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Homogeneous Reactor Project Quarterly Progress Report: February-April 1957 (open access)

Homogeneous Reactor Project Quarterly Progress Report: February-April 1957

Report issued by the Oak Ridge National Laboratory discussing quarterly progress of the Homogeneous Reactor Project. Progress of operations, design, development, and analysis is presented. This report includes tables, illustrations, and photographs.
Date: September 3, 1957
Creator: Briggs, R. B.; Winters, C. E.; Beall, S. E.; Lane, J. A.; Bohlmann, E. G.; Ferguson, D. E. et al.
System: The UNT Digital Library
Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960 (open access)

Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960

Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.
Date: February 3, 1961
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
System: The UNT Digital Library
HRT Reactor Hazards (open access)

HRT Reactor Hazards

Several potential hazards that have been recognized and anticipated in the design and fabrication of the pressure vessel in the Homogeneous Reactor Test are discussed. These hazards results from the high operating pressure and temperature of the reactor, the exposure of the reactor vessel material to potential embrittlement and other affects of fast-neutron irradiation, and the need for containment of corrosive flowing liquids. The steps taken in recognition of these hazards are also discussed. The applicability of present codes to the reactor vessel fabrication is considered. Additional fields are suggested where recommended practices developed by code writing bodies could assist in development-type reactor design and fabrication.
Date: August 3, 1956
Creator: Miller, E. C.
System: The UNT Digital Library
Basic Gamma-Ray Data for ART Heat Deposition Calculations (open access)

Basic Gamma-Ray Data for ART Heat Deposition Calculations

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 heat deposition rates due to gamma rays. Neutron fluxes in the core and reflector regions of the ART are to be obtained from two-dimensional multigroup calculations (performed by the Curtiss-Wright Corporation). These fluxes, in conjunction with the neutron absorption cross sections, determine the neutron capture and inelastic scattering rates in the core and in the reflector. The data in this report permit the calculation of the number of gamma rays originating at various energies at every point in the core and reflector.
Date: October 3, 1956
Creator: Bertini, H. W.; Copenhaver, C. M.; Perry, A. M. & Stevenson, R. B.
System: The UNT Digital Library