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Sludge Acidification - Progress Report

Description: Report discussing the progress made on research concerning sluge-supernate acidification. This report focuses mainly on "'reverse strike' acidification and the observations of the physical characteristics of the test material," which was a synthetic incubated metal waste.
Date: June 23, 1950
Creator: Harmon, M. K.
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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.
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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.
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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.
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Gamma Photometer Use for Nondestructive Determination of Uranium Content of Enriched "C" Slugs

Description: it is desired to know the accuracy and precision of uranium content determination with the γ-photometer. Several possible sources of error (involving both bias and variability) arise when the problem is fully considered. As analysis of data collected for the evaluation of this technique has progressed, there has been a continued discovery of new sources of error and bias further complicating this evaluation. These possible sources have not yet all been systematically examined and thus a complet… more
Date: March 23, 1955
Creator: Shortess, Jr., C. J.
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Alternate Acid Addition Facility for 100-K

Description: Document HW-33176, "A Proposed Scope of the 100-K Sulfuric Acid Addition Facilities", presented the justification and bases for a sulfuric acid addition facility at the 183-K headhouses and included a system for adding the acid to the raw water. Since the issue of this document several factors to consider in such a system have been brought to light by experience gained both at K and at other areas. The alternate system presented here eliminates several of the troublesome points in the previousl… more
Date: August 23, 1955
Creator: Bainard, W. D.
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Safety Aspects of Purex Plant Concentrator Operation

Description: A study was made to evaluate the possibility of an explosive reaction occurring in the Hanford Purex Plant concentrators as presently instrumented. Results revealed that the occurrence of an explosive reaction in the Purex Plant concentrators with present instrumentation is very unlikely.
Date: December 23, 1955
Creator: Shefcik, J. J.
open access

1706-KER Coolant Test Facility Operations Manual

Description: This procedure is intended to be used as: 1. An instruction and guide for operation of the KER loops. 2. To aid in familiarization and understanding of the general operation of the loops. 3. To prevent lost time due to errors in loop operation. The procedure is not meant to be completely comprehensive in all details of loop operation.
Date: January 23, 1958
Creator: Dulin, R. V.
open access

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.
open access

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.
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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.
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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.
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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.
open access

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.
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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.
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