HTTF Analyses Using RELAP5-3D

1. HTTF Analyses Using RELAP5-3D Paul D. Bayless RELAP5 International Users Seminar September 2010

2. Outline • HTTF description • Initial scoping analyses • Steady state and transient simulations • Code user observations

3. High Temperature Test Facility (HTTF) • Integral experiment being built at Oregon State University • Electrically-heated, scaled model of a high temperature gas reactor • Reference is the MHTGR (prismatic blocks) • Large ceramic block representing core and reflectors • ¼ length scale • Prototypic coolant inlet (259°C) and outlet (687°C) temperatures • Less than scaled power • Maximum pressure of ~700 kPa • Primary focus is on depressurized conduction cooldown transient

4. Initial Scoping Studies • Reference reactor simulations • Simulations using a scaled-down MHTGR model • Concerns with laminar flow and initial structure temperatures

5. MHTGR RELAP5-3D Scoping Model Features • Three systems • Primary coolant • Reactor cavity • Reactor cavity cooling system (RCCS) • Coolant gaps between the core blocks modeled • Each ring modeled separately • 2-D (radial/axial) conduction in all vertical heat structures • Conduction between fuel blocks and to adjacent reflector blocks • Radiation across gaps between reflector rings • Radiation from core barrel to vessel to RCCS • Core barrel divided azimuthally

6. MHTGR Reactor Vessel Core Region Cross Section Reactor vessel Core barrel Side reflector Fuel blocks Coolant channels Central reflector Control rod channels

7. MHTGR RELAP5-3D Core Region Radial Nodalization Reactor vessel Core barrel Side reflector Fuel blocks Coolant channels Central reflector Coolant gaps

8. Fuel Block Unit Cell MHTGR RELAP5-3D Fuel Coolant hole

9. Reactor Vessel Nodalization 120 125 130, 158 140, 160, 132, 145, 162, 134, 150 164, 136 166 115 105 200 170 255 250 295 175 100 110

10. Reactor Cavity and RCCS Nodalization 980 920 970 925 960 955 930 900 950 900 940 945

11. Base Calculation Set • Steady state • Low pressure conduction cooldown (LPCC) • 10-s forced depressurization to atmospheric pressure • Both reactor inlet and outlet open to He-filled volumes • Conduction cooldown with intact coolant system • 60-s flow coastdown • Reactor inlet closed • Reactor outlet pressure reduced over 4-hr period • Three outlet pressures • Normal operation (~6.3 MPa) • 3.0 MPa • 0.7 MPa

12. Base Calculations – Peak Fuel Temperature

13. Base Calculations – Peak Vessel Temperature

14. Base Calculations – RCCS Heat Removal

15. Base Calculations – Axial Conduction Effect

16. MHTGR/HTTF Sensitivity Calculations • 25% power case • Nominal coolant temperatures • Transient response uninteresting, no heatup • 10% power case • Nominal coolant temperatures; laminar flow in bypass channels • Full power decay heat • Transient response similar to reference plant but with higher, earlier temperature peaks • ¼ scale model • Nominal coolant temperatures • Laminar flow in all flow channels • Core and reflector temperatures much higher than reference plant • Much higher transient fuel temperatures

17. HTTF RELAP5-3D Model Description • Same components and approach as for MHTGR • No gaps between core and reflectors • All coolant holes are open at both ends without flow restrictions • Loss coefficients adjusted to provide 11% core bypass flow • Control rod holes in reflectors modeled separately from solid regions • Radial heat transfer by conduction in core, central and side reflectors • Simplified model of the RCCS

18. HTTF RELAP5-3D core region radial nodalization Reactor vessel Core barrel Permanent reflector Side reflector Coolant channels Core region Central reflector Coolant gaps Heater rod Coolant hole

19. HTTF Model Initial Unit Cells Reflector Core Coolant channel Helium gap Ceramic Heater rod

20. HTTF RELAP5-3D Model Unit Cells Reflector Core Coolant channel Heater rod Ceramic Radiation

21. Initial Steady State Calculations • Initial HTTF power was ~600 kW, but calculations showed that the power needed to be >1250 kW to get turbulent flow in the core cooling channels • Facility power subsequently upgraded to 2.2 MW • Sensitivity calculations looked at different reflector cooling hole geometries to investigate effect on initial temperature and bypass flow rate • Cooling hole geometry still being determined

22. Transient Boundary Conditions • Decay power (compared to MHTGR) • Power factor of 1/32 • Time factor of 1/2 • Scram at transient initiation • Power held constant until decay power drops below 2.2 MW • 10-s depressurization in depressurized conduction cooldown (DCC) • 60-s flow coastdown in pressurized conduction cooldown (PCC)

23. DCC Core Average Temperatures

24. DCC Radial Temperature Profile (1)

25. DCC Radial Temperature Profile (2)

26. Peak Fuel Temperature Comparison

27. Reactor Vessel Average Temperatures

28. Heat Removal and Generation

29. Transient Calculation Observations • Temperature response seemed reasonable and representative • Not a significant difference between DCC and PCC calculations

30. Code User Observations • These studies exercised new or seldom-used models in the code • 2-D conduction • Control variable-driven heat flux boundary condition on a heat structure • Decoupled heat structures • Code shortcomings • Inability to model both conduction and radiation from a heat structure surface • No 2-D conduction in structures with an imposed boundary condition