DEVELOPMENT AND PRELIMINARY ASSESSMENT OF A THREE-DIMENSIONAL THERMAL HYDRAULICS CODE, CUPID
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference13 articles.
1. Trends and needs in experimentation and numerical simulation for LWR safety
2. Evaluation of computational fluid dynamic methods for reactor safety analysis (ECORA)
3. Qualification of the CFD code Trio_U for full scale reactor applications
4. Computational Fluid Dynamics for nuclear applications: from CFD to multi-scale CMFD
5. A semi-implicit numerical scheme for transient two-phase flows on unstructured grids
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1. Development and validation of wall and interfacial friction models in LOCUST for reactor downcomer with direct vessel injection;Nuclear Engineering and Technology;2024-10
2. Analysis on helium stratification erosion by vertical steam jet using the CUPID code;Nuclear Engineering and Design;2022-03
3. Development and validation of a two-fluid three-field model for the vertical upward flow;Progress in Nuclear Energy;2021-11
4. The development of high fidelity Steam Generator three dimensional thermal hydraulic coupling code: STAF-CT;Nuclear Engineering and Technology;2021-03
5. Analysis of Helium Stratification Erosion by a Vertical Steam Jet Using CUPID;Transactions of the Korean Society of Mechanical Engineers - B;2020-07-31
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