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Eurochemic Questions -- Preliminary Report (open access)

Eurochemic Questions -- Preliminary Report

The referenced memo asked several questions on the operation of the Purex Plant which are of interest to the Eurochemic personnel. These questions are answered below. 1. A qualitative description of the nitric acid recovery systems is desired -- flow of materials, number of pieces of equipment, etc.
Date: August 24, 1959
Creator: Geier, R. G.
System: The UNT Digital Library
New Production Reactor Thermal Shielded Studies (open access)

New Production Reactor Thermal Shielded Studies

The relative neutron capture gamma production in several prospective iron thermal shielding materials for the New Production Reactor was measured to determine the merit of adding boron to the metal. It was found that for the beam geometry the used addition of 1 1/2 percent boron to the iron before casting reduced the soft gamma production by a factor of 6.5 and the hard gamma production by a factor of 10. No attempt was made to measure gamma or neutron transmissions.
Date: August 31, 1959
Creator: Friesenhahn, S. J.
System: The UNT Digital Library
Techniques for Estimating the Specific Retention Properties of Hanford Soils (open access)

Techniques for Estimating the Specific Retention Properties of Hanford Soils

Disposal on a specific retention basic of certain radioactive liquid waste solutions emanating from separations from separations plants has been practiced at Hanford since 1944. As used at Hanford, the term "specific retention" is defined as that volume of waste liquids that may be disposed to the soil* and be held against the force of gravity by the molecular attraction between sand grains and the surface tension of the water, when expressed as percent of packed soil volume. In practice it represents the volume of liquid that may be discharged to a disposal pit of known dimensions without leakage to the ground, water, expressed as percent of the total volume of a column of soil with the same cross section as the pit, and extending from the bottom of the pit to the water table. It is recognized that some degree of lateral spreading will occur which has the effect of enlarging the volume of soil contacted by the liquid.
Date: August 20, 1959
Creator: Bierschenk, William H.
System: The UNT Digital Library
Eddy Current Ultrasonic Transducer (open access)

Eddy Current Ultrasonic Transducer

In the field of nondestructive testing the ultrasonic test method is used extensively. In this method ultrasonic energy generated by a transducer is caused to enter the test specimen. The effect on the transducer is cause to enter the test specimen. The effect on the transmission or reflection of the ultrasonic energy by differing test specimen structure is used as an indirect measure of test specimen characteristics.
Date: August 24, 1959
Creator: Libby, Hugo L.
System: The UNT Digital Library
Analysis of a Nuclear Incident in a Redox Dissolver (open access)

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.
Date: August 24, 1959
Creator: Neely, V. I.
System: The UNT Digital Library
Precision Duplication of Metal Parts in Tooling Plastic (open access)

Precision Duplication of Metal Parts in Tooling Plastic

A series of experiments has been conducted during the past eighteen months with the objective of degerming the accuracy with which precision parts can be duplicated using a castable tooling plastic as a test shape to be reproduced. A precision ground ground 1/4 inch-thick, 90° steel sector of 4'' radius was chosen. The plastics used in the experiments were the die surfacer mixes of the Devon Cooperation and Ren Plastics, Inc. These were selected for use in the test because of their dimensional stability and wear resistance. Ordinary paste type floor wax was used as a mold release. The first series of tests were primarily intended to gain facility in handling this material. After achieving some familiarity with the use of these castable plastics a technique was devised which seemed to hold promise of precision duplication.
Date: August 18, 1959
Creator: Kleinpeter, J. H.
System: The UNT Digital Library
Division of Reactor Development Programs Monthly Report- July 1959 (open access)

Division of Reactor Development Programs Monthly Report- July 1959

Basic Studies. Sinterability studies on the isomorphous system UO2-PuO2 have continued. One-half inch diameter X 3/8'' long compacts containing physical mixtures of the two components have been heated in hydrogen. Sintered density as a function of time and temperature has been determined for times of one and eight hours up to 1600 C. In general, there seems to be minima on isothermal plots of density versus composition in the intermediate range 20-40 w/o PuO2. At concentrations greater than 40 w/o PuO2, density increases rapidly with increasing PuO2. In every case pure PuO2, (produced by decomposing plutonium oxalate at at 300 C) sintered to a greater density that ball ball milled PWR grade UO2. The data, for a one hour soak time, and tabulated in percent of the theoretical crystallographic density, can be seen below:
Date: August 17, 1959
Creator: McEwen, L.H.
System: The UNT Digital Library
Recovery of Plutonium from Chloride Slag and Crucible (open access)

