Speaker
Kwangjin Jung
(University of Science and Technology (UST))
Description
The hydrogen isotope storage and delivery system (SDS) is a complex system that includes many individual components. One of the most important parts of the SDS is a metal hydride bed, which stores and delivers the hydrogen isotopes and pure gases required for a nuclear fusion reactor. We have been developing a metal hydride bed using depleted uranium (DU). The hydrogen delivery performance of the metal hydride bed is an important part of satisfying the fueling requirements in accordance with the fusion fuel cycle scenario. Because DU hydride can be heated to the very high temperatures at which it is possible to pump hydrogen isotopes, we designed and fabricated a mock-up DU hydride bed without any hydrogen delivery pump. However, the application of preheating scenarios seems to be essential for more rapid and reliable hydrogen delivery performance under pressure and temperature constraints. In this study, the effect of the preheating scenarios was experimentally investigated using the DU hydride bed with hydrogen gas. The application of preheating scenarios was found to improve the hydrogen delivery performance of the DU hydride bed. In addition, two empirical equations based on our experimental results were suggested to predict the effect. One equation is mainly composed of two terms to consider the inner pressure of the DU bed and the hydrogen atomic ratio in DU hydride. The equation is used to determine Pressure-Composition-Temperature (PCT) curves. The other equation is mainly composed of a correction factor, a Boltzmann factor, and two terms to consider the inner pressure of the DU bed and the hydrogen atomic ratio in DU hydride. The equation is used to predict the variation of the hydrogen atomic ratio in DU hydride with the lapse of time. The numerical simulation results by the equations had a good agreement with the experimental results.
Co-authors
Do-Hee Ahn
(University of Science and Technology (UST), 217 Gajeongro, Yuseong, Daejeon, South Korea;Korea Atomic Energy Research Institute (KAERI), 989-111 Daedeokdaero, Yuseong, Daejeon, South Korea)
Hee-Seok Kang
(Korea Atomic Energy Research Institute (KAERI), 989-111 Daedeokdaero, Yuseong, Daejeon, South Korea)
Hongsuk Chung
(University of Science and Technology (UST), 217 Gajeongro, Yuseong, Daejeon, South Korea;Korea Atomic Energy Research Institute (KAERI), 989-111 Daedeokdaero, Yuseong, Daejeon, South Korea)
Kwangjin Jung
(University of Science and Technology (UST), 217 Gajeongro, Yuseong, Daejeon, South Korea;Korea Atomic Energy Research Institute (KAERI), 989-111 Daedeokdaero, Yuseong, Daejeon, South Korea)
Sei-Hun Yun
(National Fusion Research Institute (NFRI), 169-148 Gwahakro, Yuseong, Daejeon, South Korea)
Yeanjin Kim
(University of Science and Technology (UST), 217 Gajeongro, Yuseong, Daejeon, South Korea;Korea Atomic Energy Research Institute (KAERI), 989-111 Daedeokdaero, Yuseong, Daejeon, South Korea)
