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- 3 Plant Radiation Study Interim Report #5- Part II Data on Gamma Shielding of Special Plutonium Samples
- The calculation of shielding the thickness for plutonium is complicated by the many different energies represented in the gamma radiation emitted during decay of the plutonium isotopes. Dose rate predictions are also frequently confused by gamma from varying content of fission product impurities in the plutonium, as well as other gamma radiation induced through alpha and neutron particle absorption within the source material or its environment. After assumptions are made for these many factors the radiation data for shielding determination is still frequently inadequate because of wide variations in dose rates resulting from self-absorption. The degree if self-shielding is in turn dependent on nature of the plutonium compound, degree of compactness, weight, and over-all geometrical distribution of the source material. By preparing a variety of plutonium samples representing combinations of these varying factors, actual dose rates and gamma spectra, as obtained from them, can then be extrapolated for application to specific situations.
- "25" Critically Consultation with J. W. Morfitt : April 3, 1950
- Summary: "Criticality was considered impossible in any contingency encountered in practice under either of the following conditions which include no safety factor: (a) In any isolated cylinder not more than 5 in. in disruptor, if the total amount of U235 present does not exceed 7.5 Eg. (b) In an isolated vessel of any shape and size, if the total amount of U235 present does not exceed 880 g. An "isolated" vessel is one which does not "see" more than 0.1 [...] other vessels containing fissionable material."
- 100-N Decontamination Facility Design Guide.
- Space has been reserved near the southeast corner of the 100-N Area for the 122-N Decontamination Facility. Previous correspondence between Burns and Roe, Inc and General Electric bae discussed various facilities which might be needed in the building. The concepts of the decontamination processes are under active development by research groups at Hanford. At present, there are several workable processes known; each one has one or more fairly serious drawbacks.
- 327 Basin Aluminum Corrosion Test
- An investigation of corrosion in the 327 Building's water storage basin was made to determine whether the static storage of aluminum jacketed fuel elements could cause corrosion effects that would interfere with studies of in-pile corrosion.
- 709 Program for Reduction of Exponential Pile Data
- A multi-purpose program for processing exponential data has been prepared for the 709 computer. The main purposes of the program is to compute the material buckling from raw data (given counts, time, and counter information) or from previously calculated Athermal's. It is also possible to compute only CeCh (end and harmonic corrections) for a given B11 or series if B11's no counting data being entered. In every case, pile measurements must be submitted as input for corrections.
- 1706 KE Water Treatment for Out-of-Reactor Test Facilities.
- Water treatment systems for preparing and maintaining high purity water in out-of-reactor or in-reactor test oops are becoming increasingly important. In out0of-reactor experiments the presence of ionic impurities in the water has a marked influence on film formation and corrosion rates. It is therefore , imperative that these impurities be maintained at the lower practical concentration.
- 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.
- An Abrasive Cutoff Machine for Metallurgical Research on Radioactive Materials
- An abrasive cutoff machine design, based upon a previous model, (1) was undertaken to provide for the sampling of radioactive material. the design objective was; first, to provide samples for metallographic examination, second, to provide samples for physical and mechanical property testing, and, third, to meet the following design requirements: 1. Remote operation. 2. Airborne contamination control. 3. Radioactive waste collection. 4. Remote maintenance.
- Abrasive Cutting of Irradiated Uranium
- The preparation of radioactive metallurgical specimens for microscopic examination is one of the responsibilities of the Radiometallurgy Sub-Unit. An abrasive cut-off machine development program, based upon a previous experimental model, was undertaken to provide a method for sectioning of irradiated materials without undue personnel exposure or spread of contamination and finally to provide data for the design of an abrasive cutting unit for use in the work cells in the Radiometallurgy Building. A horizontal-feed type set-off machine, powered by a 7 1/2 hp motor with V-belt drive, has been developed for the submerged sectioning of irradiated uranium and is currently being used successfully to obtain samples for metallurgical, chemical and physical investigations without excessive personnel exposure or spread of radioactive contaminates.
- The Absorption and Translocation of Several Fission Elements by Russian Thistle
- Abstract: An investigation was conducted to determine the absorption and translocation of fission products by Russian thistle from a localized spot of contaminated soil. The amount and identity of the radioactive elements absorbed and translocated by the Russian thistle is given along with the location of these elements in the plants. Beta radioactivity to the amounts of 10 microcuries per gram caused no visible effects on the growth habits of sectioned material are included.
