Abstract
This report presents the physical characteristics of two-phase critical flow whcih can be occured in a light water nuclear power plant during LOCA and also reviews the critical flow models and their applications in detail. The existing experimental data base are reviewed and classified. The typical critical flow models which have been applied to the computer code for the accident are also reviewed. Some suggestions are presented for the development of advanced analytical models and the extension of useful experimental database. (Author).
Citation Formats
Chung, Moon Ki, and Chang, Seok Kyu.
The study of two-phase critical flow characteristics in nuclear reactor coolant system.
Korea, Republic of: N. p.,
1993.
Web.
Chung, Moon Ki, & Chang, Seok Kyu.
The study of two-phase critical flow characteristics in nuclear reactor coolant system.
Korea, Republic of.
Chung, Moon Ki, and Chang, Seok Kyu.
1993.
"The study of two-phase critical flow characteristics in nuclear reactor coolant system."
Korea, Republic of.
@misc{etde_10127070,
title = {The study of two-phase critical flow characteristics in nuclear reactor coolant system}
author = {Chung, Moon Ki, and Chang, Seok Kyu}
abstractNote = {This report presents the physical characteristics of two-phase critical flow whcih can be occured in a light water nuclear power plant during LOCA and also reviews the critical flow models and their applications in detail. The existing experimental data base are reviewed and classified. The typical critical flow models which have been applied to the computer code for the accident are also reviewed. Some suggestions are presented for the development of advanced analytical models and the extension of useful experimental database. (Author).}
place = {Korea, Republic of}
year = {1993}
month = {Jan}
}
title = {The study of two-phase critical flow characteristics in nuclear reactor coolant system}
author = {Chung, Moon Ki, and Chang, Seok Kyu}
abstractNote = {This report presents the physical characteristics of two-phase critical flow whcih can be occured in a light water nuclear power plant during LOCA and also reviews the critical flow models and their applications in detail. The existing experimental data base are reviewed and classified. The typical critical flow models which have been applied to the computer code for the accident are also reviewed. Some suggestions are presented for the development of advanced analytical models and the extension of useful experimental database. (Author).}
place = {Korea, Republic of}
year = {1993}
month = {Jan}
}