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Existing reactor expansion study basis

Description: The latest HAPO Five Year Program review, HW-59633, forecasts substantial increases in Pu production from the eight existing Hanford reactors over the next several years. These production increases would be attained by a combination of several methods which include increased reactor power levels resulting from higher process water flow rates and coolant bulk outlet temperatures, improved time operated efficiency, higher conversion ratios, and reduced transient reactivity losses. In order to pro… more
Date: June 24, 1959
Creator: Heacock, H. W.
Partner: UNT Libraries Government Documents Department
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H Reactor enrichment

Description: No Description Available.
Date: February 24, 1959
Creator: Turner, R. L.
Partner: UNT Libraries Government Documents Department
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The Palmolive cycle at Hanford

Description: The Palmolive program is directed toward the recovery of neptunium-237 and production of plutonium-238. The neptunium is recovered during the chemical processing of irradiated uranium and is purified and fabricated into target elements. The target elements are irradiated to produce plutonium-238 by neutron capture of neptunium-237 and are processed to provide plutonium for shipment to the final customer and neptunium for recycle within the system. The following report summarizes a preliminary e… more
Date: June 24, 1959
Creator: Judson, B. F. & Beard, S. J.
Partner: UNT Libraries Government Documents Department
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Design of production test IP-272-A-FP, pilot test of self-supported fuel elements in ribless zirconium process tubes

Description: Irradiation of solid and I & E fuel elements in B Reactor ribless process tube facility showed reduced hot spot incidence in the self-supported fuel elements. Since it appears expedient to evaluate the concepts of the larger fuel core size and/or greater coolant flow, on a pilot scale, this report presents the design of a pilot test. Up to 100 ribless zirconium process tubes are to be installed in C Reactor, and reactor equipment modifications will be made to permit routine charging of these tu… more
Date: September 24, 1959
Creator: Hodgson, W. H. & Hall, R. E.
Partner: UNT Libraries Government Documents Department
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LECTURE NOTES ON REACTOR CONTROLS

Description: This material is the outgrowth of the notes prepared for lectures on reactor controls given in 1953-55 at the Oak Ridge School of Reactor Technology. The course on reactor controls was for the purpose of acquainting the student with some of the elementary considerations involved in setting up a control and safety system for a nuclear reactor. Topics are discussed on kinetics, neutron energies, poisoning, analog computing, instrumentation, start-up, neutron sources, etc. (W.D.M.)
Date: June 24, 1959
Creator: Walker, C S
Partner: UNT Libraries Government Documents Department
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HYDROGEN PICKUP DURING CORROSION OF ZIRCONIUM ALLOYS

Description: Several factors such as alloy composition, hydrogen content of the alloy, surface hydrides, and hydrogen content of the water have been investigated for their effect upon the amount of hydrogen picked up by zirconium alloys during corrosion in 680 deg F water. Metallic additions of nickel increase hydrogen pickup, antimony, chromium, and iron appear to decrease the hydrogen pickup, while the addition of tin has little or no effect. The hydrogen content of the metal (50 to 400 ppm) or of the wat… more
Date: September 24, 1959
Creator: Berry, W.E.; Vaughan, D.A. & White, E.L.
Partner: UNT Libraries Government Documents Department
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DEMONSTRATION OF THE ZIRFLEX PROCESS ON IRRADIATED PWR BLANKET FUEL

Description: Fifteen PWR blanket fuel specimens varying in burnup from 80 to 1100 Mwd/ T, were declad with boiling 6 M NH/sub 4/F-1.0 M NH/sub 4/NO/sub 3/ before the UO/ sub 2/ core was dissolved in 10 M HNO/sub 3/. Uranium and plutonium losses to the decladding solution were less than 0.2% in nearly all runs. While these ments with unirradiated fuel, they are of the same order of magnitude as those obtained in the testing of the hot cell HF was used as the decladding reagent, the uranium and plutonium loss… more
Date: August 24, 1959
Creator: Gens, T. A.; West, G. A. & Ferris, L. M.
Partner: UNT Libraries Government Documents Department
open access

Lecture Notes on Reactor Controls

Description: This course on reactor controls is for the purpose of acquainting the student with some of the elementary considerations involved in setting up a control and safety system for a nuclear reactor. This material is the outgrowth of the notes prepared for the lectures on Reactor Controls given in the Oak Ridge School of Reactor Technologu. The lectures given by T. E. Cole in 1953-1955 are the basis of portions of the subject matter on reactor kinetics. Many suggestions and ideas contributed by E. R… more
Date: June 24, 1959
Creator: Walker, C. S.
Partner: UNT Libraries Government Documents Department
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A Parametric Study of a Gas Cooled Reactor

Description: The results of a parametric study on a gas cooled reactor are reported on herein. The system considered was a helium cooled, UO2 fueled arrangement with the fuel assemblies consisting of clusters of long cylindrical elements, each element covered b a stainless steel jacket. The axial power distribution was assumed to be a "chopped cosine" having an axial peak-to-average power 1.32.
Date: July 24, 1959
Creator: Epel, L. G.
Partner: UNT Libraries Government Documents Department
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THE ZIRFLEX PROCESS INTERIM DEVELOPMENT SUMMARY

Description: The Zircaloy-clad fuels and the application of the Zirflex Process for dissolution are discussed. Zirflex chemical flowsheets are presented as developed by pilot plant operatlons. The Zirflex Process is applicable to the reprocessing of fuels from the Dresden Reactor and the PWR Reactor. Other applications of the process are the Plutonium Recycle Test Reactor fuels and the New Production Reactor fuels, possible fuels from the Experimental Breeder Reactor; NPD-2 fuels; and fuels from Carolina-Vi… more
Date: June 24, 1959
Creator: Platt, A.M. & Cooley, C.R.
Partner: UNT Libraries Government Documents Department
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SM-2 REACTOR CORE AND VESSEL REVIEW REPORT FOR AUGUST 25, 1959 TO DECEMBER 14, 1959

