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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.
Partner: UNT Libraries Government Documents Department
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Acceleration of Deuterons or Alpha Particles in the AGS

Description: The magnetic field of the AGS ring can contain particles of magnetic rigidity about 34 Bv/c. This includes not only protons of kinetic energy 33 Bev, but also 32 Bev deuterons, 64 Bev alpha particles, and conceivably heavier nuclei such as 188 Bev carbon nuclei. It will be shown in this paper that such nuclei can be injected and accelerated in the AGS if some rather small modifications are made in the injection and acceleration systems. What physics could be done with such beams? Several types … more
Date: December 28, 1962
Creator: Courant, E. D.
Partner: UNT Libraries Government Documents Department
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Some Observations Regarding Rare-Earth Lactates

Description: From abstract: "Lactates of all the rare earths except lanthanum, cerium, and praseodymium were prepared and studied. In the case of lanthanum, cerium, and praseodymium the lactates are apparently so soluble that they cannot be crystallized directly from aqueous solution. Products obtained by addition of anhydrous ethanol to sirupy solutions of the light-rare-earth lactates were not well characterized and were deliquescent. Neodymium lactate trihydrate was prepared only by the addition of alcoh… more
Date: March 28, 1962
Creator: Powell, J. E. & Farrell, J. L.
Partner: UNT Libraries Government Documents Department
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Electron Requirements of Bonds in Metal Borides

Description: From abstract: "Electrical measurements have been made on CaB6, SrB6, BaB6, YB2, YB4, YB6, and YB12 for the purpose of testing models of the electronic structure of the boron atoms in the four boride types represented. The compounds CaB6, SrB6, and BaB6 were found to be semiconductors. The Hall coefficients of YB4 was also measured, but could not be interpreted because the free electron theory does not provide a theoretical value for comparison with experiment. The results are in agreement with… more
Date: May 28, 1962
Creator: Johnson, Robert W. & Daane, A. H. (Adrian Hill), 1919-
Partner: UNT Libraries Government Documents Department
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Hazards Report for SM-1 Core Temperature and Flow Instrumentation (Task XIV) Covering Special Test Procedures.

Description: Abstract: Test procedures for special tests involving in-core SM-1 temperature and flow instrumentation are described (Task XIV Package Tests). These tests involve in-core steady state flow and temperature measurements, loss of flow transients, load transients, reduced primary system pressure operations and reduced element flow. The thermal and hydraulic conditions prevailing in these tests, including steady state and transient burnout rations, are developed. The effects of reduced system pres… more
Date: February 28, 1962
Creator: Bradley, P. L. & Coombe, J. R.
Partner: UNT Libraries Government Documents Department
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BWR Reference Design for PL-3

Description: Abstract: The natural circulation, direct cycle, boiling water reactor reference design presented in this technical report is the alternate to the preferred preliminary design developed under Phase I of the PL-3 contract. The report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant eq… more
Date: February 28, 1962
Creator: Humphries, G. E.
Partner: UNT Libraries Government Documents Department
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PWR Preliminary Design for PL-3

Description: Abstract: The pressurized water reactor preliminary design presented in this volume is the preferred design developed under Phase I of the PL-3 contact. This technical report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant equipment, waste disposal, buildings and tunnels, services, … more
Date: February 28, 1962
Creator: Humphries, G. E.
Partner: UNT Libraries Government Documents Department
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Wall and Bulk Temperatures for Fluids Flowing in Concentric Annuli

Description: From introduction: "This brief paper deals with the subject of radial temperature differences for heat transfer to fluids flowing through concentric annuli under the following conditions and assumptions: a. constant heat flux; b. fully-established turbulent flow; c. heat transfer through inner wall only; d. physical properties independent of temperature."
Date: May 28, 1962
Creator: Dwyer, Orrington Embry, 1912-
Partner: UNT Libraries Government Documents Department
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Production test IP-508-D irradiation of a porous stainless steel clad fuel element assembly

Description: A large number of irradiation tests have been conducted with UO{sub 2} fuel elements to characterize the behavior of Zircaloy cladding when cooling water is allowed to penetrate the cladding to the fuel core. The test element, is designed so that cooling water will be in contact with the surface of the UO{sub 2} fuel core during irradiation. The irradiation behavior of the UO{sub 2} will be compared to the behavior of similarly irradiated, non-defected UO{sub 2} fuel-elements. Several character… more
Date: May 28, 1962
Creator: Marshall, R. K. & Cox, J. H.
Partner: UNT Libraries Government Documents Department
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Preliminary hazards review: Overboring Hanford reactors (condensed version)

Description: This is a condensed version of an extended hazards safety review of a proposal to modify the six 8 3/8-inch lattice reactors on the Hanford site. The review was intended to satisfy the specifications for a Preliminary Hazards Review as adopted at the third meeting of the General Electric Technological Hazards Council at New York City on June 15-16, 1961. This supplement is a tabular condensation of the information in the general document. One departure is made from the specifications for such a… more
Date: August 28, 1962
Creator: Nilson, R. & Carlson, P. A.
Partner: UNT Libraries Government Documents Department
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Calculated fission product release from PRTR rupture

