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

http://ir.library.oregonstate.edu/concern/graduate_thesis_or_dissertations/wd3760329

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  • 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 thermal hydraulic test facility, the High Temperature Test Facility (HTTF). It is expected that the HTTF will provide data on the systemic response of the Modular High Temperature Gas Reactor (MHTGR) during the Depressurized Conduction Cooldown (DCC) event to validate safety analysis codes and the safety concept of the VHTR. The objective of this thesis was to determine the ability of the HTTF to model the DCC event compared to the MHTGR. To do this, a thermal hydraulic systems code, RELAP5-3D/ATHENA, was used to compare the systemic response of the MHTGR and HTTF during the DCC event. Two phases of the DCC event were modeled, the molecular diffusion phase and natural circulation phase. Each phase was modeled as a Separate Effects Test (SET) and as an Integral Effects Test (IET). For each test, the radial temperature profile, peak fuel temperature as a function of time, time to peak fuel temperature, air front velocity, time to onset of natural circulation, and natural circulation flow rates were compared to the MHTGR response. This thesis also provides an analysis of the scaling distortions inherent to the HTTF.
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