Development and Implementation of CFD-Informed Models for the Advanced Subchannel Code CTF
Author:
Affiliation:
1. Pennsylvania State Univ., University Park, PA (United States)
2. North Carolina State Univ., Raleigh, NC (United States)
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Office of Scientific and Technical Information (OSTI)
Cited by 9 articles. 订阅此论文施引文献 订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献
1. Mechanistic model of critical heat flux in rod bundles based on a high-precision subchannel code;Nuclear Engineering and Design;2024-06
2. Computational Fluid Dynamics Modeling of a Pressurized Water Reactor Fuel Assembly to Estimate Loss Coefficients in Support of Subchannel Thermalhydraulics Modeling of Pressurized Water Reactor Small Modular Reactors With Advanced Fuels;Journal of Nuclear Engineering and Radiation Science;2022-07-19
3. Development of a flow sweeping mixing model for helical fuel rod bundles;Annals of Nuclear Energy;2021-09
4. Turbulent Mixing Models and Other Mixing Coefficients in Subchannel Codes—A Review Part A: Single Phase;Nuclear Technology;2020-09-01
5. A phenomenological CHF model for mixing-vane spacers in a subchannel of a rod bundle;Annals of Nuclear Energy;2020-07
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