The measurement of total normal emittance of three nuclear reactor materials
Measurement of total normal emittance of nuclear reactor materials - carbon steel, boron steel, & borated graphite
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Measurement of total normal emittance of nuclear reactor materials - carbon steel, boron steel, & borated graphite
Temperature coefficients of reactivity due to Doppler broadening of resonances in materials for in-pile thermionic reactor materials
SNAP-8 reactor materials development program - lubricant, coolant, corrosion loop, and structural materials evaluation
Neutron radiation effects on tensile, creep, fatigue, impact, and hardness properties of reactor materials
The Lewis Research Center of the National Aeronautics and Space Administration proposes to build a nuclear research reactor which will be located in the Plum Brook Ordnance Works near Sandusky, Ohio. The purpose of this report is to inform the Advisory Committee on Reactor Safeguards of the U. S. Atomic Energy Commission in regard to the design Lq of the reactor facility, the characteristics of the site, and the hazards of operation at this location. The purpose of this research reactor is to make pumped loop studies of aircraft reactor fuel elements and other reactor components, radiation effects studies on aircraft reactor materials and equipment, shielding studies, and nuclear and solid state physics experiments. The reactor is light water cooled and moderated of the MTR-type with a primary beryllium reflector and a secondary water reflector. The core initially will be a 3 by 9 array of MTR-type fuel elements and is designed for operation up to a power of 60 megawatts. The reactor facility is described in general terms. This is followed by a discussion of the nuclear characteristics and performance of the reactor. Then details of the reactor control system are discussed. A summary of the site characteristics is then presented followed by a discussion of the larger type of experiments which may eventually be operated in this facility. The considerations for normal operation are concluded with a proposed method of handling fuel elements and radioactive wastes. The potential hazards involved with failures or malfunctions of this facility are considered in some detail. These are examined first from the standpoint of preventing them or minimizing their effects and second from the standpoint of what effect they might have on the reactor facility staff and the surrounding population. The most essential feature of the design for location at the proposed site is containment of the maximum credible accident.
Interrupted flow, impingement cooling, and axial power distribution are employed to enhance the heat-transfer configuration of a solid-core nuclear thermal rocket engine. Impingement cooling is introduced to increase the local heat-transfer coefficients between the reactor material and the coolants. Increased fuel loading is used at the inlet end of the reactor to enhance heat-transfer capability where the temperature differences are the greatest. A thermal-hydraulics computer program for an unfueled NERVA reactor core is employed to analyze the proposed configuration with attention given to uniform fuel loading, number of channels through the impingement wafers, fuel-element length, mass-flow rate, and wafer gap. The impingement wafer concept (IWC) is shown to have heat-transfer characteristics that are better than those of the NERVA-derived reactor at 2500 K. The IWC concept is argued to be an effective heat-transfer configuration for solid-core nuclear thermal rocket engines.
Dielectric properties of several materials measured under vacuum, reactor radiation and cryogenic conditions
Theoretical and experimental studies of graphite and unspecified reactor material oxidation behavior to determine atmospheric reentry effects
Irradiation testing of electronic components and subassemblies in Radiation Effects Reactor
Metallic coating materials evaluated for use in transition joints for SNAP-8 transformer reactor assembly
Experimental results of rapid in-core flux mapping techniques in the plum brook reactor
Vacuum and nuclear radiation effect on space vehicle and powerplant organic materials, emphasizing accessory hardware
Properties of high temperature materials for nuclear rocket reactor application - reactor concepts for low power lightweight nuclear power plant
Uranium-containing materials, refractory metals and alloys, discussing interface interaction, thermionic properties and parameters of vacuum electron emission stability
Thermionic materials for space power application - uranium carbide-zirconium carbide fuels and tungsten cladding
High energy x-ray bursts observed by orbiting solar observatory i
Comparison of analytical and experimental calculation of neutron albedo of borated and nonborated concrete blocks for reactor neutrons
Irradiation of refractory uranium dioxide and uranium carbide fuels at high specific powers to high burnups