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Production test IP-255-A-9-FP E-N demonstration test

Description: The objectives of the test described in this report are to evaluate the integrity of I & E MINT fuel elements canned by the ``C`` process to determine the conversion ratio of I & E geometry E-N ``striped loadings,`` and to provide a demonstration loading for a full reactor loading incorporating a ``striped`` center loading and a fringe ``blanket`` loading. This test will involve two portions a 26 tube block loading of I & E enriched uranium and MINT fuel elements arranged in a striped array, an… more
Date: May 8, 1959
Creator: Hall, R. E. & Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
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Working Committee report from the General Electric Company-Hanford

Description: This Hanford-General Electric Report to the Working Committee details activities in fuel element fabrication, canning, and testing during this reporting period.
Date: April 8, 1959
Creator: Stringer, J. T.
Partner: UNT Libraries Government Documents Department
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Production test IP-226-A: Irradiation of enriched seven-rod cluster elements with twenty and thrity mil Zircaloy-2 jackets

Description: Seven enriched seven-rod cluster elements, three with thirty mil Zircaloy-2 jackets and four with twenty mil Zircaloy-2 jackets, will be irradiated at high temperature to an exposure of 4500 MWD/T. Coolant temperatures in the internal and external flow channels will be measured during irradiation.
Date: January 8, 1959
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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A Study of Reactor Systems for the Production of Tritium and Radioactive Cobalt

Description: "A conceptual design study of reactors for the join production of tritium and colbat-60 has been made. The study covered a family of four reactors raging in thermal power from 16.5 MW to 150 MW, and designed for corresponding annual productions ranging from 0.5 to 5.0 million curies of tritium respectively."--P. v.
Date: June 8, 1959
Partner: UNT Libraries Government Documents Department
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Summary of HRT Run 14

Description: This report presents a detailed study of HRT Run 14, which was abruptly terminated by the formation of a hole in the Zircaloy-2 core tank. In this run the reactor was operated at high temperature and pressure for ten days from March 25 to April 4, 1958. Nuclear power operation extended from March 29 until April 4, when fuel solution leaked into the heavy-water blanket. The maximum power level attained was 6.4 Mw.
Date: June 8, 1959
Creator: Engel, J. R.; Haubenreich, P. N.; Kolb, J. O. & Richardson, D. M.
Partner: UNT Libraries Government Documents Department
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The Rate of Uranium Sorption by a Strong-Base Anion-Exchange Resin

Description: The rate of uranium sorption by a strong-base anion-exchange resin (Dovex 21K) from a uranyl sulfate solution (U 0.005 M, H2SO4 0.02M, SO4 0.2 M) was studied using a stirred vessel technique and measuring the U235 gamma radiation on each bead. Resin initially in the chloride form and the sulfate for was studied.
Date: July 8, 1959
Creator: Bresee, J. C.
Partner: UNT Libraries Government Documents Department
open access

Calculations for Irradiation of Natural UO2-ThO2

Description: Calculations are given for eighteen stainless steel clad helium bonded specimens of UO2-ThO2 containing normal U to be placed in 6 holes in a holder in a position of the ORR not to exceed a peak unperturbed flux of 4 x 10^14 n.cm^2/sec and irradiated to a peak nvt of 1.96 x 10^21 neutrons/cm^2
Date: June 8, 1959
Creator: Ullmann, J. W.
Partner: UNT Libraries Government Documents Department
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Physical Properties of Neutralized Zirflex Waste

Description: Zirflex cladding waste is to be neutralized to pH 10 before transfer to waste storage tanks. This treatment causes the precipitation of zirconium oxide or hydroxide, which may lead to flow difficulties during transfer. The purpose of this investigation was to determine the physical properties and flow characteristics of the neutralized slurry to assist in the selectin of satisfactory transfer equipment and storage conditions.
Date: June 8, 1959
Creator: Amos, L. C.
Partner: UNT Libraries Government Documents Department
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Critical Incident Alarm - Model I Instruction and Maintenance Manual

Description: The HAPO Critical Incident Alarm, Model I, is an instrument designed to give an audible and visual alarm signal in the event of a critical incident to which it is exposed. There will be thirty-one (31) of these instruments installed and several spares located in the various manufacturing buildings in the Chemical Processing Department where there exists any possibility of a critical incident occurring. The instrument is intended as a post or after-the-fact warning device. It will offer no prote… more
Date: May 8, 1959
Creator: Kelly, P. R.
Partner: UNT Libraries Government Documents Department
open access

Improvements in Water Treatment for Once-Through Reactor Cooling

Description: Nearly all nuclear reactors being designed and built today- whether for research, power, or productions of fissionable materials- use recirculating fluids for cooling. However, a number of production reactors are still operating with single-pass cooling by treated natural water. The Hanford Atomic Products Operation of the General Electric Company presently operates production reactors for the AEC at Richland, Washington. The first reactors were built during World War II, and utilized a standar… more
Date: May 8, 1959
Creator: Richman, R. B.
Partner: UNT Libraries Government Documents Department
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Study of Factors Influencing Ductility of Iron-Aluminum Alloys. Monthly Letter Report No. 8, 15 March 1959 to 15 March 1960

Description: Studies are being made on the effects of variation of aluminum content, heat treatment, surface preparation, and other metallurgical factors on the room temperature ductility of Al-- Fe alloys. It is estimated that approximately 65 percent of the proposed research has been completed over the first eight and one-half months of the contract period.
Date: December 8, 1959
Creator: Perkins, Frank C. & Nachman, J. F. (Joseph F.)
Partner: UNT Libraries Government Documents Department
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Condensate System. Section II. Fifth Core I, Seed 1. Test Results DL-S-105

Description: The purpose of the test was to fill the condensate storage tank and the Condensate System and obtain satisfactory preliminary operation. The components of the Condensate System performed adequately and satisfactorily with the exception of fill control valve (M9-VI). This valve (M9-VI) is not used in the current operation procedure.
Date: December 8, 1959
Partner: UNT Libraries Government Documents Department
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Chemical Development Section C Monthly Progress Report August 1959

Description: Uranium extractions from carbonate solutions were effective and phase separation rates were rapid using a new commercial quaternary extractant, Alamine 336. Extraction coefficients were approximately proportional to the quaternary concentration. Addition of -0.5 mole tridecanol/mole quaternary to the solvent gave optimum extraction efficiency and phase separation rates.
Date: September 8, 1959
Creator: Brown, K. B.; Allen, K. A.; Coleman, C. F.; Crouse, D. J. & Ryon, A. D.
Partner: UNT Libraries Government Documents Department
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Nuclear Instrumentation Operation During Plant Operation. Section I. First Performance. Core I, Seed 1. Test Results DL-S-309, RNI-41

Description: The purpose of the test was to evaluate the operation of the Nuclear Instrumentation Power Range Amplifier during start up. While the station was operating at a gross load of 16.5 megawatts, a variation of 0, 8.5, 2.7 and 4.4 existed between the compensated ion chamber currents (CIC) and the test currents for channels A, B, C and D respectively. The off site modifications to channel C power range amplifier did not cause the ion chamber current and test current to be the same at 16.5 megawatts g… more
Date: December 8, 1959
Partner: UNT Libraries Government Documents Department
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