- Absorption by Soil of Strontium From 216-S Crib Waste
- A preliminary soil column experiment with a waste sample from the 207-S-11 well, which monitors the 216-S cribs, indicated that cesium was absorbed almost completely by the soil but that strontium breakthrough to ground water in the near future seemed likely. Accordingly, it was suggested that the 216-S wastes be discharged to a new disposal site, and that samples of the wastes which are currently being discharged to the 216-S cribs be obtained for soil absorption tests. The primary purpose of these tests was to obtain data which could be used to suggest ways and means of improving the absorption of strontium by soil from the process condensate stream (D-2_ and the cell drainage stream (D-1), both of which have been discharged to the 216-S cribs for the past several months.
- Absorption Characteristics of Long Soil Columns
- The purpose of this report is to present the information obtained relative to the characteristic adsorption of radioisotopes in a long (forty feet) laboratory soil column treated with a high salt, process waste of high activity density. The movement of adsorbed cations in a soil column subjected to prolonged leeching by water also was determined.
- The Abundance of the Principle Crustacea of the Columbia River and the Radioactivity They Contain
- The following document describes data collected from a 14-month period of analyzing crustaceans containing radioactivity. Provided is information based on the change of radioactivity through seasonal changes.
- The Accumulation of Radioactivity as Shown by a Limnological Study of the Columbia River in the Vicinity of Hanford Works : Preliminary Report
- The following report provides data collected during an investigation in the Columbia River. The purpose of this investigation was to research the radioactivity present in the bottom-living organisms of the river.
- Accumulation of Radioactivity in Columbia River Fish in the Vicinity of the Hanford Works
- Abstract: The data obtained from the radioassay of fish collected in vicinity of the Hanford Works between April, 1948 and June, 1950 are presented. Most of the radioactivity in the fish resulted from the concentration of p32 in the scales, bone, and certain visceral organs. The level of activity density in the fish was influenced by size, feeding habits and metabolic rate in addition to the activity density of the water. Changes in operation of nuclear reactors have resulted in progressive increases in activity densities of fish from one year to the next. The levels of radioactivity are not sufficiently high to be hazardous to either the fish or persons eating them.
- Accuracy of Volume Measurements in a Large Process Vessel
- The Non-Production Fuel Reprocessing Program involves the chemical processing of valuable reactor fuels received from privately owned power reactors. It is necessary therefore, to accurately measure the fuel material received in order to insure proper payment to reactor operator and to provide the Atomic Energy Commission with appropriate accountability data. The volume measurement study described herein was conducted in order to determine the limits of accuracy that could be obtained in measuring relatively large volumes of solution under plant processing conditions.
- Action Taken on the Spot Contamination in the Separations Plant Areas
- The following document analyzes radioactive spot contamination in and around the T and B Plant Areas.
- An Addendum to a Parametric Study of the Gas-Cooled Reactor Concept
- From introduction: "This report provides background information regarding the study results presented in the first volume of this report and provides information resulting from the studies made on the gas cooled reactor concept."
- Addendum to Report HW-30390: Estimated Power Generation in MTR Slug Test Facility
- An addendum to report HW-30390 a additional power generation calculation for P, the rate of energy release, in kilowatts, was derived.
- The Aeolotropic Elastic Relations for Uranium Crystals
- Handwritten report. This theoretical introduction to the anisotropic elastic properties of the orthorombic [sic] uranium crystal presents certain basic ideas which are useful in the study of experimental methods for determining preferred orientations in polycrystalline bodies. The method of analysis used to determine the elastic constants suggests explanations and correlations for the observations of sonic wave experiments on bars having preferred orientations and also serves as an introduction into the type of mathematical relations used in the study of anisotropic crystals.
- Air Leakage Through Labyrinth Seals
- This report contains the results of tests which demonstrated the feasibility of using graphite labyrinth type seals, i.e., a bushing machined with alternate grooves and lands on the inside diameter to create a sufficient pressure drop to provide a satisfactory seal.
- Air Sample Activity vs Flow Rate
- A bibliography on the subject of air sample activity vs flow rate has been prepared. The findings in two documents reviewed have been applied directly to this problem. It is concluded that air sample activity is not dependent on flow rate when sampling particles whose average diameter in 0.06 micron or greater.
- All In-Well Permeability Testing Packer
- Disposal of liquid radioactive wastes to ground requires knowledge of the area ground-water hydrology. Information is desired on direction and velocity of ground-water flow. Direction of flow can be determined from maps showing contours on the water table surface, such contours being derived from well water elevations. Ground-water velocity is more difficult to ascertain.
- An Alpha, Beta, Gamma Hand and Shoe Counter - Model 2
- Experimental combination hand and shoe counter redesign as a compact, simplified, register readout instrument no larger than the present Five-Fold called Model 2.
