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Improved Calibration Facility

Description: Aid in redesign of the calibration facility in order to: 1. Reduce the rate of exposure for calibration personnel below 1 mr/hr; 2. Reduce the rate of exposure outside of the 3745 Building; 3. Reduce the risk of breaking radium sources; 4. Improve the efficiency of calibration procedures by: a. Allowing calibration to be done faster; b. Providing several calibration ranges which can operate simultaneously in the present space allowed; c. Allowing instrument survey work to proceed while calibrat… more
Date: August 22, 1995
Creator: Roesch, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Bend and Impact Tests on Porous Alundum Filter Material

Description: Porous alundum filter plate samples were received for testing to determine the effects of Redox process solutions and conditions on bend and impact properties. Alundum has been suggested as a barrier material for use in the Redox Silica Gel Absorption Column T-101. Consequently, data on possible engineering property changes caused by exposure to separation process solutions and radiation are needed to evaluate the applicability of alundum as a barrier material.
Date: unknown
Creator: Boyd, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Columbia River Travel Time Measurements by Float Methods

Description: One of the problems associated with evaluating the hazards resulting from the discharge of radioactive pile coolant water into the Columbia River results from the subsequent consumption of the river water by cities downstream of Hanford. Determination of the travel time of the river water from the reactor cooling water discharge points to the first downstream cities to consume the river water (Pasco and Kennevick) is a necessary part of the hazard evaluation. Knowledge of the travel time is req… more
Date: unknown
Creator: Soldat, J. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion of Stainless Steel and Titanium in Purex 2WW

Description: In the Purex process, nitric acid is recovered from aqueous wastes by concentration and rectification. The concentrator bottoms are relatively corrosive to stainless steels, particularly on heat-exchange surfaces. This report summarizes studies aimed at determining corrosion rates for certain candidate materials of construction (304-L, 347, 312 stain steels and A-70 titanium) for the aqueous waste concentrators. Synthetic Purex Process 2WW, representing bottoms from the low level waste concentr… more
Date: unknown
Creator: Fraser, M. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford Special X-Ray Photometer: Mark II

Description: The special x-ray photometer was designed to measure various characteristics of high-absorption materials by comparing the attenuation of an x- ray beam in passing through a sample of known size with the attenuation through a standard. A general description, discussion of elements, safety features and cautions alignment and adjustment, and operation and maintenance are presented.
Date: unknown
Creator: Cartmell, T. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Metallurgy Lectures - Chapter 11

Description: Dimensional instability was one of the first difficulties encountered with uranium fuel elements. Early in the operation of the HAPO reactors it was found that uranium fuel elements changed shape as a result of having been irradiated. This problem of dimensional instability has been vigorously pursued up to the present day.
Date: unknown
Creator: Last, G. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radioactivity Levels of the Columbia River Below Richland, Washington for the Period January, February, March 1956

Description: In the Columbia River downstream from Richland, Washington there is a gradual decrease in the concentration of radioactive isotopes. At any one location there are fluctuations due to factors such as ditution and decay time. During this period at all locations the concentration of alpha particle emitters in water averaged below the detection limit of 3 x 10⁻⁹ μ c/gm. Beta particle emitters in water upstream of McNary Dam increased by a factor of 1.5 to 2, with averages at various locations rangi… more
Date: unknown
Creator: Clukey, H. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HAPO IB Fission Product Shipping Cask Design Evaluation Report

Description: As a result of the interest in fission products for use as heat sources and/or radiation sources, in early 1960. Hanford was authorized to supply a semi-refined cerium-144 rare earth product to Oak Ridge National Laboratories. Facilities were installed for collecting this product and a cask war designed for shipping this product as a stabilized, dry powder. Since that time, numerous improvements have been made in the design of the HAPO I cask as described in Revision O of this document. In add… more
Date: December 28, 1962
Creator: Smith, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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"Crud" Scrubbing with a Purex-Type Zebra Cartridge

Description: Entrained solids have in the past been one of the major factors limiting solvent extraction fission product decontamination. These solids are known to be surface active, to absorb fission products, and to form interfacial films or "cruds". A major step in eliminating these cruds was taken when the Purex columns were modified to operate with the interfaces at the waste ends of the columns rather than the product ends. This type of operation tended to flush the solids out with the waste rather th… more
Date: October 17, 1961
Creator: Richardson, G. L
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Recovery of Fission Product Rare Earth Sulfates from Purex LWW

Description: A research and development program aimed at devising processes for the economical recovery of the potentially valuable long-lived fission products from Purex waste has been under wat at Hanford for several years. When this work has begun, the concentrated waste was primarily a nitric acid solution (6 to 10 M HNO3) containing the fission products and relatively small concentrations of iron, sulfate, and other corrosion products. Flowsheets based on classical separation schemes and rather similar… more
Date: May 10, 1961
Creator: Wheelwright, E. J. & Swift, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Power Tests for PRT Reactor

