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Terminal report on the Radiolanthanum Laboratory

Description: A report which intends to acquaint the reader with the planning of the radiochemical laboratory designed for the analytical control of the radiolanthanum process and to define the terminal status of the design of this laboratory and its equipment.
Date: July 21, 1950
Creator: Figenshau, J. K.
Partner: UNT Libraries Government Documents Department
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General Engineering and Consulting Laboratory "Hot Service" Turbine Pump Progress Report: May 1 to June 15, 1948

Description: Introduction: "This report covers progress on the testing of the General Engineering and Consulting Laboratories Turbine Pump No. 1 from May 1, 1948 to Jun 15, 1948. All testing prior to April 30, 1948 has been described in Redox Experiment Testing Report No. 1 (Document HW-9474) and No. 2 (Document HW-9694)."
Date: June 21, 1948
Creator: Stringer, J. T. & Allen, A. W.
Partner: UNT Libraries Government Documents Department
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Terminal Report on the Radiolanthanum Laboratory

Description: "The purpose of this present document is twofold: (1) To acquaint the reader with the planning of the radiochemical laboratory designed for the analytical control of the Radio-lanthanum Process. (2) To define the terminal status of the design of this laboratory and its equipment."
Date: July 21, 1950
Creator: Figenshau, J. K.
Partner: UNT Libraries Government Documents Department
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Process Tube Pressure - Stress Factors

Description: This report discusses the state of stress caused by pressure in process tubes, elaborating on five "theories of failure" that each explain the stress in process tubes in a different manner. These theories, which are depicted in a graph, include maximum normal stress, maximum strain, maximum shear stress, maximum strain energy, and maximum strain energy of distortion.
Date: February 21, 1952
Creator: Reinker, P. H.
Partner: UNT Libraries Government Documents Department
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Water Adsorbed by Graphite at Various Relative Pressures

Description: Summary: "The quantity of water adsorbed by graphite at various relative pressures has been determined and the data are presented in graphical and tabular form."
Date: July 21, 1953
Creator: Spalaris, C. N.
Partner: UNT Libraries Government Documents Department
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Examination of Discharged Process Tubes

Description: Introduction: "The observations reported in this document were obtained by C.H. Pitt during his assignment to the Corrosion Group September through October 1951. The tubes examined were: 1.) 0893-F Discharged for corrosion examination after leaking; 2.) 1488-DR Discharged to determine caused of obstruction; 3.) 2276-D Discharged for corrosion examination; 4.) 2376-D Discharged for corrosion examination; 5.) 1185-H Discharged to evaluate the effect of magnesium front dummies."
Date: July 21, 1952
Creator: Dalrymple, R. S.
Partner: UNT Libraries Government Documents Department
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Corrosion of Redox Waste Storage Tank Construction Materials

Description: From introduction:"It was the aim of this investigation to determine the resistance of several materials of construction to current and anticipated and anticipated Hanford separation process waste streams under specific conditions. The corrosion rates of mild steel and austenitic stainless steel and the resistance of several commercial protective coatings were established."
Date: August 21, 1950
Creator: Koenig, W. W. & Sanborn, K. L.
Partner: UNT Libraries Government Documents Department
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Induction Melting of Uranium Dioxide Powder

Description: Fused uranium dioxide has desirable characteristics for fabricating high density nuclear fuel elements by swaging. Methods of preparing dense uranium dioxide particles being investigated at HAPO include are arc fusion, and sintering and crushing of low density powder. This paper reports the results of exploratory experiments to prepare fused uranium dioxide by induction heating of low density powder in graphite crucibles.
Date: March 21, 1959
Creator: Newkirk, H. W.
Partner: UNT Libraries Government Documents Department
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Uranium Cold Extrusion

Description: Several hollow uranium cores of "C" size I & E diameters were fabricated by cold extrusion (550 to 750 F) at Hunter Douglas Aluminum Corporation. Results show diameter control and reproducibility are excellent. Preferred orientation induced by this process is completely removed by a single standard beta heat treatment.
Date: April 21, 1959
Creator: Riedeman, G. W.
Partner: UNT Libraries Government Documents Department
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Remote Area Scintillation Monitoring System

Description: This report was written to describe briefly several possible variations of such systems along with probable cost estimates. Previous work has been shown that the application of scintillation detectors is the simplest and most reliable means for such monitoring. By proper detector selection and measuring methods, the system can be of an approximate gamma dose-rate with gamma energy independence above about 100 Kev. The same system using detector change only is directly applicable to beta, gamma,… more
Date: April 21, 1959
Creator: Spear, W. G.
Partner: UNT Libraries Government Documents Department
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Penetration of Respiratory Protective Equipment by Ruthenium at Building 202-S

Description: The four types of respirator cartridges used at the 202 S Building were tested against aerosols found at that location, and in the laboratory against non-radioactive gaseous ruthenium tetroxide. Positive penetration of two types of cartridges was shown with one process aerosol. Gaseous ruthenium tetroxide penetrated all types of cartridges tested. Leaks were found in some of the cartridges. Particle size of aerosol particles was measured by means of cascade impactor samples and electron photomi… more
Date: February 21, 1955
Creator: Gill, W. E.
Partner: UNT Libraries Government Documents Department
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Purex Cooling Water Disposal Scope Study