Recovery of Plutonium from Chloride Slag and Crucible

Neutron radiation can be greatly reduced by substituting plutonium trichloride for plutonium tetrafluoride in the dry chemistry step of metal preparation. Chloride processes are now common in the metal preparation industry, and the 234-5 Developmental Laboratory has shown plutonium trichloride can be satisfactorily prepared and reduced to the metal.
Date: August 14, 1959
Creator: Smith, R. C.
System: The UNT Digital Library
Criticality of Fuels of Low Enrichment in Cylinders (open access)

Criticality of Fuels of Low Enrichment in Cylinders

Maximum safe cylinder diameters, slab thicknesses, and minimum critical masses in spherical geometries for fuel of < 5.0& U-235 enrichment have been evaluated. It is of interest to know the minimum critical masses as a function of cylinder diameter for vessels that are not safe by geometry. Curves will be presented of critical masses as a function of cylinder diameter and fuel rod size for 1.6%, 3.0%, and 5.0% U-235 enriched metal-water systems.
Date: August 14, 1959
Creator: Ketzlach, N.
System: The UNT Digital Library
Rates of Reaction of Irradiated UO2 and Uranium Metal with Sulfuric Acid (open access)

Rates of Reaction of Irradiated UO2 and Uranium Metal with Sulfuric Acid

In the decladding of stainless steel clad fuel elements with sulfuric acid (the Sulfex process), the loss of core material to the decladding solution is determined by the rate of reaction of the core material with the solution and the time of exposure if the core to the solution. Since very little was known about the effects of irradiation history on the rates at which core materials dissolve in sulfuric acid, the present study was undertaken in an effort to determine the magnitude of such effects. This report summarizes the results obtained to date. Further work is planned when materials of higher burn-up are available.
Date: August 13, 1959
Creator: Swanson, J. L.
System: The UNT Digital Library
Plant Modification for Reprocessing Non-Production Reactor Fuels Design Criteria for Fuel Element Storage Facility Building 221-U (open access)

Plant Modification for Reprocessing Non-Production Reactor Fuels Design Criteria for Fuel Element Storage Facility Building 221-U

Facilities shall be provided in the 221-U Building for removing fuel elements from the casks as placed in the railroad tunnel from the transfer facility and moving the elements to modified existing 10' X 16' X 14' storage tanks in ten existing cells where they will be stored, until scheduled for processing.
Date: August 17, 1959
Creator: Yates, M. E.
System: The UNT Digital Library
Out-of-Reactor Tests on Pu-Al Type PRTR Elements for 1706-KER Testing (open access)

Out-of-Reactor Tests on Pu-Al Type PRTR Elements for 1706-KER Testing

The small amount of irradiation tenting experience on the plutonium-aluminum type elements planned for the Plutonium Recycle Test Reactor (PRTR) has made such testing of great importance. The high temperature pressurized recirculating water 1706 KER facility is one possible place for conducting investigations of the irradiation behavior of this type fuel element. To obtain the maximum information from the in-reactor testing and to detect possible problems, out-of-reactor test both at room and anticipated operating temperatures must be made. Room temperature pressure drop measurements and high temperatures performance of two prototypical fuel element designs proposed for KER testing are reported in this document.
Date: August 7, 1959
Creator: Doman, D. R.
System: The UNT Digital Library
Heat Transfer Calculations for CO2 Gas-Cooled Loop-PRTR (open access)

Heat Transfer Calculations for CO2 Gas-Cooled Loop-PRTR

At the request of Design Development Operation, various heat transfer and fluid flow problems were examined which are peculiar to the CO2 Gas-Cooled Loop in the PRTR. The results of these calculations are desired primarily to aid in demonstrating the adequacy of the design proposal. In addition, the operational limits of the loop and the consequences of the gas loop installation on the PRT reactor are of interest.
Date: August 4, 1959
Creator: Muraoka, J.
System: The UNT Digital Library
Field Experiments with Model Crib I. Location, Facility Design and First Experiment (open access)

Field Experiments with Model Crib I. Location, Facility Design and First Experiment

One of the research studies of the Chemical Effluents Technology Operation is the improvement of the method for predicting the capacity of a crib for the retention of wastes. In addition to laboratory work the research was extended a field experiment using a simulated crib fed with a solution containing a radioactive tracer. The purpose is twofold: (1) to check the validity of laboratory findings and (2) to observe several features of the behavior of solutions put to ground in the field.
Date: August 4, 1959
Creator: Knoll, K. C. & Nelson, J. L.
System: The UNT Digital Library
A Closed Circuit Television System for In-Well Use -- Interim Report (open access)

