“SAIRS” — Scalable Amtec Integrated Reactor space power System

Abstract Conceptual Designs of three, 111 kWe, Scalable AMTEC Integrated Reactor Space Power Systems (SAIRS) are developed. These systems employ fast-spectrum reactors cooled by sodium (Na) heat pipes, C-C armored, potassium (K) heat pipes radiators, and Alkali Metal Thermal-To-Electric Conversion (AMTEC) units. The reactor Na- and the radiator K-heat pipes operate at

[1]  Graydon L. Yoder,et al.  TECHNOLOGY DEVELOPMENT PROGRAM FOR AN ADVANCED POTASSIUM RANKINE POWER CONVERSION SYSTEM COMPATIBLE WITH SEVERAL SPACE REACTOR DESIGNS , 2003 .

[2]  Mohamed S. El-Genk,et al.  An investigation of breakdown voltage in AMTECs , 2002 .

[3]  J. Tournier,et al.  Startup of a horizontal lithium–molybdenum heat pipe from a frozen state , 2003 .

[4]  J. Tom Sena,et al.  SAFE‐100 Module Fabrication and Test , 2003 .

[5]  Mohamed S. El-Genk,et al.  Review of Refractory Materials for Alkali Metal Thermal-to-Electric Conversion Cells , 2001 .

[6]  Mohamed S. El-Genk,et al.  Performance comparison of potassium and sodium vapor anode, multi-tube AMTEC converters , 2002 .

[8]  J. Tournier,et al.  Mechanically Alloyed‐Oxide Dispersion Strengthened Steels for Use in Space Nuclear Power Systems , 2004 .

[9]  T. Cole,et al.  Thermoelectric Energy Conversion with Solid Electrolytes , 1983, Science.

[10]  Mark D. Hoover,et al.  SPACE NUCLEAR POWER SYSTEMS 1989 , 1992 .

[11]  Toshio Fujita,et al.  Evoluation of SP-100 System Designs , 1994 .

[12]  I. V. Yagodkin,et al.  Physical principles of heat pipes , 1982 .

[13]  John J. Buksa,et al.  Load-following and reliability studies of an integrated SP-100 system , 1988 .

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

[15]  Mohamed S. El-Genk,et al.  Energy Conversion Options for Advanced Radioisotope Power Systems , 2003 .

[16]  Mohamed S. El-Genk,et al.  Study of the SP-100 radiator heat pipes response to external thermalexposure , 1990 .

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

[18]  Mohamed S. El-Genk,et al.  A vapor flow model for analysis of liquid-metal heat pipe startup from a frozen state , 1996 .

[19]  J. F. Briesmeister.  MCNP-A General Monte Carlo N-Particle Transport Code , 1993 .

[20]  Mohamed S. El-Genk,et al.  Conceptual Design of HP-STMCs Space Reactor Power System for 110 kWe , 2004 .

[21]  Mohamed S. El-Genk,et al.  Design Optimization of High‐Power, Liquid Anode AMTEC , 2003 .

[22]  Mohamed S. El-Genk,et al.  A Methodology for the Neutronics Design of Space Nuclear Reactors , 2004 .

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