Effect of Temperature on Beta-Ray Measurements (open access)

Effect of Temperature on Beta-Ray Measurements

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.
System: The UNT Digital Library
Corrosion of Austenitic Stainless Steel Type 347 in Redox Process Stream : (ORNL #1 Flowsheet) (open access)

Corrosion of Austenitic Stainless Steel Type 347 in Redox Process Stream : (ORNL #1 Flowsheet)

The following report provides the results of laboratory corrosion tests held to investigate the behavior of austenitic stainless steel, Type 347, in selected O.R.N.L. #1 Redox streams.
Date: February 23, 1950
Creator: Koenig, W. W.
System: The UNT Digital Library
P-10 Chemical Equilibria (open access)

P-10 Chemical Equilibria

This report studies tritium oxides and tritium in water vapor, a product of P-10.
Date: March 23, 1950
Creator: Roesch, William C.
System: The UNT Digital Library
Sludge Acidification - Progress Report (open access)

Sludge Acidification - Progress Report

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.
System: The UNT Digital Library
Settling and Dissolution Characteristics and Composition of Hanford Waste Metal Sludge (open access)

Settling and Dissolution Characteristics and Composition of Hanford Waste Metal Sludge

Report reviewing a study regarding the chemical properties, appearance, texture, homogeneity and slurrying ability of waste metal sludge. The settling rates of sludge-supernatant slurries is also discussed.
Date: June 23, 1950
Creator: Brandt, H. L. & Burns, W. A.
System: The UNT Digital Library
1706-KER Coolant Test Facility Operations Manual (open access)

1706-KER Coolant Test Facility Operations Manual

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.
System: The UNT Digital Library
Steady-State Recirculated Reactor Stability and Operational Characteristics - Water and Metal Temperature Coefficients (open access)

Steady-State Recirculated Reactor Stability and Operational Characteristics - Water and Metal Temperature Coefficients

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 stability but also determine many operational characteristics.
Date: December 23, 1959
Creator: Allen, C. W.
System: The UNT Digital Library
Safety Aspects of Purex Plant Concentrator Operation (open access)

Safety Aspects of Purex Plant Concentrator Operation

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.
System: The UNT Digital Library
Corrosion of Stainless Steels in Purex Acid Concentrators (open access)

Corrosion of Stainless Steels in Purex Acid Concentrators

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.
System: The UNT Digital Library
Possible Process Alternatives for Converting Recovered Uranyl Nitrate to Uranium Hexafluoride (open access)

Possible Process Alternatives for Converting Recovered Uranyl Nitrate to Uranium Hexafluoride

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 elemental fluorine.
Date: June 23, 1953
Creator: Clagett, F. & Harmon, M. K.
System: The UNT Digital Library
An Ionization Chamber Method for the Standardization of Tritiated Water Samples (open access)

An Ionization Chamber Method for the Standardization of Tritiated Water Samples

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 source strength and the source strength as computed from pressure, temperature, volume, purity, and dilution data on the original gaseous T2 sample.
Date: July 23, 1953
Creator: Myers, I. T.
System: The UNT Digital Library
Structural Evaluation of Underground Waste Storage Tanks (open access)

Structural Evaluation of Underground Waste Storage Tanks

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.
System: The UNT Digital Library
Shielding of PRTR Gas Loop & Filter (open access)

Shielding of PRTR Gas Loop & Filter

"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.
System: The UNT Digital Library
Polishing and Etching of Uranium Dioxide (open access)

Polishing and Etching of Uranium Dioxide

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 electron microscopy requirements.
Date: March 23, 1959
Creator: Thomas, K. H.
System: The UNT Digital Library
Gamma Photometer Use for Nondestructive Determination of Uranium Content of Enriched "C" Slugs (open access)

Gamma Photometer Use for Nondestructive Determination of Uranium Content of Enriched "C" Slugs

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 complete answer cannot be given at this time. The following is an attempt to state the problem and make recommendations concerning its over-all solution. These recommendations are not assumed to be the totality of those possible; however, they will provide a starting point.
Date: March 23, 1955
Creator: Shortess, Jr., C. J.
System: The UNT Digital Library
Alternate Acid Addition Facility for 100-K (open access)

Alternate Acid Addition Facility for 100-K

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 previously proposed system.
Date: August 23, 1955
Creator: Bainard, W. D.
System: The UNT Digital Library
Plutonium Recovery from Contaminated Materials Project CGC-813-Scope Revision  No. 2 (open access)

Plutonium Recovery from Contaminated Materials Project CGC-813-Scope Revision No. 2

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.
System: The UNT Digital Library
A Brief Course in Radiation Dosimetry and its Application to Personnel Protection (open access)

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

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 processing, etc.
Date: January 23, 1958
Creator: Roesch, Wm. C.
System: The UNT Digital Library
Gamma Heating in PRTR Gas Loop (open access)

Gamma Heating in PRTR Gas Loop

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.
System: The UNT Digital Library
A Mathematical and Statistical Approach to the Design and Analysis of a Reactor Containment Vessel Pressure Test (open access)

A Mathematical and Statistical Approach to the Design and Analysis of a Reactor Containment Vessel Pressure Test

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 precision of the series is given in terms of the individual instrument precisions. The question of accuracy and its relationship to the temperature gradient within the vessel is also considered.
Date: March 23, 1960
Creator: Nicholson, W. L.
System: The UNT Digital Library
Volatilization of Cesium During Calcination and Hydrolysis of Cs2ZnFe(CN)6 Precipitates (open access)

Volatilization of Cesium During Calcination and Hydrolysis of Cs2ZnFe(CN)6 Precipitates

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 hydrolysis of Cs2ZnFe(CN)6 precipitates containing cesium-137. Experimental procedures and results are presented in this report.
Date: March 23, 1960
Creator: Bouse, Donald G. & Schulz, Wallace W.
System: The UNT Digital Library
Shielding Efficiency of Heavy Element Neoprene Gloves at Low X-Ray Energies (open access)

Shielding Efficiency of Heavy Element Neoprene Gloves at Low X-Ray Energies

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 glove and the second, a lead loaded neoprene glove available in two thicknesses. Included in the study was a standard 30 gauge neoprene glove.
Date: November 23, 1959
Creator: Mehas, T. C.
System: The UNT Digital Library