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Book Neutron Flux Enhancement in the NRAD Reactor

Download or read book Neutron Flux Enhancement in the NRAD Reactor written by and published by . This book was released on 1988 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In 1987 a series of experiments were conducted at the NRAD reactor facility at Argonne National Laboratory - West (ANL-W) to investigate the possibility of increasing the thermal neutron content at the end of the reactor's east beam tube through the use of hydrogenous flux traps. It was desired to increase the thermal flux for a series of experiments to be performed in the east radiography cell, in which the enhanced flux was required in a relatively small volume. Hence, it was feasible to attempt to focus the cross section of the beam to a smaller area. Two flux traps were constructed from unborated polypropylene and tested to determine their effectiveness. Both traps were open to the entire cross-sectional area of the neutron beam (as it emerges from the wall and enters the beam room). The sides then converged such that at the end of the trap the beam would be 'focused' to a greater intensity. The differences in the two flux traps were primarily in length, and hence angle to the beam as the inlet and outlet cross-sectional areas were held constant. It should be noted that merely placing a slab of polypropylene in the beam will not yield significant multiplication as neutrons are primarily scattered away.

Book An Easier Way to a Harder Spectrum

Download or read book An Easier Way to a Harder Spectrum written by Michael T. Pierce (Jr.) and published by . This book was released on 2019 with total page 998 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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

Book Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 1212 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975-11 with total page 960 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book A Study of Thermal and Resonance Neutron Flux Detectors

Download or read book A Study of Thermal and Resonance Neutron Flux Detectors written by George M. Jacks and published by . This book was released on 1961 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Calculation of Thermal Neutron Fluxes in Primary Shields

Download or read book Calculation of Thermal Neutron Fluxes in Primary Shields written by D. C. Anderson and published by . This book was released on 1959 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Determination of the Thermal Neutron Flux in a Research Reactor

Download or read book The Determination of the Thermal Neutron Flux in a Research Reactor written by Alan Jay Blotcky and published by . This book was released on 1971 with total page 152 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Dosimetry Issues for an Ultra High Flux Beam and Multipurpose Research Reactor Design

Download or read book Dosimetry Issues for an Ultra High Flux Beam and Multipurpose Research Reactor Design written by CD. West and published by . This book was released on 1994 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Neutron Source is a new user facility for all fields of neutron research, including neutron beam experiments, materials analysis, materials testing, and isotope production. The complement and layout of the experimental facilities have been determined sufficiently, at a conceptual design level, to make reliable cost and schedule estimates. The source of neutrons will be a heavy water reactor, constructed largely of aluminum, with an available thermal neutron flux 5-10 times higher than existing research reactors.

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1988 with total page 972 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Experimental Investigation of Thermal Neutron Flux Distributions and Disadvantage Factors in Simulated Reactor Slab Lattices

Download or read book Experimental Investigation of Thermal Neutron Flux Distributions and Disadvantage Factors in Simulated Reactor Slab Lattices written by Donald John Bennet and published by . This book was released on 1963 with total page 134 pages. Available in PDF, EPUB and Kindle. Book excerpt: