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Filtering by: Subject Water cooled reactors -- Oregon -- Corvallis Advisor Woods, Brian G.

Scaling study of the depressurized conduction cooldown event in the high temperature test facility using RELAP5-3D/ATHENA

Creator:

Aldridge, Robert J.

Abstract:

In 2008, the Department of Energy (DOE) and Nuclear Regulatory Commission (NCR) decided that the Next Generation Nuclear Plant (NGNP) would be the Very High Temperature Reactor (VHTR). In support of the licensing and validation effort of the VHTR, Oregon State University was tasked with designing, building, and operating a...

Resource Type:

Masters Thesis

Full Text:

Simplified Boiling Water Reactor GCFR Gas Cooled Fast Reactor GR-SAC Gas Reactor Severe Accident Code
Nitrogen concentration sensitivity study of the lock exchange phenomenon in the high temperature test facility

Creator:

Utberg, John E., Jr

Abstract:

The Modular High Temperature Gas-Cooled Reactor (MHTGR) is a graphite moderated reactor that utilizes helium as its coolant. One consideration of importance is how the MHTGR will perform during a Depressurized Conduction Cooldown (DCC) accident, which generally can be divided into three phases: depressurization, air ingress, and natural circulation. After...

Resource Type:

Masters Thesis

Full Text:

Temperature Gas-Cooled Reactor NGNP Next Generation Nuclear Plant OSU Oregon State University PCC
Scaling analysis of the OSU high temperature test facility during a pressurized conduction cooldown event using RELAP5-3D

Creator:

Castañeda, Juan A.

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...

Resource Type:

Masters Thesis

Full Text:

), Supercritical-Water-Cooled Reactor (SCWR) and the Very-High-Temperature Reactor (VHTR). [2] In the United