High Temperature Water Heat Pipes Radiator for a Brayton Space Reactor Power System

A high temperature water heat pipes radiator design is developed for a space power system with a sectored gas‐cooled reactor and three Closed Brayton Cycle (CBC) engines, for avoidance of single point failures in reactor cooling and energy conversion and rejection. The CBC engines operate at turbine inlet and exit temperatures of 1144 K and 952 K. They have a net efficiency of 19.4% and each provides 30.5 kWe of net electrical power to the load. A He‐Xe gas mixture serves as the turbine working fluid and cools the reactor core, entering at 904 K and exiting at 1149 K. Each CBC loop is coupled to a reactor sector, which is neutronically and thermally coupled, but hydraulically decoupled to the other two sectors, and to a NaK‐78 secondary loop with two water heat pipes radiator panels. The segmented panels each consist of a forward fixed segment and two rear deployable segments, operating hydraulically in parallel. The deployed radiator has an effective surface area of 203 m2, and when the rear segments are...

[1]  Mohamed S. El-Genk,et al.  Solid‐Core, Gas‐Cooled Reactor for Space and Surface Power , 2006 .

[2]  David I. Poston,et al.  Design and analysis of the SAFE-400 space fission reactor , 2002 .

[3]  A. W. Cronenberg,et al.  Irradiation effects on fuels for space reactors , 1984 .

[4]  Jennifer Liscum‐Powell,et al.  Neutronics Analysis and Design Optimization of the Pellet Bed Reactor for Bimodal Applications , 2008 .

[5]  Mohamed S. El-Genk,et al.  Liquid Metal Heat Pipes Radiator for Space Nuclear Reactor Power Systems , 2005 .

[6]  Mohamed S. El-Genk,et al.  SCoRe — Concepts of Liquid Metal Cooled Space Reactors for Avoidance of Single‐Point Failure , 2005 .

[7]  K. L. Meier Space reactor preliminary mechanical design , 1983 .

[8]  Jared P. Squire,et al.  Principal VASIMR Results and Present Objectives , 2005 .

[9]  Mohamed S. El-Genk,et al.  Radiator Heat Pipes with Carbon‐Carbon Fins and Armor for Space Nuclear Reactor Power Systems , 2005 .

[10]  Jennifer Liscum‐Powell,et al.  Options for enhanced performance of pellet bed reactor bimodal systems , 2008 .

[11]  Mohamed S. El-Genk,et al.  Uranium nitride fuel swelling correlation , 1990 .

[12]  Mohamed S. El-Genk,et al.  Reactor Lithium Heat Pipes for HP-STMCs Space Reactor Power System , 2004 .

[13]  Maribeth E. Hunt,et al.  SP‐100 high‐temperautre advanced radiator development , 1991 .

[15]  J. P. Hawley,et al.  Water immersion safety for SNAP reactors , 1967 .

[16]  Stanley K. Borowski,et al.  “Bimodal” NTR and LANTR propulsion for human missions to Mars/Phobos , 1999 .

[17]  Mohamed S. El-Genk,et al.  High-Energy-Utilization, Dual-Mode System Concept for Mars Missions , 2001 .

[18]  David I. Poston Nuclear safety calculations for heatpipe power system reactors , 2002 .