Description: The most adverse power distribution was revised based on a comparison of PDQ calculations and measurements made during the SM-2 flexible experiments. A review of the basic nuclear data and calculational models employed in the SM-2 nuclear analysis was rnade. A comparison between initial reactivily, hot-to-cold reactivity change, and xenon reactivity with experiment was rnade. Based on a revised power distribution, the core flow requirement was reestimated to be 7800 gpm. Tentative designs of th… more
Date: December 24, 1959
Partner: UNT Libraries Government Documents Department
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SPRAY DEPOSITION OF CALCIUM METAL ON NICKEL OR INCONEL

Description: The inert--gas arc-spray method was studied in an effort to develop a continuous process for coating metals with calcium. Duplex electrode arc-spray equipment was used throughout the investigation. While the process appeared feasible, vapors produced during arc spraying and generally poor adhesion of the calcium to the base metal were considered the major deterrerts to the process. Other methods studied or investigated disclosed that the plasma-jet process improved the bonding between calcium a… more
Date: August 24, 1959
Creator: Haskins, A.F. & Evans, R.M.
Partner: UNT Libraries Government Documents Department
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A PARAMETRIC STUDY OF A GAS COOLED REACTOR

Description: The results of a parametric study on a gas cooled reactor are repotrtd. The system considered was a heliumcooled, UC/sup 2/-fueled arrargement with fuel assemblies consisting of clusters of long cylindrical elements, each element covered by a stainless steel jacket. The axial power distribution was assumed to be a chopped cosine having an axial peak-to-average power of 1.32. The three parameters of interest in the study were the diameter of coolant channel, pressure drop through core, and pumpi… more
Date: July 24, 1959
Creator: Epel, L.G.
Partner: UNT Libraries Government Documents Department
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HIGH-LEVEL SPILL AT THE HILAC

Description: On July 3, 1959, an incident occurred in the Hilac Building when the turning of the wrong valve resulted in pressurizing a helium cooling box, with a resultant blowout of a thin foil. The burst of He gas disintegrated experimental foils made up with 10/sup 11/ dpm of Cm/sup 244/. The resultant activity was quickly dispersed as airborne particulates throughout the building. The 27 people in the building were evacuated within 10 minutes under surveillance of the Health Chemistry personnel; wherev… more
Date: September 24, 1959
Creator: Garden, N B & Dailey, C
Partner: UNT Libraries Government Documents Department
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Estimate of Hazard Produced by Accidental Release of Gaseous Fission Products from an ORR Fused Salt Capsule Experiment

Description: An accidental release of gaseous fission products from an ORR fused salt capsule, containing 26 mg. of U/sup 235/, was postulated and the resuiting hazard estimated by calculating the maximum external and internal dose an individual could receive from exposure to the gaseous fission products and their decay products. Assuming all the contained gaseous fission produets are released, the resulting external and internal dosc, to organs other than the thyroid, arc insignificant. The dose to the thy… more
Date: April 24, 1959
Creator: Adams, R. E. & Browning, W. E.
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.
Partner: UNT Libraries Government Documents Department
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Eurochemic Questions -- Preliminary Report

Description: 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.
Partner: UNT Libraries Government Documents Department
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Strontium Program Quarterly Summary Report: November 1958 - January 1959

Description: From Abstract: "This report is one of a sequence of quarterly reports, each designed to up-date its predecessor beginning with HASL-42, "Environmental Contamination from Weapon Tests." Herein are reported data which have accrued since HASL-51. In particular, the levels of strontium 90 in fallout, milk, tap water, vegetation, and foods are given, based on data available from November 1, 1958 to January 30, 1959."
Date: February 24, 1959
Creator: Hardy, Edward P., Jr. & Klein, Stanley
Partner: UNT Libraries Government Documents Department
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Adams disassembly procedure for Bldg. 10, Nevada Test Site

Description: The disassembly of the `Adams` primary was scheduled for April 28, 29, and 30, 1959. The method of disassembly is provided as a procedure to be accomplished in order and the time and initials of the person accomplishing each step recorded.
Date: April 24, 1959
Creator: Beckman, K. F.
Partner: UNT Libraries Government Documents Department
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The Zirflex- Interim Development Summary

Description: The processing of spent fuels from nuclear power and propulsion reactors is planned by Hanford Atomic Products Operation as part of the Atomic Energy Commission's interim processing scheme. The spent nuclear fuels have cores of UO2, U, or alloys of U-Mb, U-Al, or U-Zr clad in either stainless steel, aluminum, or Zircaloy. This report discusses only the Zircaloy-clad fuels and the applications of the Zirflex Process for dissolution. Zirflex chemical flow sheets are presented as developed by pilo… more
Date: June 24, 1959
Creator: Platt, A. M. & Cooley, C. R.
Partner: UNT Libraries Government Documents Department
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Quarterly Report- July, August, September 1958 Plutonium Fuels Development Plutonium Metallurgy Operation

Description: Examination of Al- 1.65w/o Pu and Al- 12 w/o Si- 1.65 w/o Pu capsules irradiated 55- 60% burnout of the plutonium atoms revealed a 1.4% volume increase and no apparent microstructural changes. A four rod cluster containing Al-8 w/o Pu and Al-12 w/o Si-8 w/o Pu alloy cores is currently under irradiation in Loop 3 of KE Reactor at a water temperature of approximately 230C. A second cluster has been fabricated an is scheduled for charging late in 1958. Two seven-rod clusters for irradiation in KE… more
Date: February 24, 1959
Creator: Wick, O.J.
Partner: UNT Libraries Government Documents Department
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