE’s legal responsibility to manage and dispose of the nation’s commercial and legacy defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW).”
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.