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Crack Propagation Tests ofZincaloy-2 Reactor Pressure Tubing in Both the Normal and Hydrided Conditions

Description: The purpose of this document is to discuss the problems of crack propagation, and catastrophic brittle fracture and to discuss tests that are designed to predict the ability of the material to resist brittle fracture.
Date: June 1, 1954
Creator: Aungst, R. C. & Defferding, Leo J.
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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A Study of the Wear and Galling of Autoclaved Zircaloy-2 By Various Materials

Description: This is the third of a series of reports describing the phases of a study of the wear and galling of autoclavedZircaloy-2 by various bearing surface materials. The first report (1) showed that increasing contact area between the autoclaved Zircaloy-2 surfaces will not prevent scratching. It also showed that metals softer than Zircaloy-2 in general do not scratch it. The second report (2) described how eight metals and alloys were wear-tested on autoclaved Zircaloy-2 as prospects for fuel elemen… more
Date: July 5, 1960
Creator: Weber, J. W.
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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Depassivation of 304-L Stainless Steel in Sulfex Decladding Solutions

Description: In the Sulfex process, stainless steel cladding, generally 304-L, is removed from fuel elements by dissolution in boiling four to six molar sulfuric acid. When cladding removal is complete, the decladding solution is removed is removed to waste. The exposed fuel cores are rinsed and dissolved in nitric acid.
Date: June 30, 1960
Creator: Duke, E. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thickness Measurement by Ultrasonic Frequency Modulation

Description: A prototype instrument has been designed and built which demonstrates an ultrasonic pulse echo technique of measuring metal thickness in the range .010 to .080 inches. Extension of the range of measurement on the thick side appears straightforward, however, transducer frequency response considerations may limit the extension of the method for very thin sections. The instrument is based upon the principle that sections, when driven by pulses of vibratory energy, resonate at frequencies dependen… more
Date: June 28, 1960
Creator: Lambert, T.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fluidized-Bed Calcination Studies with Stimulated ICPP Waste Solution

Description: At the present time, high-radioactivity-level wastes at Hanford are neutralized and stored as liquid in underground tanks lined with mild steel. This method of storage is relatively inexpensive and is satisfactory on a short-term basis. However, on a long term basis, liquid storage is less desirable than solid storage because of the greater mobility of the liquid. In addition, storage as aa solid would significantly reduce the volume of waste stored. Consequently, various research and developme… more
Date: June 6, 1960
Creator: Schneider, K. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Termination Report for Development Test IP-306-K Spline Coilers at K Reactor

Description: A reliable spline disposal system is necessary for full utilization of the Poison Spline Control System. The spline choppers were not reliable enough so a spline coiler was developed and designed to replace the choppers. A Development Test, IP-306-X (HW-63820), was issued authorizing on-pile testing of the spline coiler at X area. This report closes the Development Test and discusses the use of spline coilers.
Date: June 24, 1960
Creator: McCarthy, P. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Non-destructive Testing Hanford Fuel

Description: At present, emphasis is being given the application of nondestructive testing to the inspection of nuclear fuel in conjunction with complete product specifications. The objective is to quantitatively specify fuel quality parameters, and to measure the entire fuel production against these specifications nondestructively. Under this concept the acceptability of a given fuel element becomes a well-defined factor readily determined by appropriate nondestructive tests.
Date: June 22, 1960
Creator: Worlton, D.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Use of Isolated Junction Sheathed Thermocouples for Moderator Temperature Measurements

Description: Two types of enclosed hot junction arrangements are possible with sheathed mineral insulated thermocouples. They are the integral junction and he isolated junction. The integral junction is formed by welding, soldering, brazing or forging the two wires into the end of the sheath. The process forms a good thermal and electrical contact between the three materials.
Date: June 16, 1960
Creator: Lovett, D. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Steam Water Pressure Drop and Critical Discharge Flow - A Digital Computer Program

Description: It is the purpose of this report to explain the bands and uses of a digital computer program for the calculation of steady state steam-water pressure drop and critical flow in pipes. The program has been coded for the IBM 709 computer. While so attempt has been made to obtain improved models of two-phase flow, it is believed that the numerical integration technique used in the code will permit more accurate calculation where pressure drops are large compared to the upstream pressure. The techni… more
Date: June 17, 1960
Creator: Massena, W. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sampling and Analytical Data on Al-Pu Alloy for PRTR Start-Up Tests

