@inproceedings{4ef0c6c0fdfd491e8671322ffc04e7ce,
title = "Experimental evaluation of the bypass flow in the VHTR core",
abstract = "In the core of Very High Temperature Gas-Cooled Reactor for the hydrogen production, there is the bypass flow that does not pass through coolant holes within the graphite blocks. The main bypass flow path is the gap channel between the core blocks. The amount of effective coolant and the temperature of the outlet coolant decrease as the bypass flow rate increases. Since the bypass flow affects the success of hydrogen production, it is important to evaluate the amount and the distribution of the bypass flow. In this study, the experimental facility to measure the amount of the bypass flow was designed and set up. The experiments and CFD analysis to evaluate the bypass were carried out with several gap sizes and the combinations of the blocks. As the results, the bypass flow ratio increases as gap size, it is independent of the inlet mass flow rate but decreases as the number of fuel block in the unit cell increase.",
author = "Yoon, \{Su Jong\} and Cho, \{Ahn Tae\} and Kim, \{Kwang Yong\} and Kim, \{Min Hwan\} and Park, \{Goon Cherl\}",
year = "2007",
language = "English",
isbn = "0894480529",
series = "American Nuclear Society Embedded Topical Meeting - 2007 International Topical Meeting on Safety and Technology of Nuclear Hydrogen Production, Control, and Management",
pages = "233--239",
booktitle = "American Nuclear Society Embedded Topical Meeting - 2007 International Topical Meeting on Safety and Technology of Nuclear Hydrogen Production, Control, and Management",
note = "2007 International Topical Meeting on Safety and Technology of Nuclear Hydrogen Production, Control, and Management ; Conference date: 24-06-2007 Through 28-06-2007",
}