- An Alpha, Beta, Gamma Transistorized Survey Meter
- A portable, light weight transistorized alpha, beta, and gamma survey meter was designed and fabricated.
- An Alpha Energy Analyzer
- This report provides an overview of a gridded ionization chamber, instructions on how to operate the instrument, and then discusses the performance of the instrument so far.
- The Alpha Half-Life of the Isotope Pu-241
- A plutonium solution of known Pu-241 content was purified by solvent extraction techniques to remove uranium and americium impurities. Portions of this purified solution were then analyzed for U-237 as a function of time. Since the growth of U-237 occurs directly by the alpha decay of Pu-241, these measurements provided sufficient data for calculation of the Pu-241 alpha half-life, which was found to be 2.91 ± 0.50 x 10⁵ years.
- 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.
- Alternating Current and Square-Wave Polarography
- A exploratory study was made of a polarographic technique in which an alternating sine or square-wave potential is superimposed upon the applied d.c. potential of the polarographic scan. Recording of the a.c. component of the polarographic current results in derivative-type waves. It was shown that the technique yields greater sensitivity and greater selectivity than normal polarographic technique.
- Aluminum Alloy Work at Hanford
- Investigation of aqueous and steam corrosion at elevated temperature has been carried on at Hanford for several tears. A number of reports have been published on various phases of the corrosion program but, except for monthly reports, little has been written on the progress of the Corrosion and Coatings Operation alloy development program. This interim report will outline the more important current phases of the aluminum alloy program.
- Analysis of a Nuclear Incident in a Redox Dissolver
- Since the start of E-metal processing in December, 1958, critical mass control in the Redox dissolvers has been provided by a combination of administrative controls, revised dissolver charging procedures, and new dissolving processes and operation control procedures. These were all based on a maximum allowable charge of E-Metal to the dissolvers which was equivalent to 45 percent of the minimum critical mass.
- Analysis of Broadened X-ray Diffraction Peaks
- This report is a manual describing the methods developed by Stokes (1) and Warren and Averbach (2) (3) for the determination of the effects of cold work by x-ray diffraction methods. Only the method of mathematical analysis is presented while the method of obtaining the necessary x-ray diffraction patterns is not mentioned. This manual will be used for an experimental study of irradiation damage to uranium.
- Analysis of Errors to be Expected in Measuring the Neutron Absorption Cross Section of C-12
- An experiment now in progress should give some accurate information about the thermal neutron absorption cross section of carbon 12. This report outlines and summarizes this experiment and analyzes it to determine the main sources of error and the probably error in the final result.
- Analysis of High Purity Water by Spectrochemistry
- When water is used as a coolant in any heat-producing process, the purity of the cooling water is of considerable importance, both from the standpoint of build-up of deposited solids inside the cooling tubes, and as an indication of corrosion of the tubes or any other materials with which the water comes in contact. The first problem has long been recognized, and is generally solved by pretreatment of the water. Efficient treatment can reduce the total solids content to less than 0.1 ppm, and the concentration of individual elements to the order of 0.01 ppm. If water of this purity is used, the analysis of the input and output stresses can result in some useful information. The input stream analysis, of course, is direct measure of the quality of the original cooling water, and frequent analysis by a reasonably fast method can be used to keep pretreatment under control. But of even greater significance is the difference in the impurity content of input and output streams. In a simple, straight-through system the difference generally will be negligible. If a closed, recirculating system is considered, however, with the coolant water circulating through the process to be cooled and then through a heat exchanger or refrigerator, the build-up of dissolved impurities can be used as a direct indication of the rate of corrosion of the cooling system. If a closed system is used along with a means of continuous purification such as an ion exchanger, the analysis becomes a means of monitoring the efficiency of the purification system. Such applications are especially useful in research on corrosion of materials subjected to water under various conditions, and can be applied as well on a routine basis for control purposes. Analyses generally are made for each element of interest individually by the most suitable …
- The Analysis of TBP Process Streams for Calcium with the Flame Photometer
- Summary: A method was found for determining calcium concentrations in TBP process streams in spite of serious interferences bysodium, ferrous, uranyl, sulfate, phosphate, and sulfamate ions as well as by TBP. The precision attainable varied from sample to sample, depending upon its composition. In general, errors of 20% or greater occurred. The smallest determinable amount of calcium was about 10 mg/1.
- An Analysis of the In-Line Uranium Photometer Data from Purex Hot Semi-Works Runs PX-2 Through PX-9
- Results of eight runs using in-line U photometers in organic and aqueous streams of the Purex Hot Semi-Works are presented. Their operation, both mechanically and electrically, was satisfactory, indicating changes in stream U concentrations over wide ranges.