Description: In answer to the question, "How well do we know the composition of the fuel material for the PRTR start-up tests?", the analytical data on the PRTR fuel elements and other fuel elements which were fabricated by similar processes was gathered and analyzed. The results of this analysis are presented.
Date: June 15, 1960
Creator: Bloomster, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Water Chemistry for KER Loop 1- June 29, 1959 to December 31, 1959

Description: One of the primary reasons for operating the high pressure KER loops is to obtain information concerning water quality control characteristics for recirculating water cooled reactors. The KER-1 loop is predominantly carbon steel and approximates the water quality conditions specified for the New Production Reactor (NPR).
Date: June 15, 1960
Creator: Demmitt, T. F. & Wood, E. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary Listing of Subcritical Measurements of Heterogenous Water-Uranium lattices Made at Hanford

Description: Exponential and critical approach type measurements have been made to determine the critical mass, material buckling, and in a few cases, the extrapolation length for the lattices. This report attempts to list all measurements on water-uranium heterogenous lattices made to date at Hanford. All lattices were water moderated hexagonal arrays loaded with uranium of enrichments up to 3.15.
Date: June 8, 1960
Creator: Lloyd, R. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Process Improvement Transition Authorization #11-I Installation of Van Stone Seal Inserts - F Reactor.

Description: Continued operation of F reactor with high water collection rates during the past 12 years has resulted in numerous detrimental effects. In addition to promoting external corrosion tube leaks, water leaks have corroded the Gunbarrel to the biological shield donut assemblies and cast iron thermal shield blocks, thus preventing the majority of tubes in F reactor from unrestrained thermal expansion. Fatigue of the Van Stone flange under the resulting compression loads leads to eventual failure in … more
Date: June 7, 1960
Creator: Russell, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Scavenging as a Predisposal Treatment for NPR Decontamination Wastes

Description: A disposal method is needed for wastes generated from the decontamination of the NPR primary coolant loop. The limitations imposed by facilities design criteria for the disposal of NPR wastes preclude direct river release of the spent cleaning solutions because of the anticipated quantities of radioactive material in these wastes. The soil at a 100-N Area trench or crib should not be relied on for removing radionucleotides by ion exchange or filtration because of the high salt content of the wa… more
Date: June 7, 1960
Creator: Koop, W. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Study for the Feasibility for the Large Sale Recovery of Ionium (Thorium-230) from the Uranium Ore Milling Industry in the United States

Description: Over the past ten years, there has been considerable interest and expenditure on the recovery of ionium (thorium-230) from certain residues accumulated from the World War II uranium process at St. Louis, Missouri. Most of these efforts were reported in the classified literature. However, an unclassified report was issued recently by the Mallinckrodt Chemical Works on the plant design for ionium recovery. A review of the earlier efforts shows that consideration of ionium recovery was limited to… more
Date: June 1, 1960
Creator: Rohrmann, C. A.
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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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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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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Nuclearly Safe Mass Limits, Volume Limits, Infinite Cylinder Diameters and Slab Thicknesses for Slightly Enriched Uranium Rods in Light Water

Description: Graphs have been made which show the nuclearly safe parameters for uranium rods in light water with uranium enrichments up to five weight percent U-235. These data were to serve as a guide to those persons who may be involved with the maintenance of nuclear safety in handling and processing operations with slightly enriched uranium fuel elements. The data are applicable to fuel element fabrication and processing operations, and in general to those operations involving the handling and storage o… more
Date: May 24, 1960
Creator: Clayton, E.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly Report Technology of Non-Production Reactor Fuels Processing Budget Activity 2790

Description: This report summarizes the research and development work carried out during December, 1959, and January and February, 1960, for Budget Activity 2790 - Separations Development for Non-Production Reactors. The major effort on Activity 2790 has been completed. Current efforts on the remaining problem areas will enable Hanford to begin reprocessing fuel elements from power reactors which employ depleted or slightly enriched uranium fuels in July, 1962.
Date: May 19, 1960
Creator: Cooper, V. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plutonium Oxide- Plastic Mixtures for Critical Mass Studies

Description: Critical mass experiments to be conducted at HAPO will require dilute and concentrated plutonium solutions. Since very high plutonium concentrations (~2,000 g/l) cannot be attained in pumpable solutions, solid plutonium compounds will be utilized for this phase of the work. Mixtures of plutonium oxide and polyethylene, methyl methacrylate or paraffin compacted in containers have been considers for use in highly-concentrated plutonium systems of known hydrogen to plutonium atomic ratio (H/Pu).
Date: May 12, 1960
Creator: Crocker, H. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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