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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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Rupture Kinetics of Zircaloy-Clad Fuel Elements in High Temperature Water and Steam Interim Report 6 Effects of Carbon and Zirconium Content on Uranium Corrosion and Rupture Mechanism

Description: This is the sixth in a series of interim reports describing various phases of the study of fuel element rupture kinetics and mechanisms. Previous reports issued are: No. 1- Experimental Methods and Procedures, HW-61378, No. 2- Coextruded Rod Elements with Pinhole Defects, HW-61379, No. 3 - Mechanism of the Uranium-Water Reaction, HW - 61799, No. 4 Coextruded Tube Elements with Pinhole Defects and Various Annular Spacings, HW- 62348, No. 5- Comparison of In-Reactor and Ex-Reactor Ruptures, HW-62… more
Date: December 30, 1959
Creator: Troutner, V. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development and Testing of an Improved Agitator for the Redox and Purex Separations Plants

Description: Relatively frequent agitator failures in HAPO Separations Plants have interfered with process continuity, contributed to process difficulties, and resulted in considerable maintenance expense. Predominantly the failures have been because of gear-reduction drive unit break-down or because of metallic fatigue and degeneration of the shaft-paddle assemblies. A simplified, slow-speed, direct drive agitator, previously described in HW-52755, proved to be quite durable and satisfactory during extende… more
Date: December 24, 1959
Creator: Dunn, J. & Sloat, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Steady-State Recirculated Reactor Stability and Operational Characteristics - Water and Metal Temperature Coefficients

Description: 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 stabi… more
Date: December 23, 1959
Creator: Allen, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design Criteria for PRP- Critical Facility Project CAH-842

Description: The PRP Critical Facility is an experimental reactor for use in determination of basic nuclear constants of heterogenous reactors recycling plutonium, and exponential and criticality studies at power levels up to 100 watts and neutron fluxes of about 109 nv. Provision is made for changing reactor lattices using irradiated and unirradiated fuel elements with either a light or heavy water moderator.
Date: December 18, 1959
Creator: Nelson, H. K. & O'Neill, G. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ionium (Thorium-230) for Radioisotope Preparation (Status Report)

Description: For many years effort has been directed toward the development of means for the practical utilization of the heat evolved from the radioactive decay of certain fission and irradiation products. Fission products, in view of their availability in the plentiful, high-level wastes resulting from the processing of irradiated, nuclear reactor fuels have been most intensively studied for applications where their heat of decay might be converted into useful energy such as electricity for the operations… more
Date: December 15, 1959
Creator: Coppinger, E. A. & Rohrmann, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion of Type 202 Stainless Steel in High Temperature Water

Description: The chromium-nickel-manganese alloys are a group of austenitic stainless steels which were developed during the Korean War to conserve nickel. These alloys are very similar to their corresponding 300 Series grades in mechanical, physical and corrosion properties. A portion of the nickel in the 300 Series grades has been replaced by approximately 2% manganese for each percent of nickel replaced. Two compositions, AISI 201 and AISI 202, are recognized as standard grades. Two other compositions, A… more
Date: December 11, 1959
Creator: Larrick, A. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Zirflex Dissolution of the Annular Cladding of Simulated Power Fuel Elements

Description: The current interest in a tube-in-tube type Zircaloy-2 clad UO2 fuel element for use in the power reactors provided the incentive for a study of the dissolution of cladding from an annular space. The objectives of the study were to compare the estimated rate of dissolution in the annuli with rates on fully exposed metal. Because of an interest from the design standpoint, heat balance data from the study are reported.
Date: December 9, 1959
Creator: Smith, P. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Autoclave Corrosion Behavior of U-Low Carbon and U-Low Zirconium Alloy Fuels

Description: A preliminary evaluation of the autoclave corrosion behavior of a series of U-low C alloys and a series of U-low Zr alloys prepared by Fuels Fabrication Development Operation has been made. The corrosion testing was conducted by Coatings and Corrosion Operation by the experimental methods and procedure outlined in HW-61378.
Date: December 1, 1959
Creator: Goffard, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comments on Equipment for a PRTR Water Quality Control Laboratory

Description: This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating… more
Date: December 1, 1959
Creator: Anderson, H. J. & Peray, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Studies on the Oxides of Plutonium

Description: In support of the Plutonium Recycle Program at Hanford, the properties of PuO2 are being investigated. This paper reports sintering studies on PuO2 and PuO2-UO2 mixtures and solid solutions; melting studies on PuO2 and UO2; thermal expansion data to 1000 C; and irradiation data on PuO2-UO2 mixtures. The existence of a continuous series of solid solutions formed during sintering has been established for the system UO2-PuO2. A linear relation between lattice parameter and composition exists. Exte… more
Date: December 1959
Creator: Chikalla, T. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Correlation of Exponential and PCTR Measurements of Cluster Fuel Elements with Theory

Description: Accurate knowledge of the lattice parameters comprised in the four factor formula k∞=η∈Pi are required for optimum designing of reactors. In the special case of cluster fuel elements conventional handbook formulas are of little use. It is the intent of this paper to report the results of some recent improvements in the calculation of these parameters. By the addition of certain refinements in the calculation of these parameters. By the addition of certain refinements to the conventional calcula… more
Date: December 31, 1958
Creator: Joanou, G. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fluorescent X-Ray Spectrography- A Recent Analytical Technique

Description: Because of the relative simplicity of the X-Ray spectra and recent improvements in instrumentation, analytical applications of X-Ray of spectrography are becoming very popular. The method us applicable to both qualitative and quantitative determinations of all elements heavier than sodium. Elements in multicomponent systems, such as alloys and minerals, and elements such as, W, Pt, Nb, Ta, Hf, Zr, and the rare earths, which are difficult to separate or determine by other methods, can usually be… more
Date: December 17, 1958
Creator: Lambert, M. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Regeneration of Silver Reactors

Description: A study of the variables involved in regeneration was undertaken to determine means of improving the regeneration efficiency and increasing the useful life of a reactor. Information gained from regeneration studies on a 4-inch-diameter by 8-foot-high column indicates that the present regeneration procedure is optimum as to quantity, concentration, and rate of addition of regenerant solution. It appears feasible to restore a plugged reactor by washing off all the silver nitrate from the packing … more
Date: December 27, 1955
Creator: Amos, L. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Safety Aspects of Purex Plant Concentrator Operation

Description: 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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Tentative Anion Exchange-Precipitation Procedure for the Determination of Cs¹³⁷

Description: An anion exchange precipitation procedure was developed for the determination of Cs¹³⁷ in various aged fission product waste solutions, and other solutions containing Cs¹³⁷. The procedure is based on the ability of an anion exchange column to function simultaneously at an anion exchanger and as a precipitating agent (1).
Date: December 22, 1955
Creator: Perkins, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary of HAPO Research and Development Program on Ceramic Fuel Materials

Description: The Metallurgy Research Sub-Section at HAPO has conducted a research and development study of a variety of nuclear fuel materials. A summary of the status of the program currently being conducted on ceramic fuel material and a brief discussion of the future program is outlined below.
Date: December 12, 1955
Creator: Sanderson, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transient Flow of Steam-Water Mixtures

Description: In the analysis of problems involving transient flow and heat transfer in steam-water mixtures, it is necessary to derive an approximate integral equation of motion for a non-ideal compressible fluid in a duct having finite discontinuities in flow geometry. This equation is derived in this document.
Date: December 12, 1955
Creator: Tippets, F. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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