Serial/Series Title

Language

Thermal Decomposition of Plutonium (IV) Oxalate and Hydrofluorination of Plutonium (IV) Oxalate and Oxide (open access)

Thermal Decomposition of Plutonium (IV) Oxalate and Hydrofluorination of Plutonium (IV) Oxalate and Oxide

The work described in this report was done to determine the path of decomposition of plutonium (IV) oxalate and to determine the factors affecting the reactivity of the oxide with the hydrogen fluoride.
Date: August 1, 1956
Creator: Myers, M. N.
System: The UNT Digital Library
Irradiation of U-Mg Matrix Fuel Materials to High Exposures (open access)

Irradiation of U-Mg Matrix Fuel Materials to High Exposures

An experiment designed to evaluate the in-pile performance of the U-Mg fuel material when irradiated to high burnups has been completed. Twelve specimens of the fuel material which contained uranium particles that packed 50 volume per cent, (91.5 weight per cent), uranium in a magnesium matrix were canned in Zircaloy cans and irradiated in the Materials Testing Reactor to 0.1 (1000 MWD/T), 0.3 (5000 MWD/T), 1.0 (10000 MWD/T) and 2.0 20000 MWD/T) per cent burnup of the total uranium atoms; more exactly, 1 MWD/T = 1.16 x 10⁻⁴ per cent burnup of the total uranium atoms. Irradiation of the twelve capsules began on August 1, 1954. The burnup figures used in this report are calculated values assuming a conversion ratio for the capsules of 1.0. Because of the lack of confirmed experimental burnup data for exposures of this magnitude, there is a possible error in the calculated values of about 20 per cent at 2.0 per cent burnup. However, recent results based on chemical analysis for cesium indicate that the calculated values of burnup agree quite closely for the higher exposures. Burnup estimates based on the results of the chemical analysis will be published when they become available. Six of …
Date: August 1, 1956
Creator: Freshley, M. D. & Last, G. A.
System: The UNT Digital Library
The Use and Calibration of Scintillation Counter--Model Y (open access)

The Use and Calibration of Scintillation Counter--Model Y

Several improvements have been made in the gamma scintillation counter (GSC). The Model V gamma scintillation counter uses a canned thallium activated sodium iodide crystal as a detector. Although the electronic components remain unchanged, a modification of the sample support has been made to improve reproducibility of geometry. To assure comparable results between various counters, they must be operated at the same energy threshold and counting yield. Methods have been developed to assure operation at a preferred energy threshold of 0.1 Mev and an arbitrarily fixed counting yield of 3.36% for Cs-Ba-137. Partial pulse height discrimination against U 237 is also accomplished.
Date: August 1, 1953
Creator: Brauer, F. P. & Leboeuf, M. B.
System: The UNT Digital Library
A Large Area Alpha Scintillation Probe (open access)

A Large Area Alpha Scintillation Probe

An Alpha Scintillation Probe for use with the HAPO Cart Poppies has been designed to replace the air proportional probes presently used. The new probe has an average geometry of about 15 or 16 percent over an effective probe area of 23.4 in². Stability of operation under normal conditions of vibrations, humidity and temperature are inherent qualities and the average background count is stable at about two counts per minute. The high voltage used is in the order of 1,200 to 1,250 volts with a current requirement of 100 microamperes.
Date: August 1, 1955
Creator: Spear, W. G.
System: The UNT Digital Library
Surface Structure of Pile Irradiated 2S Aluminum (open access)

Surface Structure of Pile Irradiated 2S Aluminum

The surfaces of cold rolled, half hard, nitric acid treated, autoclave etched, 2S aluminum coupons were studied by optical and electronoscopic methods, before and after exposure to hot water alone and hot water and neutron bombardment. The non-exposed aluminum surfaces have a characteristic pattern which is absent in the exposed coupons. All of the exposed coupons were corroded. In general the coupons exposed to the higher flux intensities of irradiation were more severely corroded than those exposed to the lower flux intensities of irradiation or to the hot water alone. Representative photo-and electron micrographs illustrate the various types of surface structure observed on the control and experimental coupons.
Date: August 1, 1955
Creator: Borasky, R. & Mastel, B.
System: The UNT Digital Library