A Closed Circuit Television System for In-Well Use -- Interim Report

Wells drilled to date on the Hanford project represent and initial investment of over one million dollars. These nearly six hundred wells have been used and will continue to be used for observation and monitoring purposes of direct interest to ground disposal of radioactive wastes. Through measurement of depth to the water table the changing gradients as a result of large volume waste disposal are determined and direction of ground water flow established. The extent of contamination in ground water is measured in samples dawn from these wells. Aquifer permeability is measured and ground water velocity predicted from pumping tests carried out out in these structure
Date: August 5, 1959
Creator: Ratcliffe, C. A.
System: The UNT Digital Library
Cofit - A 709 Program for Determining Extrapolation Length from Horizontal Traverse Data (open access)

Cofit - A 709 Program for Determining Extrapolation Length from Horizontal Traverse Data

A program has been prepared for the 709 computer which will determine extrapolation length from horizontal traverses measurements taken in an exponential pile. The flux across the pile is assured to fit a cosine function of the form y = A cos B (X-C)
Date: August 11, 1959
Creator: Matsumoto, D. D.
System: The UNT Digital Library
Quarterly Report - October, November, December 1958 Plutonium Fuels Development Plutonium Metallurgy Operation (open access)

Quarterly Report - October, November, December 1958 Plutonium Fuels Development Plutonium Metallurgy Operation

A number of Pu-Al and UO2-PuO2 Zircaloy clad capsules have been fabricated for irradiation in the MTR. In addition, a four rod cluster containing Al 8 w/o Pu and Al 12 w/o Si 8 w/o Pu cores has been successfully irradiated and discharged from Loop 3 of the KER. A second four rod cluster is awaiting irradiation and design and fabrication of a seven rod cluster test element is underway.
Date: August 17, 1959
Creator: Wick, O.J.
System: The UNT Digital Library
709 Program for Reduction of Exponential Pile Data (open access)

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.
Date: August 20, 1959
Creator: Matsumoto, D. D.
System: The UNT Digital Library
Mechanical Features of a Continuous Ion Exchange Unit (open access)

Mechanical Features of a Continuous Ion Exchange Unit

This review covers: (a) The continuous countercurrent ion exchangers which have been described in the patent and/or technical literature. (b) Some of the other moving bed processes which are similar in mechanical arrangement to a continuous countercurrent ion exchange and which might have certain features adaptable to an ion exchange unit. (c) The auxiliary mechanical devices which are or may be used in an ion exchange apparatus.
Date: August 7, 1956
Creator: Lauer, B. E.
System: The UNT Digital Library
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
Hanford Use of Experimental Water Filter Plant (open access)

Hanford Use of Experimental Water Filter Plant

An improved method of water plant control has been developed at Hanford which employs a sensitive turbidiy measuring microphorometer and a model water filtration plant. The microphotometer operates on a light scattering principle and is accurate in the range of 0.0 to 0.1 parts per million turbidity. The model filter plant used is a five gallon per minute plant which can simulate the conditions normally occurring in the large water plants. It is the purpose of this report to describe the model filter plant and to demonstrate the value of the model and microphotometer for effective water plant control and water plant design scoping.
Date: August 20, 1956
Creator: Conley, W.R.; Botsford, C. W. & Pitman, R.W.
System: The UNT Digital Library
Incontamination of Pig Skin Contaminated With a Plutonium Solution (open access)

Incontamination of Pig Skin Contaminated With a Plutonium Solution

Different methods of decontaminating plutonium contaminated skin were studied by contamination localized areas of pig skin and then testing the different decontamination methods. Results indicate that the most effective of the decontamination methods tested involved the application of a plastic adherent material to the skin and its later removal by peeling.
Date: August 20, 1959
Creator: George, L. A.; Dockum, H. L. & Bustad, L. K.
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
Metallurgical Examination of K-Loop Fuel Elements Resulting from Rupture Incident (open access)

Metallurgical Examination of K-Loop Fuel Elements Resulting from Rupture Incident

The first and third slugs downstream from the H-Loop ruptured and a piece of can wall from the ruptured slug were received from Pile Materials Sub-Section for metallurgical examination. The examination has been completed and the extent and type off aluminum corrosion which occurred on these samples has been determined.
Date: August 13, 1956
Creator: Mallett, G. R.
System: The UNT Digital Library