Application of CUPID for subchannel-scale thermal–hydraulic analysis of pressurized water reactor core under single-phase conditions

There have been recent efforts to establish methods for high-fidelity and multi-physics simulation with coupled thermal–hydraulic (T/H) and neutronics codes for the entire core of a light water reactor under accident conditions. Considering the computing power necessary for a pin-by-pin analysis of...

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Bibliographic Details
Main Authors: Seok Jong Yoon, Seul Been Kim, Goon Cherl Park, Han Young Yoon, Hyoung Kyu Cho
Format: Article
Language:English
Published: Elsevier 2018-02-01
Series:Nuclear Engineering and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573317302632