Evaluation of DNBR with neutronics calculation in LWR systems

• Published in: Nuclear energy and technology Vol. 9; no. 2; pp. 77 - 83
• Main Authors: Khan, Suhail Ahmad, Kannan, Umasankari
• Format: Journal Article
• Language: English
• Published: Sofia Pensoft Publishers 20.06.2023; National Research Nuclear University (MEPhI)
• Subjects: Configuration management; Core analysis; DNBR; Finite difference method; Heat Flux; Heat transfer; Hydraulics; Light water reactors; Nuclear accidents & safety; Nuclear power plants; Nuclear reactors; Nuclear safety; Nucleate boiling; Pressurized water reactors; Reactors; TRIHEXFA; W-3 Ton

The heat flux in a Light Water Reactor (LWR) system is used to estimate the Departure from Nucleate Boiling Ratio (DNBR) of the system which is an important thermal hydraulic parameter for nuclear reactors from heat removal point of view. The DNBR signifies an operational safety limit i.e. the nucle...