Validation of codes for modeling and simulation of nuclear power plants: A review

Author:

Moshkbar-Bakhshayesh Khalil,Mohtashami Soroush

Publisher

Elsevier BV

Reference179 articles.

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3. An overview on thermal-hydraulic phenomena for water cooled nuclear reactors; part I: SETs, and ITFs of PWRs, BWRs;Aksan;Vvers. Nuclear Engineering and Design,2019

4. CSNI code validation matrix of thermo-hydraulic codes for LWR LOCA and transients;Aksan,1987

5. Aksan, N., 2008a. International standard problems and small break loss-of-coolant accident (SBLOCA). Science and Technology of Nuclear Installations 2008.

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