Technical Report Archive & Image Library (TRAIL) - 17 Matching Results

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A Brief Course in Radiation Dosimetry and its Application to Personnel Protection

Description: By radiation dosimetry, we will mean the determination of the energy deposited per unit mass of irradiated material by ionizing radiation. Usually the material of interest in tissue and the results are to be applied to a radiobiological experiment, a radiotherapy treatment, or the protection of personnel from radiation hazards. The same methods, however, are applied to such engineering problems as the production of heat by reactor radiations, the use of radiation in chemical reactions or food p… more
Date: January 23, 1958
Creator: Roesch, Wm. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion of Stainless Steels in Purex Acid Concentrators

Description: The corrosion resistance of four types of austenitic stainless steels to Purex process first and second acid concentrator bottoms was determined. Although the compositions of the two solutions were very similar, tests in simulated solutions of both compositions were conducted to strengthen the basis for the conclusions which were to be made.
Date: April 23, 1953
Creator: Sanborn, Kenneth L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of Temperature on Beta-Ray Measurements

Description: Summary: "This report investigates photographic methods of measuring beta radiation and includes a study of temperature effects on these measurements. Experimental data are submitted to show that an increase in film temperature before and during beta irradiation causes a definite increase in density for the same dosage. Recommendations drawn from experience gained in the experimental works are offered."
Date: November 23, 1949
Creator: Stevens, A. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gamma Heating in PRTR Gas Loop

Description: It is being considered that the in-reactor portion of the test section of the PRTR Gas-Cooled Loop Facility consist, in part, of two concentric Inconel-X tubes. The outer tube is the main stress member, with 3.5 O.D. and a wall thickness of 0.065. The inner tube is 3.0 O.D. and has a wall thickness of 0.030. The inner tube provides an annular gas space to serve as thermal insulation.
Date: June 23, 1959
Creator: Reginbel, J.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Ionization Chamber Method for the Standardization of Tritiated Water Samples

Description: Ionization measurements of water vapor in vapor-liquid equilibrium were made with a series of chambers on a tritiated water sample which was prepared by burning T2 to T2O and diluting it with H2O. A correction was made for the difference of vapor pressures of HTO and H2O. The effect of HTO adsorbed on chamber walls and electrodes was eliminated from the final result. Using Gerbes data on the number of electron volts to produce an ion pair in air, agreement obtained between the measured sourc… more
Date: July 23, 1953
Creator: Myers, I. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Mathematical and Statistical Approach to the Design and Analysis of a Reactor Containment Vessel Pressure Test

Description: This report discusses the mathematical and statistical questions concerned with the estimation of a leak rate from data collected during a reactor containment vessel pressure test such as that performed on the PRTR vessel in May, 1959. A mathematical method is suggested in Section 3 for the construction of a total number of gas molecules in the containment vessel time series using vessel absolute pressure and temperature readings at several positions within the vessel. A formula for the precisi… more
Date: March 23, 1960
Creator: Nicholson, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plutonium Recovery from Contaminated Materials Project CGC-813-Scope Revision No. 2

Description: An inventory of the contaminated materials accumulated since the initiation of this project in June 1958, revealed a larger variety and quantity of materials that could be burned, than was specified for the initial scope. Therefore, it is desirable to revise the scope to permit handling the majority of these materials with the initially installed equipment.
Date: January 23, 1959
Creator: Doud, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Polishing and Etching of Uranium Dioxide

Description: Various methods and procedures for preparing uranium dioxide bodies for metallographic examination and study have been utilized by various investigators. Unfortunately, these methods are not in general satisfactory for use on irradiated uranium dioxide. Since radiation damage studies on irradiated uranium dioxide require use of electron microscopy, and reveal structure by virtue of surface relief. This report covers an investigation of etching methods compatible with radiometallurgy and electro… more
Date: March 23, 1959
Creator: Thomas, K. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Possible Process Alternatives for Converting Recovered Uranyl Nitrate to Uranium Hexafluoride

Description: The uranium recovery processes which are in operation or under construction at the present time--TBP, Redox and Purex--yield an aqueous uranyl nitrate solution as the recovered uranium product. For conversion of this recovered uranium to UF6 for feed to the gaseous diffusion plants, the uranyl nitrate in the solution is concentrated with or without prior organic stripping, calcined to UC3, reduced to UO2 with hydrogen, hydro-fluorinated to UF4 with RF, and finally fluorinated to UF6 with eleme… more
Date: June 23, 1953
Creator: Clagett, F. & Harmon, M. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Shielding Efficiency of Heavy Element Neoprene Gloves at Low X-Ray Energies

Description: The utilization of gloves wherein heavy element additives have been included is a significant means of reducing exposure to hands and, consequently, increasing allowable working time in operations which require direct contact with low energy isotopes - such as plutonium. The number of such gloves available has been limited considerably by the feasibility of fabrication and the practicality of application. The following study was made on two basic gloves - the first, a heavy zinc-neoprene coated… more
Date: November 23, 1959
Creator: Mehas, T. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Shielding of PRTR Gas Loop & Filter

Description: "The PRTR Pressured Gas-Cooled Loop Facility, or Gas Loop, is an experimental facility to be installed in the Plutonium Recycle Test Reactor for use in studies contributing to advancement of the technology of gas-cooled reactors. The facility will provide an in-reactor loop for studying phenomena occurring under conditions likely to exist in gas-cooled reactors.
Date: April 23, 1959
Creator: Reginmbal, J.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Steady-State Recirculated Reactor Stability and Operational Characteristics - Water and Metal Temperature Coefficients

Description: It is desirable that a reactor exhibit a self-regulating effect. If this were not true any disturbance to the reactor would result in a continual increase in the magnitude of the disturbance and the reactor would be unstable. In this investigation the reactor is considered to have two reactivity feed-backs: metal temperature and water temperature reactivity effects. These two variables through a metal temperature coefficient and water temperature coefficient determine not only the reactor stabi… more
Date: December 23, 1959
Creator: Allen, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Structural Evaluation of Underground Waste Storage Tanks

Description: To set forth limiting values of internal vapor pressure and effective liquid specific gravity which will permit the maximum utilization of the existing underground waste storage capacity. It is also intended to describe briefly the elements which could contribute to ultimate failure.
Date: June 23, 1955
Creator: Smith, Edgar F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Volatilization of Cesium During Calcination and Hydrolysis of Cs2ZnFe(CN)6 Precipitates

Description: The feasibility of removing and recovering cesium-137 from various HAPO process solutions by precipitation of Cs2ZnFe(CN)6 has been demonstrated previously. Pilot plant studies of calcination and steam hydrolysis of non-radioactive Cs2ZnFe(CN)6 precipitates by members of the Process Equipment Development Operation are currently in progress. In support of these pilot plant studies, experiments were performed to determine the extent, if any, to which cesium volatilizes during calcination and hydr… more
Date: March 23, 1960
Creator: Bouse, Donald G. & Schulz, Wallace W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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