Description: The purposes of this study are to review the available information affecting the disposal of Purex cooling water, powerhouse waste water, and B plant cooling water, to consider the feasibility of various disposal schemes, and to prepare recommendations to the Manufacturing Department for the most desirable courses of action.
Date: September 21, 1955
Creator: Corley, J. P.
Partner: UNT Libraries Government Documents Department
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Thermal Annealing Kinetics of Interlayer Spacing Damage in Irradiated Graphite

Description: The primary objective of this work is to add to the understanding of irradiated graphite. This report describes an experimental technique whereby changes in crystal lattice parameter may be studied as a function of time at constant temperature. The results given here are limited to changes in the C₀ spacing for a typical sample of irradiated graphite in the temperature range 100 to 750 C.
Date: June 21, 1955
Creator: Nightingale, R. E.
Partner: UNT Libraries Government Documents Department
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A Review of the MPC's for Natural Thorium

Description: The possible hazards from the refining and processing of thorium are of wide interest in atomic energy work. A review of the data available was made at Hanford in the last year to support consultations on the hazards of radioisotopes with other plants which may handle thorium. Since a major discrepancy between the published values of air MPC's and the metabolic data was noted, a review of the calculations on thorium was made in order to obtain the best estimates available. This document tabulat… more
Date: November 21, 1955
Creator: Healy, J. W.
Partner: UNT Libraries Government Documents Department
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Stack Effluent Monitor Operation and Maintenance

Description: The Stack Effluent Radioisotope Monitor is an instrument which continuously measures and records the amounts of each of several different radioactive isotopes in the stack effluent of the Redox Facility. An informal report, HW-56151, describing the theory of operation and the circuits was prepared and is available to Hanford personnel from the technical files. The formal report, HW-56151 Rev, containing essentially the same information, is available from the Office of Technical Services, Depar… more
Date: July 21, 1959
Creator: Harvey, R. A.
Partner: UNT Libraries Government Documents Department
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An Aqua Recia Flowsheet for Uranium Dissolution

Description: Relatively long time cycles are required for the standard nitric acid dissolution of enriched uranium using safe batch size techniques for criticality control. Upwards of forty eight hours are required for the total dissolution of solid of I and E enriched slugs in nitric acid. The dissolution capacity may be increased by: (1) using a dissolver critically safe by virtue of its geometry or, (2)increasing the rate of uranium dissolution. Dilute agua regia -- a mixture of hydrochloric and nitric a… more
Date: July 21, 1959
Creator: Shefcik, J. J.
Partner: UNT Libraries Government Documents Department
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A Remote Phase Separation Bulb for Highly Radioactive Sample Analyses

Description: Extraction systems involving chelating agents are widely used in radiochemical separations on a control basis due to the economy in time and equipment. In the case of waste streams, the element of interest is, by definition, at a very low concentration in the presence of gross fission product activities. The resultant large sample size necessary for a reliable analytical results creates a marked radiation hazard to laboratory personnel.
Date: July 21, 1959
Creator: Campbell, M. H.
Partner: UNT Libraries Government Documents Department
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The Pilot Plant Operation of a Vertical Tube, Recirculating Dissolver for the Dissolution of Uranium Dioxide in Nitric Acid

Description: The need for criticality control in the proposed reprocessing of slightly enriched non-production fuels at Hanford has led to the development of a geometrically "safe", vertical tube, recirculating dissolver. A study of the nitric acid dissolution of uranium dioxide in a pilot plant dissolver of this type is reported here. The study was pointed toward the comparison of uranium dioxide dissolution rates in a batch and a recirculating dissolver and the definition of hydraulic problems associated … more
Date: March 21, 1960
Creator: Smith, P. W.
Partner: UNT Libraries Government Documents Department
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Controlled Temperature Irradiation of Graphite Interim Report No. 4. PT-IP-22A

Description: Property changes to common graphites resulting from reactor irradiation depends strongly on the temperature of exposure. Radiation affects at 30 C and 400 to 500 C are quite well known; however, at intermediate temperatures, results are not well known although a large volume of graphite in most reactors operate in this range. Production test, IP-22A, was reactivated, after a dormant period of many months, to study radiation damage between 30 and 400 C. This report concerns mainly the experiment… more
Date: October 21, 1959
Creator: Koyame, K.
Partner: UNT Libraries Government Documents Department
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Transient Pressures Developed by Sodium-Nitric Acid Reactions

Description: The Atomic Energy Commission has assigned Hanford Atomic Products Operation the responsibility of reprocessing some of the slightly enriched uranium fuel elements from nuclear power reactors. Some stainless steel clad fuel elements contain sodium or a sodium-potassium alloy as a heat transfer medium between metallic core and outer sheath. The nature of the reaction between water and sodium is well known; however, the reaction between sodium and an oxidizing acid is more energetic and not so wel… more
Date: October 21, 1959
Creator: Huck, C. E. & Shefcik, J. J.
Partner: UNT Libraries Government Documents Department
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