Description: Startup and testing of the PRTR has been divided into three parts, Design Tests, Critical Tests and Power Tests. This document is the third of the series and describes the performance tests which will be made under nuclear power and the general schedule of operation. Responsibility for the startup of the reactor has been assigned to the PRTR Startup Council. The Power Test Sub-Council, which has done the planning of the initial power operation, was established by the Startup Council. Operation … more
Date: April 1, 1961
Creator: Lewis, W. R.; Atwood, J. M.; Dunn, R. E.; Evans, E. A.; Fox, J. C.; Peterson, R. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of Gamma Radiation on the Physical Properties of Elastics

Description: This article presents data on the effects of gamma radiation on the physical properties of a number of different classes of plastics materials of construction which were screened to determine their capabilities and limitations for service in applications where ionizing radiation exists. The irradiations were carried out in air at ambient temperature at normal atmospheric pressure to various gamma radiation doses up to 1*10^9 r depending upon the stability of the materials to radiation exposure.… more
Date: January 20, 1961
Creator: Harrington, Robert
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Notes on Lattice Parameter Calculations

Description: In the last two or three years there has been a notable improvement in the knowledge and understanding of reactor lattice physics. During this interval, measurements of parameters have been improved and the methods of analysis have been greatly strengthened. It has become apparent that the classical ways for computing the lattice parameters are not sufficient. It is the purpose of this report to publish under one cover as much of the most recent information as possible.
Date: October 6, 1960
Creator: Joanou, G. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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APDAC-I, A PCTR Data Analysis Code for the IBM 709

Description: 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.
Date: September 7, 1960
Creator: Lilley, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Project CGC-830 Plant Modifications for Reprocessing Non-Production Reactor Fuels

Description: Facilities are to be designed for installation at Hanford for the reprocessing of irradiated, low enrichment fuels from non-production reactors, see Reference 1 and 2. The initial design of the processing facilities is to be based on processing the fuels discharged from the Dresden, Yankee, Piqua, Pathfinder and Shippingport (blanket elements only) reactors. Properties of the fuels and cladding make it impossible to completely process them in existing equipment, although the separation and deco… more
Date: July 29, 1960
Creator: Bierman, S. R.; Graf, W. A.; Kass, M.; Kligfield, G.; McKee, R.W.; Patridge, L. F. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Coagulant Aids as Filter Aids

Description: The Hanford water treatment plants were operated for a number of years with alum as a coagulant and activated silica as a coagulant and a polyacrylamide as a filter conditioning agent. (other polyelectrolytes may be used.) Sufficient time has elapsed to make a comparison of the two methods of operation valid and useful. Such a comparison is the purpose of this paper.
Date: July 21, 1960
Creator: Conley, W. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PCTR Measurement of EGCR Control Rod Worth

Description: This paper describes the measurement of control rod strength in the PCTR. The first section outlines the theory and method of such a measurement, and the second section presents the results of the measurement of the Experimental Gas Cooled Reactor (EGCR) control rod strength. The reactor parameter actually inferred is the difference in the infinitive multiplication factor for a control rod supercell with and without the control rod in place in the supercell. These measurements are, therefore, v… more
Date: July 20, 1960
Creator: Nichols, P. F.; Engesser, F. C. & Oakes, T. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Integrated Radiological Instrumentation System Planning

Description: In recognition of the need for an integrated system plan for future development requirements for radiological instrumentation, this information report was written to provide the initial step concerning such a planning. The report is to be considered a basic information analysis of the present in-use plant radiological instrumentation, of the instrumentation now undergoing active development, and of the future development work contemplated.
Date: July 14, 1960
Creator: Spear, W. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Invention Report: Hermetically Sealed Closure on a Sheathed Thermocouple

Description: Applications of sheathed (metal) thermocouples may require in many instances, the insertion of the thermocouple thermal junction into an area that must be hermetically sealed to the outside. This same area usually contains highly reactive heat transfer medium such as an eutectic alloy of sodium and potassium of sodium alone. When fissionable materials are being irradiated, fission products that are driven off would also be present and must be contained under varying temperatures and pressures.
Date: July 12, 1960
Creator: Kosut, Bert S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PRTR Calandria Fabrication Report

Description: The Plutonium Recycle Test Reactor is heavy water moderated with a heavy or light water reflector contained by a complex aluminum vessel called a Calandria. ( See Figure 1). Construction of this vessel started in August, 1958, at a large West Coast vendor's plant and was completed at Hanford in December, 1959. The fabrication problems associated with a high integrity welded aluminum vessel were generally unrealized prior to this period. This report covers the fabrication of the Calandria and li… more
Date: July 12, 1960
Creator: Pedersen, L. T. & Kreiter, M. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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