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Preliminary Design Report - Title 1 on Mobile Gamma Irradiator
Introduction: The Mobile Gamma Irradiator is a semi-production demonstration unit capable of being transported from one area to another for use in irradiating fruit and farm produce, with the capability of furnishing dosages in the pasteurization range.
Date:
October 30, 1964
Creator:
Lowenberg, H. & Allentuck, J.
System:
The UNT Digital Library
Corrosion and Activity Transfer in the SRE Primary Sodium System
Abstract: An evaluation extending over a two-year period was made of primary system sodium and of stainless steel, zirconium, and beryllium specimens exposed in the hot and cold legs of a bypass loop in the primary system of the Sodium Reactor Experiment (SRE).
Date:
October 30, 1961
Creator:
Johnson, H. E.
System:
The UNT Digital Library
Progress Report for the Month of October, 1947 : Contract No. W-38-094-eng-27
This report for October, 1947 describes progress regarding ore dressing and pyrometallurgical studies, chemical work on phosphates, chemical work on shales, and analytical work.
Date:
October 30, 1947
Creator:
Bearse, A. E.; Center, E. J.; Pray, H. A.; Richardson, A. C. & Sullivan, John D.
System:
The UNT Digital Library
Report on Eurida (Toh Atin) District Carrizo uplift area, Arizona
Report and corollary maps on the Eurida (Toh Atin) District, Carrio Uplift, Arizona.
Date:
October 30, 1948
Creator:
Eakland, Edward H.
System:
The UNT Digital Library
Preliminary Report on Recovery of Uranium From High Carbonate Belgian Congo Uranium Ores
Leaching of high carbonite Belgian Congo uranium ores with sulfuric acid and recovery of the uranium from leach solutions by uranous phosphate precipitation are described.
Date:
October 30, 1951
Creator:
George, D. R.; Kennedy, R. H.; Rubino, E. M. & Howland, F. A.
System:
The UNT Digital Library
Loss of Level in D/P Cell Reference Chambers. Section I. First Performance. Core I, Seed 1. Test Results DL-S-279 (RNI-23)
The purpose of the test is to determine the reason for the decreases in the liquid levels of the reference chambers serving the reactor plant remote liquid level indicators. The remote gages and the local liquid level gages agreed closely for the Reactor Plant Component Cooling Water Expansion Tank and the Coolant Discharge and Vent System flash tank and blow-off tank. There appeared to be no loss of water from the D/P cell reference chambers for these two systems over the period of the test. There was no definite indication of leakage from the Valve Operating System reference chamber, however, the differences between remote indicator readings and the sight glass readings are attributed to sticking of the ball check valve on the upper sight glass, inaccuracy of the readings and instrument error. It is recommended that he lower shut-off valve on the upper sight glass be cleaned and reopened prior to reading the sight glass to ensure that the ball check valve is not stuck in the closed position. No lead age was found in any of the level indicating systems.
Date:
October 30, 1959
Creator:
Gentry, George
System:
The UNT Digital Library
Determination of Flux Levels in Neutron Detector Wells. Section II. First Performance. Core I, Seed 1. Test Results DL-S-242, T-641311
The purpose of the test was to determine the neutron flux level in a BF3 counter well during the second performance of DL-S-225. The measured activity of the irradiation brass bolt was due entirely to the radioactive decay of Zn65. The thermal neutron flux in the BF3 counter well during the second 1000 hour run was calculated to be 2.5 x 10(9) neutrons/cm2 sec.
Date:
October 30, 1959
Creator:
George, John R. & Cappola, M., Jr.
System:
The UNT Digital Library