Integral System Testing for Prismatic Block Core Design HTGR
- Oregon State Univ., Corvallis, OR (United States)
The High Temperature Test Facility (HTTF) at Oregon State University (OSU) is an integral system test facility scaled ¼ in length and diameter as compared against its reference design, the General Atomics Modular High Temperature Gas Reactor (MHTGR). The HTTF currently has over 400 data acquisition channels including thermocouples, pressure transducers, differential pressure transducers, flow meters, and gas sensors. It consists of of a primary loop containing the reactor vessel with an electrically heated ceramic core, a steam generator, gas circulator and associated piping. The maximum core power output at the HTTF in its current configuration is 880 kW. The primary loop is capable of operating at prototypical temperatures at a pressure of 8 bar. The steam generator discharges its steam to the atmosphere. A Reactor Cavity Cooling System (RCCS) is also present at the HTTF. This consists of forced water-cooled panels that surround the reactor vessel. This RCCS is not a scaled version of an actual HTGR design but rather is used to specify the boundary conditions to control radiation heat transfer from the vessel wall. The purpose of this research project was to complete eight integral-level thermal-fluid tests at the HTTF in order to investigate the phenomenological behavior of these events at a system level. Although not part of the scope of this project, the data collected can also be used for code validation. The tests completed under this project include the following tests: (1) PG-28 Low Power (<350kW) Lower Plenum Mixing Test (2) PG-29 Low Power (<350kW) Double Ended Inlet-Outlet Crossover Duct Break, Hybrid Heater (3) PG-32 Low Power (<350kW) Asymmetric Core Heatup (4) PG-30 Low Power (<350kW) Lower Plenum Mixing, Constant Temperature Test (5) PG-31 Low Power (<350kW) Pressure Vessel Bottom Break with Restored Forced Convection Cooling Test (6) PG-33 Zero Power Long Term Cooldown Test (7) PG-34 Low Power (<350kW) Asymmetric Core Heatup Full Hybrid Heater (8) PG-35 Zero Power Crossover Duct Exchange Flow and Diffusion Test 1. In support of this test campaign, the HTTF Scaling Report was revised to include additional detail and analysis concerning the intracore natural circulation. The HTTF Instrumentation Plan was also revised under this project. Additionally, a computational fluid dynamics (CFD) scoping analysis that examined upper plenum mixing events was completed.
- Research Organization:
- Oregon State Univ., Corvallis, OR (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- DOE Contract Number:
- NE0008538
- OSTI ID:
- 1580081
- Report Number(s):
- OSU-HTTF-NEUP-001; 16-10244
- Country of Publication:
- United States
- Language:
- English
Similar Records
RELAP5-3D Modeling of High Temperature Test Facility (HTTF) Test PG-26
Modeling of HTTF test PG-26 using RELAP5-3D and SAM