The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Online ISSN : 2424-2934
2015.23
Session ID : ICONE23-1506
Conference information
ICONE23-1506 STUDY ON HEAT TRANSFER CHARACTERISTICS OF ONE SIDE HEATED VERTICAL CHANNEL FOR THE VESSEL COOLING SYSTEM OF VHTR
Shinji KuriyamaTetsuaki TakedaShumpei Funatani
Author information
CONFERENCE PROCEEDINGS FREE ACCESS

Details
Abstract
The Very High Temperature Reactor (VHTR) is a next generation nuclear reactor system. It has the characteristic that the thermal capacity of the core is so large. Therefore, even if the depressurization accident occurs and the reactor power goes up instantly, the temperature of the core will change slowly. The VHTR system can passively remove the decay heat of the core by natural convection and radiation from the surface of the reactor pressure vessel (RPV). The objectives of this study is to investigate the heat transfer characteristics of natural convection of an one-side heated vertical rectangular channel inserting porous materials with high porosity and to develop the passive cooling system for the VHTR. We carried out the experiment and numerical analysis using the one-side heated vertical rectangular channel. The heat transfer and fluid flow characteristics of the natural convection cooling were analyzed using the commercial CFD code. The result shows that the amount of removed heat inserting the copper wire (porosity = 0.9964) was about 8% higher than that without the copper wire.
Content from these authors
© 2015 The Japan Society of Mechanical Engineers
Previous article Next article
feedback
Top