Description: Approximately 15 minutes after shutdown on August 21, 1962, evidence of a rupture was observed in the form of high radiation levels in the containment vessel and rupture monitor indications. Discharge of a special MgO-PuO{sub 2} test element revealed a cladding break of about 1.5 inches in length and about 1/4 inch wide in the widest place, located 36 inches from the top of the fuel element as it would have been oriented in the reactor. A visual examination in Radiometallurgy revealed that appr… more
Date: September 28, 1962
Creator: Stoddard, J. A.
Partner: UNT Libraries Government Documents Department
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Relocation of radial enrichment at the K reactors to decrease enrichment inventory

Description: The enrichment inventory required in the Hanford reactors is greatly dependent on the location of the radial enrichment ring. Present and past philosophy has dictated that the radial enrichment be located as close to the periphery of the reactors as possible, consistent with total control criteria, to obtain maximum flattening efficiency. As long as individual tube power limits dictate total pile power this philosophy of maximum flattening is consistent with a goal of maximum production. For th… more
Date: March 28, 1962
Creator: Kosmata, A. R.
Partner: UNT Libraries Government Documents Department
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Instrumentation studies, Status report 2 (High level rate-of-rise)

Description: The purpose of this document is to present the latest results of a continuing instrumentation study being conducted by Research and Engineering. In a previous report results of 1-and 6-node calculations, for percentage- and fixed temperature-trip instrumentation were presented. These results were used to obtain a general understanding of the problem and to assess the value of using a multinodal approach. Calculations to determine the amount of protection provided by linear rate and period instr… more
Date: November 28, 1962
Creator: Stiede, W. L. & Monnie, D. I.
Partner: UNT Libraries Government Documents Department
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A Review of Hanford Power Level Limits

Description: As for any nuclear reactor, the operation of the Hanford reactors is governed by many technical and administrative considerations. With the completion of current project action, later this year, certain of the technical limitations on reactor power level will be relieved, notably at the K Reactors, At that time, the technical and engineering limitations will be more liberal at some reactors than required for operation at the administrative power level limits, imposed by the Atomic Energy Commis… more
Date: June 28, 1962
Creator: Van Wormer, F. W.
Partner: UNT Libraries Government Documents Department
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Design of production test IP-468-A-FP, program for evaluation of alpha extruded fuel cores

Description: The alpha phase extrusion of dingot bars to rods for core blank heat treatment at MCW offers a three-fold incentive, including: (1) establishment of an independent alternate source of uranium cores, (2) a slight cost improvement of MCW extrusion over FMPC rolling of dingot and (3) potential improvement in core quality and performance. The purpose of this test is two-fold: (1) to evaluate gross dimensional stability and (2) to evaluate the gross irradiation performance of alpha phase extruded di… more
Date: January 28, 1962
Creator: Clinton, M. A. & Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
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Low Temperature Polymorphic Transformations of Calcined Alumina

Description: The factors which affect the transformation of amorphous alumina to crystalline alumina in the temperature range 350 to 650/sup 0/C were studied. Amorphous alumina, with small amounts of added impurities, was heated in an atmosphere containing the oxides of nitrogen, air, and water vapor, and the amount of crystalline alumina was determined. Alpha alumina was the predominant crystalline form after heating amorphous alumina that was prepared in a fluid bed calciner. The effects of temperature, c… more
Date: September 28, 1962
Creator: Murray, R. F. & Rhodes, D. W.
Partner: UNT Libraries Government Documents Department
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Improved Zirconium Alloys Annual Report: 1961 - 1961

Description: Annual technical report describing the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between February 1, 1961 to February 28, 1962 and was conducted by the United States and the European Atomic Energy Community (EURATOM).
Date: February 28, 1962
Creator: Weinstein, Daniel & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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Primary Shield Optimization Survey for the PL-3 Reactor

Description: A detailed study of four reactor and shield configurations was made. Two basic reactor types, the boiling water and pressurized water reactors were considered. Shield materials of lead-water and iron-water were used with varying thicknesses for determining the optimum shield configuration for the PL-3 reactor. Also presented is a survey of available shielding codes. (auth)
Date: June 28, 1962
Creator: Scoles, J. F. & Crouch, A. N.
Partner: UNT Libraries Government Documents Department
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Comparison of Gaseous Waste Handling Systems for PL-3

Description: Gaseous waste handling systems are compared for direct and indirect boiling water and pressurized water reactors for PL-3 application. Areas that are common to the various concepts are not discussed since they do not enter into a comparison study. The major differences present are in the handling of active gases released to or held in the primary system coolant. These gases which could be present, their possibIe release from the system, and the necessary processing requirements are discussed in… more
Date: February 28, 1962
Creator: Noble, J. H. & Duke, E. E.
Partner: UNT Libraries Government Documents Department
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