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BASIC INELASTIC NEUTRON DATA FOR AGE CALCULATIONS FOR VARIOUS FUEL AND MODERATOR COMPOSITIONS

Description: BS>Graphs were prepared as basic inelastic neutron data requested for neutron age calculations to be made using the compositions NaF-ZrF/sub 4/, BeF/ sub 2/, LiF-BeF/sub 2/, and ZrH. Nuclear temperature as a function of incident neutron energy was obtained for F, Be, and Zr. (W.D.M.)
Date: June 1, 1956
Creator: Copenhaver, C.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Anisotropic Elastic Scattering of Neutrons

Description: In an elastic collision the neutron loses part of its kinetic energy to the nucleus with both the kinetic and momentum of the system being conserved. However, for many elements the scattering is not isotropic in the center-of-mass system at the higher neutron energies. Many of the present reactor multigroup codes include anisotropic scattering at the high neutron energies, while many others assume isotropic scattering at all energies. In order to consider some of the effects of including anisot… more
Date: March 21, 1957
Creator: Copenhaver, C. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Basic Gamma-Ray Data for ART Heat Deposition Calculations

Description: In order that fairly accurate thermal stress calculations can be made on the ART, it is necessary to have a reasonable picture of the temperature distribution in the reactor. To get the temperature distributions, and to determine cooling requirements in various parts of the reactor, one must know the heat deposition rates due to alpha particles, beta rays, gamma rays, and neutrons in all parts of the reactor. The present report contains only the basic physical data necessary to determine the he… more
Date: October 3, 1956
Creator: Bertini, H. W.; Copenhaver, C. M.; Perry, A. M. & Stevenson, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THE HGCR-1, A DESIGN STUDY OF A NUCLEAR POWER STATION EMPLOYING A HIGH- TEMPERATURE GAS-COOLED REACTOR WITH GRAPHITE-UO$sub 2$ FUEL ELEMENTS

Description: The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO/sub 2/ fuel appear to be less than 0.2% of thos… more
Date: July 28, 1959
Creator: Cottrell, W. B.; Copenhaver, C. M.; Culver, H. N.; Fontana, M. H.; Kelleghan, V. J. & Samuels, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UO₂ Fuel Elements

Description: "The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO₂ fuel appear to be less than 0.2% of those pro… more
Date: 1959
Creator: Cottrell, William B.; Copenhaver, C. M.; Culver, H. N.; Fontana, M. H.; Kelleghan, V. J. & Samuels, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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