An investigation of dual-mode operation of a nuclear-thermal rocket engine

Abstract

MASTER 18. Estimate of the thermal radiation from the surface of an aluminum or a titanium pressure vessel 19. Block diagram of external region cooling in series with the tie tubes and periphery cooling 20. Block diagram of separate cooUng circuit for external regions 21. Maximum fuel temperatures using special elements at various closed-cycle power levels, hydrogen coolant 22. Special element exit gas temperatures for Fig. 21 cases 20 23. Maximum fuel temperatures using special elements at various closed-cycle power levels, helium coolant 21 24. Special element exit gas temperature for Fig. 23 cases 25. Block diagram of flow paths using special elements and parallel cooUng of other reactor regions 26. Block diagram of flow paths using special elements and series cooling of other reactor regions 27. Performance hmit curves for heat pipe 28. Brayton component mass as a function of electric power level 29. Brayton cycle power-conversion subsystem mass as a function of electric power level and turbine inlet temperature 30. Mass comparison of 10-MWe dual-mode and independent nuclear propulsion/power systems TABLES I-A. Lithium Heat Pipe Input for HTPIPE I-B. Summary of Output Generated by HTPIPE II. Component Specific Masses for a 10-MWe Man-Rated Power System III. Assumptions Used to Calculate Component Masses for Dual-Mode

Integrated Propulsion and Power Modeling for Bimodal Nuclear Thermal Rockets

“…They concluded that the thermal degradation and fuel burn-up effects of extended operation at such high power levels limit the use of BNTR systems to power generation levels below about 50 kWe [61]. No other study has examined power generation levels that high.…”