Diagnostics of the critical heat flux state of a VVER reactor based on a channel steaming model

Svetlana A. Kachur

doi:10.3897/nucet.5.36475

Research Article

Nuclear Energy and Technology 5(2): 139-144
https://doi.org/10.3897/nucet.5.36475 (21 Jun 2019)

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Mohamed AbdulHameed, Aly Shaaban, Hussein Gamal, Ayah Elshahat (2022)
A methodology for CHF prediction in VVER rod bundles. Nuclear Engineering and Design 393: 111751.

DOI: 10.1016/j.nucengdes.2022.111751

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