- Analysis of the Zircaloy-2 Creep Data with Two Extrapolation Methods
- The experimental evaluation of low (10⁻⁸ in/in/hr) creep rates are costly and time consuming. Thus, in answer to a request from the design group, the creep data on Zircaloy-2 obtained at Battelle Memorial Institute is extrapolated into the low creep rate range. Because the methods of extrapolation have not been evaluated at very low creep rates on Zircaloy, two different methods are used to analyze the creep data. The methods of extrapolation are given so that future analyses can be carried out by the design group or by other sections interested in predicting creep rates which have not been experimentally determined.
- Analysis of vegetation for I¹³¹
- Report detailing an analysis of the deposition of I-131 on vegetation. Analysis was necessary to determine the potential hazards of the gases from the dissolution of the metal on vegetation.
- Analytical applications of refractive index
- Report detailing the refractive index of solutions of uranyl nitrate, nitric acid and aluminum nitrate. This report builds upon preliminary data and a brief discussion that from a previous report. This report covers more accurate and detailed data that had be accumulated following the initial report.
- Analytical procedures for the metal fabrication process
- From introduction: The present report describes further refinements of the apparatus and the method to meet a need for a sensitive determination of carbon in plutonium.
- Analytical procedures for the plutonium Metal Fabrication Process
- Report describing the results of the cupferron extraction-copper spark method in determining the impurity elements in plutonium metal. This was required the 234-5 Project analytical program.
- Analytical Procedures for the Plutonium Metal Fabrication Process
- Report describing methods of determining trace impurities in plutonium in connection with the Metal Fabrication Process. The methods included are the cupferron extraction-copper spark method and the direct copper spark method.
- Analytical procedures for the plutonium Metal Fabrication Process
- A report describing a the results of a fluorimetric and volumetric method for the determination of fluoride. This method was developed for the determination of ionizable fluorine in gases in the range of 1-500ppm. This method was chosen because the determination depends on the generation of a color rather than the bleaching effect or on a change of color.
- Anodic Etching Procedure for Uranium: Useful Lifetime of Baths Without Regeneration
- The useful lifetimes of the phosphoric-hydrochloric anodic etching solution and the nitric acid stripping solutions were studied. Groups of uranium wafers of surface areas approximately 0.033 sq ft were anodically etched and stripped. From the losses in weight observed, it was concluded that at least three square feet of uranium may be anodized per liter of phosphoric-hydrochloric acid solution without regeneration. The nitric acid stripping solution was found to be satisfactory for at least one square foot of uranium per liter, but the reaction rate decreased rapidly after the treatment of two square feet per liter.
- The Anodizing of Zirconium
- Five continuous coatings were produced on zirconium coupons using an anodizing technique. These layers appear to be quite adherent and not subject to visible or audible failure caused by flaxion of the basis metal, Their abrasion resistance, though not investigated thoroughly, appears to be moderately good.
- APDAC-I, A PCTR Data Analysis Code for the IBM 709
- A flexible foil data processing program is described. Raw data on foil radioactivity are the basic input information required. Output may consists of relative activities, saturated activities, and/or cadmium ratio and flux spectrum data. A statistical analysis of the data is executed with the direct calculation, and errors estimated for the output data.
- Apparent viscosity of neutralized and concentrated raw slurry : TBP HW-no. 4 and HW flowsheet
- Report describing how the neutralized aqueous waste from the TBP Metal Recovery Process will be concentrated by evaporation to minimize the requirements for underground storage tank capacity.
- Apparent viscosity of simulated underground metal waste slurries
- From introduction: "This report presents the apparent viscosities of supernate-sludge slurries prepared synthetically to simulate the conditions known to exist in the waste storage tanks, but with fission products and plutonium absent."
- Application and Operation of the 325 Building Well Counter
- Well-type scintillation counters have found use in many radiochemical laboratories. A gamma scintillation well counter has been used to measure the gamma activity of liquid samples in the 325 Building counting room for about a year. This well counter has been built and calibrated so that gamma activity measurements made with it can be easily compared with measurements made with the gamma scintillation counter (GSC). The well counter is electronically identical to the present GSC and differs only in the shape of the crystal used and the physical arrangement of the lead shield. The crystal contains a well which allows a tube containing the sample to be inserted in the crystal. The physical arrangement of the detector greatly simplifies the preparation of liquid samples for activity measurement. The 325 Building well counter and its application to chemical research and plant process analysis will be discussed in the following paragraphs. An operating procedure is also included.
- The Application of Nuclear Track Emulsions to the Analysis of Urine for very Low Level Plutonium
- The following document analyzes plutonium in urine which uses nuclear track film for evaluation of the quantity of separated plutonium.