Development of a Reactor Vessel Thermal–Hydraulics Analysis Method in Natural Circulation Conditions with a Coarse-Mesh Subchannel Cfd Model

Author:

HAMASE Erina,Miyake Yasuhiro,Imai Yasutomo,Doda Norihiro,Ono Ayako,Tanaka Masaaki

Publisher

Elsevier BV

Reference15 articles.

1. Hydrodynamic Models and Correlations for Bare and Wirewrapped Hexagonal Rod Bundles -Bundle Friction Factors, Subchannel Friction Factors and Mixing Parameters;S Cheng;Nucl. Eng. and Des,1986

2. A General Correlation of Friction Factors for Various Types of Surfaces in Crossflow;A Gunter;ASME Transactions,1945

3. Development of Reactor Vessel Thermal Hydraulic Evaluation Method under Natural Circulation Decay Heat Removal Conditions in Sodium-cooled Fast Reactors (1) Applicability of Subchannel based CFD Analysis Method using Porous Body Model;E Hamase;Atomic Energy Society of Japan 2019 Annual Meeting, 3I08,2019

4. Development of Reactor Vessel Thermal Hydraulic Evaluation Method under Natural Circulation Decay Heat Removal Conditions in Sodium-cooled Fast Reactor -Application of Subchannel based CFD Analysis Method to a Fuel Subassembly at Low Flow Rate Conditions;E Hamase;Mechanical Engineering Congress,2020

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