Thermal-hydraulics Analysis of a Radioisotope-powered Mars Hopper Propulsion System [electronic resource]

Cermet; Mars Hopper; Nuclear; Power; Radioisotope; Rtg.

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Bibliographic Details
Online Access: Online Access (via OSTI)
Corporate Author: Idaho National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Department of Energy. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 2011.
Subjects:

MARC

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245 0 0 |a Thermal-hydraulics Analysis of a Radioisotope-powered Mars Hopper Propulsion System  |h [electronic resource] 
260 |a Washington, D.C. :  |b United States. Department of Energy. ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,  |c 2011. 
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500 |a 02/01/2011. 
500 |a "inl/con-10-20461" 
500 |a Nuclear and Emerging Technologies for Space 2011,Albuquerque, NM,02/07/2011,02/10/2011. 
500 |a Robert C. O'Brien; Andrew C. Klein; William T. Taitano; Justice Gibson; Brian Myers; Steven D. Howe. 
520 3 |a Thermal-hydraulics analyses results produced using a combined suite of computational design and analysis codes are presented for the preliminary design of a concept Radioisotope Thermal Rocket (RTR) propulsion system. Modeling of the transient heating and steady state temperatures of the system is presented. Simulation results for propellant blow down during impulsive operation are also presented. The results from this study validate the feasibility of a practical thermally capacitive RTR propulsion system. 
520 0 |a Cermet; Mars Hopper; Nuclear; Power; Radioisotope; Rtg. 
536 |b DE-AC07-05ID14517. 
650 7 |a Design.  |2 local. 
650 7 |a Heating.  |2 local. 
650 7 |a Hoppers.  |2 local. 
650 7 |a Propulsion Systems.  |2 local. 
650 7 |a Radioisotopes.  |2 local. 
650 7 |a Rockets.  |2 local. 
650 7 |a Thermal Hydraulics.  |2 local. 
650 7 |a Simulation.  |2 local. 
650 7 |a Transients.  |2 local. 
650 7 |a General Studies Of Nuclear Reactors.  |2 edbsc. 
710 2 |a Idaho National Laboratory.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |4 spn. 
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