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Construction and demonstration of a reactor system for testing methanol synthesis catalystsLittle, Douglas James January 2011 (has links)
Digitized by Kansas Correctional Industries
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Design and construction of a fast neutron irradiation facility for use at elevated temperatureIsmuntoyo, Robertus January 2011 (has links)
Typescript (photocopy). / Digitized by Kansas Correctional Industries
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A state variable feedback design for the control system for an in-core thermionic reactorSumma, William Joseph, 1944- January 1968 (has links)
No description available.
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Experimental investigation of subcooled void growth for upflow and downflow at low velocities and low pressureBibeau, Eric Louis January 1988 (has links)
A two-phase experimental loop was designed and built to simulate the operating
conditions of the SLOWPOKE reactor. Void growth was measured for both upflow and downflow for velocities between 0.07 to 0.46 m/s and at a pressure of 155 kPa. The buoyancy effect causes the Onset of Significant Void, OSV, to occur at higher subcooling for downflow than for upflow. This effect is maximum close to the bubble rise velocity (0.23 m/s) and decreases at higher velocities. The results indicate that bubble detachment is not the only critical parameter affecting OSV. The OSV correlations from the literature
did not predict the experimental results well. Investigation of the heat transfer mechanisms indicates that fully developed sub cooled boiling occurs prior to OSV. / Applied Science, Faculty of / Mechanical Engineering, Department of / Graduate
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Acoustical boiling detection system for natural convection pool-type reactorsVidalin, William Edward January 1978 (has links)
No description available.
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The design and construction of a subcritical nuclear reactorSchuler, Thomas McKinley, Jr. 15 November 2013 (has links)
A subcritical heterogeneous nuclear reactor was designed and constructed for use in the nuclear engineering program at Virginia Polytechnic Institute. Natural uranium fuel and reactor grade graphite were used as building materials.
Considering that no two samples of moderator have the same characteristics, the resulting parameters measured on this reactor are in good agreement with published data. The reactor performs the primary function as a versatile laboratory instrument that can measure as many reactor parameters as possible. / Master of Science
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Development of systems analysis program for space reactor studiesLewis, Bryan R. 14 June 1993 (has links)
An overall systems design code was developed to model
an advanced in-core thermionic energy conversion based
nuclear reactor system for space applications at power
levels of 10 to 50 kWe. The purpose of this work was to
provide the overall shell for the systems code and to also
provide the detailed neutronic analysis section of the code.
The design code that was developed is to be used to evaluate
a reactor system based upon a single cell thermionic fuel
element which uses advanced technology to enhance the
performance of single cell thermionic fuel elements.
A literature survey provided information concerning how
other organizations performed system studies on similar
space reactor designs. / Graduation date: 1994
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System modeling and reactor design study of an advanced incore thermionic space reactorLee, Hsing Hui 12 October 1992 (has links)
Incore thermionic space reactor design concepts which operate at a
nominal power output range of 20 to 50 kWe are described. Details of the
neutronic, thermionic, thermal hydraulics and shielding performance are
presented. Due to the strong absorption of thermal neutrons by natural
tungsten, and the large amount of that material within the reactor core,
two designs are considered.
An overall system design code has been developed at Oregon State
University to model advanced incore thermionic energy conversion based
nuclear reactor systems for space applications. The code modules include
neutronics and core criticality, a thermionic fuel element performance
module with integral thermal hydraulics calculation capability, a
radiation shielding module, and a module for the waste heat rejection.
The results show that the driverless single cell ATI configuration,
which does not have driver rods, proved to be more efficient than the
driven core, which has driver rods. It also shows that the inclusion of
the true axial and radial power distribution decrease the overall
conversion efficiency. The flattening of the radial power distribution by
three different methods would lead to a higher efficiency. The results
show that only one thermionic fuel element (TFE) works at the optimum
emitter temperature; all other TFEs are off the optimum performance and
result in 40 % decrease of the efficiency of the overall system. / Graduation date: 1993
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Nuclear design analysis of low-power (1-30 KWe) space nuclear reactor systemsGedeon, Stephen R. 23 November 1993 (has links)
Preliminary nuclear design studies have been completed on ten
configurations of nuclear reactors for low power (1-30 kWe) space
applications utilizing thermionic energy conversion. Additional design
studies have been conducted on the TRICE multimegawatt in-core
thermionic reactor configuration. In each of the cases, a reactor
configuration has been determined which has the potential for operating
7 years with sufficient reactivity margin. Additional safety
evaluations have been conducted on these configurations including the
determination of sufficient shutdown reactivity, and consideration of
water immersion, water flooding, sand burial, and reactor compaction
accident scenarios. It has been found, within the analysis conducted
using the MCNP Monte Carlo neutron transport code, that there are
configurations which are feasible and deserve further analysis. It has
also been found that solid core reactors which rely solely on conduction
for heat removal as well as pin type cores immersed in a liquid metal
bath have merit. The solid cores look attractive when flooding and
compaction accident scenarios are considered as there is little chance
for water to enter the core and cause significant neutron moderation. A
fuel volume fraction effect has also been found in the consideration of
the sand burial cases for the SP-100 derived configurations. / Graduation date: 1994
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Time-dependent continuous-energy solutions in neutron transport theory for plane and spherical infinite mediaRoybal, Jerry Anthony January 1981 (has links)
No description available.
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