Abstract
The FLOOD4 code which evaluates reflood behavior during LOCA of PWR is explained and is used to predict LOFT L2-4 test during reflood. The FLOOD4 model has downcomer, lower plenum, core, upper plenum, intact loop and broken loop in PWR, and the code calculates thermal and hydraulic behavior during reflood.Prediction of the L2-4 test presents the following requirements for revising and modifying the code: (1) To define a change of gap conductance in a nuclear fuel. (2) To investigate heat transfer correlation in dispersed flow and film boiling regime. (3) To consider superheated steam in dispersed flow regime and to replace empirical heat transfer correlations with analytical or semi-analytical ones. (4) To investigate flow resistance in downcomer, lower plenum and core.
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callMore From: Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
Disclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
