Optimization and parallelization of the thermal–hydraulic subchannel code CTF for high-fidelity multi-physics applications

Author:

Salko Robert K.,Schmidt Rodney C.,Avramova Maria N.

Funder

Consortium for Advanced Simulation of Light Water Reactors

US Department of Energy

Office of Science of the US Department of Energy

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference23 articles.

1. Avramova, M., 2007. Development of an Innovative Spacer Grid Model Utilizing Computational Fluid Dynamics within a Subchannel Analysis Tool (Ph.D. thesis), The Pennsylvania State University.

2. COBRA-TF Input Manual;Avramova,2014

3. Avramova, M., Cuervo, D., 2011. Assessment of CTF boiling transition and critical heat flux modeling capabilities using the OECD/NRC BFBT and PSBT benchmarks database. In Proceedings of the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Toronto, Ontario, Canada.

4. Avramova, M. et al., 2003a. PWR MSLB simulations using COBRA-TF advanced thermal–hydraulic code. In Transactions from 2003 ANS Winter Meeting, New Orleans.

5. Avramova, M. et al., 2003b. COBRA-TF PWR core wide and hot subchannel calculations. In Transactions from 2003 ANS Winter Meeting, New Orleans.

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1. An embedded coupling design and development of NECP-Bamboo2.0 and START for PWR whole-core pin-by-pin analysis;Annals of Nuclear Energy;2024-05

2. Parallelization and optimization for a pin-by-pin whole core thermal–hydraulic analysis code;Annals of Nuclear Energy;2024-02

3. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

4. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

5. References;Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors;2024

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