Unit Operations Section Monthly Progress Report May 1959 (open access)

Unit Operations Section Monthly Progress Report May 1959

The measured diffusivity of uranyl nitrate in water at 25ºC was 0.7*10^e cm^2/sec with about 40% average deviation. A program was started to develop nonnuclear uses for depleted uranium. Two continuous DRUHM reaction tuns were terminate due to erratic operation of the sodium metering system. In the second Fluorox run with crude UF, which lasted for 29 hr, a total material balance of 94.8% was obtained and 17.9& of the theoretical amount of UF was collected in cold traps and chemical traps.
Date: August 25, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
System: The UNT Digital Library
A Feasibility Report on a Method of Direct Total Body Measurement of Enriched Uranium in Man (open access)

A Feasibility Report on a Method of Direct Total Body Measurement of Enriched Uranium in Man

In certain phases uranium processing it is poss!ble for operating personnel to acquire internal deposits of uranium. This body burden can be acquired by injection, as in contamination of a wound, by ingestion, of by inhalation. In order to estimate internal exposures, some means of determining the location and extent of these internal deposits is essential.
Date: August 7, 1959
Creator: Sanders, Fred W.
System: The UNT Digital Library
Chemical Development Section C Monthly Progress Report July 1959 (open access)

Chemical Development Section C Monthly Progress Report July 1959

Nitrate contained in raffinates from Canadian Blind River mills interferes seriously with thorium extraction by secondary amines. With primary amines, however, the effect is negligible and these compounds are the preferred process extractants.
Date: August 5, 1959
Creator: Brown, K. B.; Allen, K. A.; Blake, C. A.; Coleman, C. F.; Crouse, D. J.; Ryon, A. D. et al.
System: The UNT Digital Library
Core Levitation in the EOCR in Case of Main Coolant Pipe Failure (open access)

Core Levitation in the EOCR in Case of Main Coolant Pipe Failure

This memorandum summarizes the results of an analysis to determine the extent of displacement of the EOCR core due to blowdown in case of several postulated hot main gas coolant pipe failures. Results show that the core will be damaged for any hot pipe double-ended failure. Excepting the improbable case of no coolant flow existing proper to the break, the core will be damaged for any hot pipe fracture exposing a total flow area to the atmosphere equal to that of one pipe. Smaller breaks will probably be safe in this respect.
Date: August 4, 1959
Creator: Fontana, M. H.
System: The UNT Digital Library
Calculation of Transport Cross Sections (open access)

Calculation of Transport Cross Sections

Many elements exhibit anisotropic scattering at energies of interest in reactor calculations. A method is presented for the calculation of transport cross sections including the observed anisotropy.
Date: August 5, 1959
Creator: Nestor, C. W.
System: The UNT Digital Library
The Use of Boron for Fluoride Complexing in Thorex Dissolver Solutions (open access)

The Use of Boron for Fluoride Complexing in Thorex Dissolver Solutions

Preliminary measurements of the corrosion of titanium were made in 13 M HNO3-0.05 M fluoride using 0.1 M H3BO3 as a liquid and vapor phase complexing agent. Titanium Ax-55 was attacked at average rates of 0.58 and 0.33 mils/month in the liquid and vapor. In dissolver solutions containing 0.5 and 1.0 M titanium, all rates were less than 0.1 mils/month.
Date: August 6, 1959
Creator: Kitts, F. G.
System: The UNT Digital Library
Radiators for Space Power Plants (open access)

Radiators for Space Power Plants

An improved heat sink for space vehicles was proposed in ORNL-CF-59-1-21. Subsequent work on the problem has indicated that there is a substantial probability of a puncture of such a radiator by meteors. To meet this problem a modified geometry has been evolved for which the probability of a meteor puncture should be reduced by a factor of at least 100 relative to the radiator of the original proposal at the expense of an increase in radiator weight of possibly 30%. This memorandum outlines the approach to the problem and a series of similar promising solutions.
Date: August 7, 1959
Creator: Fraas, A. P.
System: The UNT Digital Library
Temperature and Rate of Heat Removal of UO2 Test Elements (open access)

Temperature and Rate of Heat Removal of UO2 Test Elements

The method of calculation of various quantities relating the temperature and the rate of heat removal of UO2 test elements is presented. Graphs of the appropriate quantities as a function of the rate of heat removal are included.
Date: August 5, 1959
Creator: Perry, A. M.
System: The UNT Digital Library
Two-Liquid-Phase Temperature Limits for the Homogeneous Reactor Fuel Solution and its Concentrates; Comments on Solid-Liquid Equilibria. (open access)

Two-Liquid-Phase Temperature Limits for the Homogeneous Reactor Fuel Solution and its Concentrates; Comments on Solid-Liquid Equilibria.

Temperatures are given at which two liquid phases form in a synthetic homogeneous reactor fuel solution and its concentrates. The data show a two-liquid-phase boundary temperature of 332°C for the Particular HRT Fuel composition and a flat minimum temperature of 305°C for the initial solution concentrated between 300 and 329°C are presented to indicate solution stability in this temperature region. Some related comments on current HRT operations are given.
Date: August 11, 1959
Creator: Marshall, W. L.; Gill, J. S. & Moore, R. E.
System: The UNT Digital Library
Study of Dispersant Agents for Thorium Oxide (open access)

Study of Dispersant Agents for Thorium Oxide

A preliminary study of dispersing agents for thorium oxide has been completed and several of the dispersants have possible uses. Also many of the industrial dispersing agents tested are not usable with thorium oxide due to induced behavior causing balling and caking. The effects of nitric acid concentration have been observed to also effect each dispersing agent.
Date: August 7, 1959
Creator: Bate, L. C. & Leddicotte, G. W.
System: The UNT Digital Library
Secondary-Side Water Treatment for Corrosion Control in Aluminum Heat Exchangers: Practices and Results at the Oak Ride Research Reactor (open access)

Secondary-Side Water Treatment for Corrosion Control in Aluminum Heat Exchangers: Practices and Results at the Oak Ride Research Reactor

Standard water treatment practices have proven adequate for scale and corrosion control on the secondary side of the ORR pool-cooling heat exchanger. Corrosion rates measured on specimens exposed to secondary water showed maximum corrosion rates of approximately 1 mpy during the first exposure period and these rates decreased during subsequent exposure.
Date: August 12, 1959
Creator: P. D. Neumann
System: The UNT Digital Library
Instantaneous Velocity Profile Measurement by Photography (open access)

Instantaneous Velocity Profile Measurement by Photography

The following is taken from ORNL-2257, Instantaneous Velocity Profile Measurement by Photography, by R. E. Lynch, L. D. Palmer, and G. M. Winn. This report is in in preparation status; and errors, inconsistances, and omissions in he language, as well as in the technical aspects, may exist. The technique of using phosphorescent particles to enable photographic determination of qualitative and quantitative instantaneous velocity profiles is covered by AEC Patent Application No. SN-710, 371 issued to F. E. Lynch, L. D. Palmer, H. F. Poppendiek, and G. M. Winn and entitled " A Method of and Means for Visualizing Fluid Flow Patterns.
Date: August 17, 1959
Creator: Lynch, F. E.; Palmer, L. D.; Winn, G. M. & Hoffman, H. W.
System: The UNT Digital Library