Neutron Flux Characterization of the Kansas State University TRIGA Mark II's Northeast Beam Port PDF Download
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Author: John Charles Boyington
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
A high-resolution, multi-dimensional flux characterization was performed for the Kansas State University TRIGA Mark II's Northeast Beam Port for the purpose of informing future experimental work, such as detector characterization, done using the beam. First, the Beam Port geometry was added to the existing reactor model. Then the in-core fission rates were tallied using MCNP to provide a source term for the beam transport. The program ADVANTG was used for automated generation of weight windows to accelerate the convergence of tallies in the beam port model. A tally was then collected at the end of the beam port and results are presented. Results from this tally were used to produce simulated responses and response functions for two detectors: a gold foil-based passive spectrometer and a standard set of Bonner Spheres. An experiment was conducted with both measurement devices to obtain responses. These measurements showed decent shape agreement and a small magnitude bias relative to the simulated results. Finally, the measurements, simulated flux, and response functions were used to unfold a final set of spectra using three different unfolding techniques. The Doroshenko directed divergence and Gravel (modified Sand-II) methods produced physically-realistic spectra which successfully fit the measured data, while MAXED did not.
Author: John Charles Boyington
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
A high-resolution, multi-dimensional flux characterization was performed for the Kansas State University TRIGA Mark II's Northeast Beam Port for the purpose of informing future experimental work, such as detector characterization, done using the beam. First, the Beam Port geometry was added to the existing reactor model. Then the in-core fission rates were tallied using MCNP to provide a source term for the beam transport. The program ADVANTG was used for automated generation of weight windows to accelerate the convergence of tallies in the beam port model. A tally was then collected at the end of the beam port and results are presented. Results from this tally were used to produce simulated responses and response functions for two detectors: a gold foil-based passive spectrometer and a standard set of Bonner Spheres. An experiment was conducted with both measurement devices to obtain responses. These measurements showed decent shape agreement and a small magnitude bias relative to the simulated results. Finally, the measurements, simulated flux, and response functions were used to unfold a final set of spectra using three different unfolding techniques. The Doroshenko directed divergence and Gravel (modified Sand-II) methods produced physically-realistic spectra which successfully fit the measured data, while MAXED did not.
Author: Kenneth Edward Habiger
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 172
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Author: Gary Don Bouchey
Publisher:
ISBN:
Category :
Languages : en
Pages : 194
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Author: Troy Casey Unruh
Publisher:
ISBN:
Category :
Languages : en
Pages :
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Book Description
Semiconductor neutron detector design, fabrication and testing are all performed at Kansas State University (KSU). The most prevalent neutron detectors built by the KSU Semiconductor Materials And Radiological Technologies Laboratory (SMART Lab) are comprised of silicon diodes with [superscript]6LiF as a neutron converter material. Neutron response testing and calibration of the detectors is performed in a neutron detector test facility. The facility utilizes diffraction with a pyrolytic graphite (PG) monochromator to produce a diffracted neutron beam at the northwest beamport of the KSU Training Research Isotope production General Atomics (TRIGA) Mark-II nuclear reactor. A 2-D neutron beam monitor can also be used in conjunction with the test facility for active calibrations. Described in the following work are the design, construction and operation of a neutron detector test facility and a 2-D neutron detection array. The diffracted neutron beam at the detector test facility has been characterized to yield a neutron beam with an average Gaussian energy of 0.0253 eV. The diffracted beam yields a flux of 1.2x10[superscript]4 neutrons/cm[superscript]2/s at 100 kW of reactor power. The PG monochromator is diffracting on the (002) plane that has been positioned at a Bragg angle of 15.5 degrees. The 2-D neutron detection array has been characterized for uniform pixel response and uniform neutron detection efficiency. The 2-D 5x5 array of neutron detectors with a neutron detection efficiency of approximately 0.5 percent has been used as a beam monitor when performing detector testing. The amplifier circuits for the 5x5 array were designed at the KSU Electronics Design Lab (EDL) and were coupled to a LabVIEW field-programmable gate array that is read out by a custom LabVIEW virtual instrument. The virtual instrument has been calibrated to produce a pixel response that varies by less than two percent from pixel to pixel. The array has been used for imaging and active monitoring of the diffracted neutron beam at the detector test facility. The following work is part of on-going research to develop various types of solid state semiconductor neutron detectors.
Author: Romel Siqueira França
Publisher:
ISBN:
Category :
Languages : en
Pages : 137
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Book Description
This research presents the characterization, modeling, and design of the UFTR (University of Florida Training Reactor) radiation beam ports for reactor analysis applications. Extensive validation of beam port is required. Using MCNP5 results were produced for the multigroup neutron flux distributions, neutron spectrum and neutron reaction rates. Due to the strength of the neutron source in the reactor core, the neutron flux distribution and reaction rate can be monitored along the radiation beam port. The goal of the design in this research is to determine the neutron flux distribution, neutron energy flux and neutron reaction rate throughout the beam port. The calculation of the neutron flux distribution, neutron spectrum and neutron reaction rates along the beam port were tallied. To compute the multigroup neutron flux distributions, and neutron energy flux FMESH4 and *F4 tallies were used, respectively. Sets of 47 and 62 energy groups were analyzed for these tallies. To calculate neutron reaction rates, the tally F4 along with the tally multiplier FM4 was used.
Author: Christopher J. Watchman
Publisher:
ISBN:
Category : Boron-neutron capture therapy
Languages : en
Pages : 176
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Author: Tatjana Jevremovic
Publisher: Springer Science & Business Media
ISBN: 0387856080
Category : Technology & Engineering
Languages : en
Pages : 558
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Book Description
Nuclear engineering plays an important role in various industrial, health care, and energy processes. Modern physics has generated its fundamental principles. A growing number of students and practicing engineers need updated material to access the technical language and content of nuclear principles. "Nuclear Principles in Engineering, Second Edition" is written for students, engineers, physicians and scientists who need up-to-date information in basic nuclear concepts and calculation methods using numerous examples and illustrative computer application areas. This new edition features a modern graphical interpretation of the phenomena described in the book fused with the results from research and new applications of nuclear engineering, including but not limited to nuclear engineering, power engineering, homeland security, health physics, radiation treatment and imaging, radiation shielding systems, aerospace and propulsion engineering, and power production propulsion.
Author: Royston H. Filby
Publisher: Springer
ISBN:
Category : Science
Languages : en
Pages : 526
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Book Description
The increased demand on fossil fuels for energy production has resulted in expanded research and development efforts on direct use of fossil fuels and conversion of fossil fuels into synthetic fuels. These efforts have focused on the efficiency of the energy production and/or conversion processes, and of the emission control technology, as well as delineation of the health and environmental impacts of those processes and their by-products. A key ingredient of these studies is the analytical capability necessary to identify and quan tify those chemicals of interest in the process and by-produce streams from coal combustion, oil shale retorting, petroleum refin ing, coal l1quifaction and gasification. These capabilities are needed to analyze a formidable range of materials including liquids, solids, gases and aerosols containing large numbers of criteria and pollutants including potentially hazardous polynuclear aromatic hy drocarbons, organo-sulfur and organo-nitrogen species, trace elements and heavy metals, among others. Taking notice of these developments we sought to provide a forum to discuss the latest information on new and novel applica tions of a subset of those necessary analytical capabilities, namely atomic and nuclear techniques. Consequently, we organized the con ference on Atomic and Nuclear Methods in Fossil Fuel Energy Research, which was held in Mayaguez, Puerto Rico from December 1 to December 4, 1980."
Author: J. M. Davidson
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 40
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Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category : Radiochemistry
Languages : en
Pages : 216
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