Development of bearings for nuclear reactors in space
Bearing developments for nuclear reactors in space environment
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Bearing developments for nuclear reactors in space environment
Explosive containment capsule for nuclear reactor irradiation
Nuclear reactor Brayton cycle space power system design point characteristics, discussing cycle parameters, working fluid, turbine inlet temperature, operating pressure level, etc
Water radiolysis measurement in nuclear reactor tests, discussing experiment design as doubly telescoping sequences of blocks
The Space Nuclear Reactor Power System Technology Program designated SP-100 was created in 1983 by NASA, the U.S. Department of Defense, and the Defense Advanced Research Projects Agency. Attention is presently given to the development history of SP-100 over the course of its first year, in which it has been engaged in program objectives' definition, the analysis of civil and military missions, nuclear power system functional requirements' definition, concept definition studies, the selection of primary concepts for technology feasibility validation, and the acquisition of initial experimental and analytical results.
Stability of coupled-core nuclear reactor systems
Preliminary designs of space power nuclear reactor shields
Impact tests on model nuclear reactor containment system with models weighing 350 lb to 1305 lb and impact velocities varying from 241 to 580 ft/sec
To help determine the systems requirements for a 300-kWe space nuclear reactor power system, a mission and spacecraft have been examined which utilize electric propulsion and this nuclear reactor power for multiple transfers of cargo between low earth orbit (LEO) and geosynchronous earth orbit (GEO). A propulsion system employing ion thrusters and xenon propellant was selected. Propellant and thrusters are replaced after each sortie to GEO. The mass of the Orbital Transfer Vehicle (OTV), empty and dry, is 11,000 kg; nominal propellant load is 5000 kg. The OTV operates between a circular orbit at 925 km altitude, 28.5 deg inclination, and GEO. Cargo is brought to the OTV by Shuttle and an Orbital Maneuvering Vehicle (OMV); the OTV then takes it to GEO. The OTV can also bring cargo back from GEO, for transfer by OMV to the Shuttle. OTV propellant is resupplied and the ion thrusters are replaced by the OMV before each trip to GEO. At the end of mission life, the OTV's electric propulsion is used to place it in a heliocentric orbit so that the reactor will not return to earth. The nominal cargo capability to GEO is 6000 kg with a transit time of 120 days; 1350 kg can be transferred in 90 days, and 14,300 kg in 240 days. These capabilities can be considerably increased by using separate Shuttle launches to bring up propellant and cargo, or by changing to mercury propellant.
A space-based radar mission and spacecraft, using a 300 kWe nuclear reactor power system, has been examined, with emphasis on aspects affecting the power system. The radar antenna is a horizontal planar array, 32 X 64 m. The orbit is at 61 deg, 1088 km. The mass of the antenna with support structure is 42,000 kg; of the nuclear reactor power system, 8,300 kg; of the whole spacecraft about 51,000 kg, necessitating multiple launches and orbital assembly. The assembly orbit is at 57 deg, 400 km, high enough to provide the orbital lifetime needed for orbital assembly. The selected scenario uses six Shuttle launches to bring the spacecraft and a Centaur G upper-stage vehicle to assembly orbit. After assembly, the Centaur places the spacecraft in operational orbit, where it is deployed on radio command, the power system started, and the spacecraft becomes operational. Electric propulsion is an alternative and allows deployment in assembly orbit, but introduces a question of nuclear safety.
Measurement of total normal emittance of nuclear reactor materials - carbon steel, boron steel, & borated graphite
Linear optimal feedback control synthesis for nuclear reactor system models
Experiments performed under conditions found in nuclear reactor superheaters determine the corrosion rate of stainless steel and nickel alloys used in them. Electropolishing was the primary surface treatment before the corrosion test. Corrosion is determined by weight loss of specimens after defilming.
Modification of M- 1 liquid hydrogen turbopump for use in Phoebus nuclear reactor
Mathematical models for estimating thermal conductivity of cermet fuel materials used in nuclear reactor
Electrical properties of xenon filled thermionic diodes in nuclear reactor radiation field
Large containment capsule for nuclear reactor irradiation of explosive materials
Nuclear reactor control rod assembly with improved driving mechanism