CSNR Home
Universities Space Research Association created the Center for Space Nuclear Research (CSNR) in 2005 in partnership with Idaho National Laboratory to foster collaboration with Department of Energy, NASA, Department of Defense, university and industry scientists and programs. CSNR scientists and engineers research and develop advanced space nuclear systems, including power and energy transmission systems, nuclear thermal propulsion, and radioisotopic generators. The CSNR is located at the State of Idaho's Center for Advanced Energy Studies (CAES) building in Idaho Falls, Idaho and operates today in partnership with our NASA and DOE sponsors.
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Example Technical Areas of Research at CSNR:
Nuclear Thermal Propulsion
The United States first explored the use of nuclear power in space in the 1950s. Between 1955 and 1972, the U.S. built and tested more than 20 nuclear-propelled rocket engines in the Rover/NERVA program. Researchers are further developing the concept, which is viewed as one of the most promising technologies for powering human missions to Mars.
CSNR researchers are developing tungsten-based, ceramic, and even liquid and gaseous fuels for use in a nuclear thermal rocket. In the case of tungsten CERMET fuels, these share many of the benefits of the graphite fuels developed in the NERVA program -- a lot of power can be released from a small volume with inherent launch safety features. Developing an NTR requires fuel and related structural components to be fabricated and its performance characterized. CSNR's tungsten CERMET fuel has been tested both in reactors (INL TREAT reactor) and in hydrogen furnaces (NASA MSFC) and has been shown to sustain coolable geometry under the extreme temperatures (>3000 K) and nuclear reactor conditions of NTP systems.
The nuclear thermal rocket (NTR) is a "game changing" technology that could be developed, tested, and deployed in this decade.
Iridium Alloy Modeling
The PuO2 pellets in a Multi-Mission Radioisotope Thermoelectric Generator (MMRTG) are contained in an iridium alloy clad to prevent the spread of contamination in the event of a launch or reentry accident. Thorium is contained in the alloy to prevent grain growth at high temperatures, but thorium can be trapped at the cladding surface as ThO2 if O2 is available. Oxygen is released or absorbed by changes in the stoichiometry of the plutonia pellets during processing. This project modeled oxygen release and movement within the MMRTG and explore changes in processing.
Pu-238 Production in ATR, HFIR, and Advanced Reactors
Plutonium-238 production for use in Radioisotope Thermoelectric Generators (RTGs) is becoming increasingly important in the United States but domestic production ceased in late 1980s. Since then, the USA has relied on the stockpiles, some of which were purchased from Russia at the end of the cold war. The plutonium stockpile has steadily decreased due to utilization in RTGs and also due to the decay of Pu-238 with its 88-year half-life. Summer Fellows at CSNR have worked on a series of studies of the feasibility for irradiating Np-237 in the Advanced Test Reactor (ATR) at the INL and the High Flux Isotope Reactor (HFIR) at ORNL. The studies have evaluated the use of various irradiation positions in the ATR, configurations of target rods, irradiation scenarios and methods for reducing the production of gamma-emitting isotopes, such as Pu-236.
Advanced Heat Exchanger and Radiator Technologies
Advanced Nuclear Electric Propulsion
In-Space Energy Transmission
Advanced Purification Technologies for Future Nuclear Fuel Systems
Chemical and Fuel Performance Testing
Ground nuclear and non-nuclear testing strategies, capabilities and national needs.
