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Natural Circulation Burn Out Heat Flux For The ORR

Description: Natural circulation flow rate is calculated for the ORR core. From this flow rate, the burn out heat flux is found to be between 22,000 and 35,000 Btu/ft2-hr. It is concluded that under present conditions a positive acting after heat removal system is necessary for 30 mw operation.
Date: February 15, 1960
Creator: Wett, J. F.
Partner: UNT Libraries Government Documents Department
open access

Estimate Of Potential Fuel Reprocessing, Revision #30 Part A

Description: The power and estimated reprocessing load are tabulated for existing and proposed for United States and United States-built reactors of 10 Kw or greater thermal power.
Date: March 15, 1960
Creator: Ullmann, J. W.
Partner: UNT Libraries Government Documents Department
open access

High Flux Isotope Reactor - A General Description

Description: This report is issued primarily to make available a general description which reflects the current status of the High Flux Isotope Reactor which is being planned for construction at Oak Ridge National Laboratory.
Date: March 15, 1960
Creator: Cole, T. E.
Partner: UNT Libraries Government Documents Department
open access

Calculated Thermal Ionization And Enthalpy of Hydrogen, Nitrogen, And Argon At One Atmosphere Pressure In The 298-20, 000'K Temperature Range

Description: The degree of dissociation and ionization and the enthalpies of hydrogen and nitrogen, and the degree of ionization and the enthalpy of argon are calculated for one atmosphere pressure and temperatures up to 20,000'K. All three gases are more than 93% ionized at 20,000'K, and have enthalpies ranging from 553 kcals for argon to 1074 and 1225 kcals, respectively, for hydrogen and nitrogen.
Date: September 15, 1960
Creator: Bond, Walter Dayton
Partner: UNT Libraries Government Documents Department
open access

Nuclear Characteristics of BeO-Moderated Cores vs Graphite-Moderated Cores

Description: Multigroup calculations were performed to compare BeO-moderated cores, using various void fractions and core diameters. The core leakages and conversion ratios which were calculated are presented in a series of curves.
Date: January 15, 1960
Creator: Carlsmith, R. S.
Partner: UNT Libraries Government Documents Department
open access

Results of Differential Bed Study of the Kinetics of the Absorption of UF6 on Sodium Fluoride

Description: One step in the Volatility process for power reactor fuel reprocessing involves the absorption and subsequent desorption of UF6 from NaF pellets in fixed beds. In 1958 an experimental study of the kinetics of absorption of HF on NaF beds was made. The purpose of this work was to extend the study to the kinetics of UF6 absorption on NaF. The results should be useful in the design and operation of the Volatility process.
Date: January 15, 1960
Creator: Groves, F. R.
Partner: UNT Libraries Government Documents Department
open access

Momentum and Heat Transfer to a Fluid Flowing Turbulently in a Pipe

Description: A mathematical model is presented for the prediction of heat transfer coefficients for fully developed turbulent flow of fluids in circular pipes by analogy to the transfer of momentum. There is also presented an empirical velocity distribution equation derived from existing experimental data for use in the analogy model. Heat transfer coefficients for fluids with Prandtl numbers ranging from 0.01 to 100 and Reynolds numbers ranging from 5x10^3 to 10^7 are presented in tabular and graphical for… more
Date: September 15, 1960
Creator: Hefner, R. J.
Partner: UNT Libraries Government Documents Department
open access

High Flux Isotope Reactor: a General Description

Description: Current status of the High Flux Isotope Reactor which is being planned for construction at Oak Ridge.
Date: March 15, 1960
Creator: Cole, T. E.
Partner: UNT Libraries Government Documents Department
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