Trade Studies for a 20 MWe Low Specific Mass Nuclear Power System for Space Propulsion
Highly Integrated Quality Assurance - An Empirical Case
Experimental Studies of NaK in a Simulated Space Environment
A Hypothesis on Biological Protection from Space Radiation Through the Use of New Therapeutic Gases
Advanced Materials and Optimization of a Radioisotope Thermal Rocket Motor for a Mars Hopper
In-situ Missions for the Exploration of Titan's Lakes
Feasibility Study of a Three-Stage Radioisotope-Powered Mars Ascent Vehicle
Fusion Space Propulsion Using Fast-Ignition Inertial Confinement Fusion (FI-ICF)
Hyperthermal Environments Simulator for Nuclear Thermal Rocket Fuels Development
Advanced Stirling Radioisotope Generator Flight Design Project Overview
Alternative Radioisotopes for Heat and Power Sources
HTGR Power System Technology for Space Exploration Missions
Design and Test of Advanced Thermal Simulators for an Alkali Metal-Cooled Reactor Simulator
Heat Pipes and Heat Rejection Component Testing at NASA-GRC
Reactivity Control Options for a Space Fission Power System
SPS Fabrication of Tungsten and Tungsten Rhenium Alloys in Support of NTR Fuels Development
10 kW Radioisotope Power Pulsed Brayton Cycle For Space Application
Design of a Low Specific Mass 10 kWe Nuclear Reactor for Space Propulsion
Ultra-Light Heat Pipe Radiators for Fission Surface Power
A Small Fission Power System for NASA Planetary Science Missions
An Overview of Facilities and Capabilities to Support the Development of Nuclear Thermal Propulsion
A Combined Neutronic-Thermal Hydraulic Model of a Tungsten CERMET NTR Fuel Element
Life Testing of Yb~1~4MnSb~1~1 for High Performance Thermoelectric Couples
Advanced Stirling Convertor (ASC-E2) Performance Testing at NASA Glenn Research Center
Radiation Specifications for Fission Power Conversion Component Materials
Material Studies Related to the Use of NaK Heat Exchangers Coupled to Stirling Heater Heads
Fusion Power Sources for Mars Exploration
Post Test Analysis of a Ten Year Sodium Heat Pipe Life Test
Design and Test Plans for a Non-Nuclear Fission Power System Technology Demonstration Unit
Joint Radioisotope Electric Propulsion Studies - Neptune System Explorer
``Scotty, I Need More Power'' - The Fission System Gateway to Abundant Power for Exploration
A Conceptual Multi-Megawatt Reactor System Based on a Tungsten CERMET Reactor
The Four-GPHS Stirling Generator: XP300
Preliminary Mission Architecture for Mars Sample Return Utilizing Nuclear Thermal Rockets
Kuiper Belt Object Orbiter Using Advanced Radioisotope Power Sources and Electric Propulsion
Uranus Mission Concept Options
Trojan Tour Mission Concepts Provide Several Options for Cost-Effective Break-Through Science
Extensibility of the Fission Surface Power (FSP) System from the Moon to Mars
Transient Response to Rapid Cooling of a Stainless Steel Sodium Heat Pipe