Space Weather and the Tracking of Deep Space Probes by the NASA Deep Space Network (DSN): The Galileo and SOHO LASCO Experience
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Engineering topics
Publications and source records attributed to Mayo, W..
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A procedure is developed and used to calculate the detailed power distribution in the fuel elements next to a beryllium oxide reflector of a fast-spectrum, thermionic reactor. The results of the calculations show that, although the average power density in these outer fuel elements is not far from the core average, the power density at the very edge of the fuel closest to the beryllium oxide is about 1.8 times the core avearge.
Several fast-spectrum space power reactor concepts that use boron carbide control devices were examined to determine the neutronic feasibility of the designs. The designs considered were (1) a 199-fuel-pin, 12-poison-reflector-control-drum reactor; (2) a 232-fuel-pin reactor with 12 reflector drums and three in-core control rods; (3) a 337-fuel-pin design with 12 incore control rods; and a 181-fuel-pin design with six drums closely coupled to the core to increase reactivity per drum. Adequate reactivity control and excess reactivity could be obtained for each concept, and the goals of 50,000 hours at 2.17 thermal megawatts with a lithium-7 coolant outlet temperature of 1222 K could be met without exceeding the 1-percent-clad-creep criterion. Heating rates in the boron carbide were calculated, but a heat transfer analysis was not done.
An investigation was conducted to determine minimum dimensions and minimum weight obtainable in a design for a reactor using uranium-233 nitride or plutonium-239 nitride as fuel. Such a reactor had been considered by Krasner et al. (1971). Present space power status is discussed, together with questions of reactor design and power distribution in the reactor. The characteristics of various reactor types are compared, giving attention also to a zirconium hydride reactor.
A preliminary cost estimate for a small reactor in Brayton space power systems with (u-233)n or (pu-239)n as the fuel in the T-111 fuel elements totaled to about four million dollars; considered is a 22.8 in. diameter reactor with 247 fuel elements.
Nuclear reactor design as heat source for electric power generation in space
Design and experiments with compact fast spectrum reactor for generating electric power in space
Estimating fuel loading requirements for power tailored fast spectrum reactor with molybdenum reflector
Fuel loading requirements and resulting neutron energy spectrum after adding lithium nitride, hafnium, tantalum, and tungsten to molybdenum reflected critical assembly
Fuel loading requirements and neutron energy spectrum prediction for fast lithium cooled reactor with molybdenum-reflected critical assembly
Performance prediction for fast reactor with axially moving reflector control system
Reflector based poison drum control on equal size reactor cores fueled with U-233 and U-235
Neutron interaction behavior of beryllium oxide and molybdenum reflectors for nuclear reactors
Radial power tailoring for uranium dioxide-T-111 clad reactor with contained fission product gases
Neutronic effects of yttrium hydride moderator insertion in fast spectrum reactors
Neutronic calculations of fuel and poison drum control of refractory metal, fast spectrum space power reactors
Reactivity control of fast nuclear reactors containing yttrium hydride moderating zones
Reactor calculations with TDSN discrete ordinates program