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Author: A. Edward Profio Publisher: ISBN: Category : Fast neutrons Languages : en Pages : 120
Book Description
The angular flux spectrum was measured in a 43 cm sphere filled with the mixture ZrH1.9O0.3Fe0.1A10.05B0.01' representing the approximate homogenized TRIGA reactor core composition (without uranium, and with boron added for thermal neutron absorption). The sphere was reflected with 5.08 cm of water. A 7.6 cm diameter depleted uranium target embedded at the center, excited by a 20 nsec pulsed electron beam for a Linac, was the neutron source for the time-of-flight experiment (50 meter flight distance). Detectors were a 5 by 5 cm liquid scintillator for spectra from 0.4-14 MeV, and a boron capture gamma ray detector for 0.1-0.5 MeV. Measurements were made at 7.6 cm penetration (0 and 51 degrees to the radius vector), at the core-reflector interface, and at the surface of the reflector (0 and 46 degrees). Calculations of the spectrum in the experimental assembly were made with the GAPLSN S sub n code in S8, with 20-group P3 cross sections from the GAM-II code. Comparisons between calculations and experiment were made to decide on the angular mesh, order of anisotropic scattering approximation, energy grouping, and cross sections for a similar calculation of the critical TRIGA reactor spectrum. Results of the calculated cylindrical geometry, P3, S8 angular flux spectrum and total leakage spectrum at the surface of the reflector are tabulated. (Author).
Author: A. Edward Profio Publisher: ISBN: Category : Fast neutrons Languages : en Pages : 120
Book Description
The angular flux spectrum was measured in a 43 cm sphere filled with the mixture ZrH1.9O0.3Fe0.1A10.05B0.01' representing the approximate homogenized TRIGA reactor core composition (without uranium, and with boron added for thermal neutron absorption). The sphere was reflected with 5.08 cm of water. A 7.6 cm diameter depleted uranium target embedded at the center, excited by a 20 nsec pulsed electron beam for a Linac, was the neutron source for the time-of-flight experiment (50 meter flight distance). Detectors were a 5 by 5 cm liquid scintillator for spectra from 0.4-14 MeV, and a boron capture gamma ray detector for 0.1-0.5 MeV. Measurements were made at 7.6 cm penetration (0 and 51 degrees to the radius vector), at the core-reflector interface, and at the surface of the reflector (0 and 46 degrees). Calculations of the spectrum in the experimental assembly were made with the GAPLSN S sub n code in S8, with 20-group P3 cross sections from the GAM-II code. Comparisons between calculations and experiment were made to decide on the angular mesh, order of anisotropic scattering approximation, energy grouping, and cross sections for a similar calculation of the critical TRIGA reactor spectrum. Results of the calculated cylindrical geometry, P3, S8 angular flux spectrum and total leakage spectrum at the surface of the reflector are tabulated. (Author).
Author: Michael T. Pierce (Jr.) Publisher: ISBN: Category : Languages : en Pages : 998
Book Description
The TRIGA Mark II research reactor has a flux spectrum with a predominance of thermal neutrons. While most research can be conducted using this thermal neutron flux, an exclusively fast neutron flux is preferred for some experiments, such as radiation damage studies. Although fast neutron flux spectrums are available using fast reactors or neutron generators, only a few fast reactors are currently in operation and neutron generators tend to have low fluxes. As a result, this report evaluated the possibility of generating a fast neutron flux spectrum in a thermal reactor through the use of an irradiator consisting of layers of uranium, boron, and cadmium. Simulations using Monte Carlo N-Particle Code (MCNP) determined that thin layers of these materials in an irradiator inserted into the 3-Element Facility of the UT-Austin TRIGA reactor will generate a fast neutron flux spectrum with negligible thermal flux and where over 91% of the total flux consists of neutrons with energy greater than 10 keV. Further research is recommended to calculate heat dissipation and to determine the reactivity worth of the irradiator
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The fast neutron spectrum of the Coupled Fast Reactivity Measurements Facility (CFRMF) at the Idaho National Engineering Laboratory (INEL) is being used to study and standardize fast reactor neutron dosimetry materials and methods. The CFRMF has been designated a ''benchmark experiment'' to test the cross section data of dosimetry materials as well as other materials used and produced in fast reactors. Information about the neutron energy spectrum of the CFRMF is presented. (auth).
Author: Kenneth Dwight Dobbin Publisher: ISBN: Category : Neutron sources Languages : en Pages : 228
Book Description
A standard fast reactor spectrum can be created by the partial moderation of the U-235 fission spectrum in an air cavity. Spherical natural uranium shells are driven by thermal neutrons from a thermal column. The uranium is placed at the center of a spherical graphite hohlraum to reduce the anisotropic effect of a planar source of thermal neutrons. The Oregon State University (OSU) fast neutron spectrum facility design employs this method which is being used by Albert Fabry in Mol, Belgium and the NISUS assembly in London, United Kingdom, to create a fast neutron spectrum. The OSU facility uses the ther malizing column of a TRIGA Mark II reactor for a thermal neutron source. The mechanical design is presented showing the location of the facility, the aluminum container and internals, and the transport assembly. Two computer codes are introduced in the nuclear design. SLAB is a first approximation diffusion theory code which justifies the use of one foot of graphite backed with water in place of "infinite graphite." FASTSPEC is a diffusion theory approximation code in spherical geometry which shows that the design will produce a spectrum characteristic of a fast reactor. Phase I operation is a mechanical test, health physics evaluation, and a thermal neutron calibration of the facility with a thermal neutron absorber in place of the uranium. The data for phase I is included. Phase II operation will be the insertion of an uranium driver shell and the calibration of the fast spectrum. Only phase I is complete at this time.
Author: A. P. Veselkin Publisher: ISBN: Category : Languages : en Pages : 145
Book Description
The report discusses the following: Measurement conditions and methods; The formation of fast-neutron spectra in various media; and Attenuation of fast-neutron fluxes.
Author: A. Edward Profio
Author: A. Edward Profio
Author: Michael T. Pierce (Jr.)
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Author: C. Z. Serpan
Author: Kenneth Dwight Dobbin
Author: A. P. Veselkin
Author: P. B. Hemmig
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