Record Details
Scaling analysis of the OSU high temperature test facility during a pressurized conduction cooldown event using RELAP5-3D
ScholarsArchive at Oregon State University
| Field | Value |
|---|---|
| Title | Scaling analysis of the OSU high temperature test facility during a pressurized conduction cooldown event using RELAP5-3D |
| Names |
Castañeda, Juan A.
(creator) Woods, Brian G. (advisor) |
| Date Issued | 2014-05-21 (iso8601) |
| Note | Graduation date: 2014 |
| Abstract | In early 2000, the Generation IV International Forum (GIF) was created to perform research and development for the next generation nuclear systems. Among the selected nuclear systems was the Very High Temperature Gas-Cooled Reactor (VHTR). Then in 2008, the U.S. Department of Energy (DOE) decided that the Next Generation Nuclear Plant (NGNP) would be the VHTR. The VHTR was chosen because it has the capability to produce electricity, hydrogen and may be used for other high-temperature process heat applications. In support of licensing and validation of the VHTR, Oregon State University was tasked to develop a high temperature apparatus that will be able to capture the thermal fluids phenomena of the VHTR and perform integral effects tests for validation of existing safety codes. The design has been called the High Temperature Test Facility (HTTF), which is a scaled design of the Modular High Temperature Gas-Cooled Reactor (MHTGR). The objective of this study was to investigate the ability of the HTTF to simulate the Pressurized Conduction Cooldown (PCC) Event during the natural circulation phase in the MHTGR. This was achieved with the aid of a thermal hydraulic systems code, RELAP5-3D. |
| Genre | Thesis/Dissertation |
| Access Condition | http://creativecommons.org/licenses/by-nd/3.0/us/ |
| Topic | Gas cooled reactors -- Oregon -- Corvallis -- Safety measures -- Testing |
| Identifier | http://hdl.handle.net/1957/49938 |
