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General Engineering and Consulting Laboratory "Hot Service" Turbine Pump Progress Report: May 1 to June 15, 1948 (open access)

General Engineering and Consulting Laboratory "Hot Service" Turbine Pump Progress Report: May 1 to June 15, 1948

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.
System: The UNT Digital Library
Redox : Analytical Research Group Report [for] March and April 1949 (open access)

Redox : Analytical Research Group Report [for] March and April 1949

Report discussing the results of research conducted by the Hanford Works Analytical Research Group during the period from March 1949 to April 1949.
Date: June 21, 1949
Creator: Schmidt, H. R.
System: The UNT Digital Library
The Determination of Free Nitric Acid in Solutions Containing Uranyl Nitrate, Aluminum Nitrtae and Sodium Dichromate (open access)

The Determination of Free Nitric Acid in Solutions Containing Uranyl Nitrate, Aluminum Nitrtae and Sodium Dichromate

The following report describes the developmental process of the determination of free nitric acid in solutions containing uranyl nitrate, aluminum nitrate and sodium dichromate.
Date: October 21, 1949
Creator: Moore, Robert Lee & Schmidt, H. R.
System: The UNT Digital Library
Statistical evaluation of calibrartion data-infrared method for determination of % TBP (open access)

Statistical evaluation of calibrartion data-infrared method for determination of % TBP

A report which discusses the data submitted for evaluation. This data is about optical densities from infrared spectrometer readings on eight standard samples, ranging in percent TBP from 6.71 to 17.85.
Date: March 21, 1950
Creator: Healy, W. C.
System: The UNT Digital Library
Terminal report on the Radiolanthanum Laboratory (open access)

Terminal report on the Radiolanthanum Laboratory

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.
System: The UNT Digital Library
Terminal Report on the Radiolanthanum Laboratory (open access)

Terminal Report on the Radiolanthanum Laboratory

"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.
System: The UNT Digital Library
Corrosion of Redox Waste Storage Tank Construction Materials (open access)

Corrosion of Redox Waste Storage Tank Construction Materials

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.
System: The UNT Digital Library
Process Tube Pressure - Stress Factors (open access)

Process Tube Pressure - Stress Factors

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.
System: The UNT Digital Library
Examination of Discharged Process Tubes (open access)

Examination of Discharged Process Tubes

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.
System: The UNT Digital Library
Water Adsorbed by Graphite at Various Relative Pressures (open access)

Water Adsorbed by Graphite at Various Relative Pressures

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.
System: The UNT Digital Library
Penetration of Respiratory Protective Equipment by Ruthenium at Building 202-S (open access)

Penetration of Respiratory Protective Equipment by Ruthenium at Building 202-S

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 photomicrographs. A high percentage of the aerosol particles was found to be less than 0.2 microns in diameter. Ru¹⁰³ + Ru¹⁰⁶ and Zr⁹⁵ + Nb⁹⁵ were shown to be present in the process aerosol by gamma ray spectrometer analysis. Possible causes of penetration of respiratory equipment by ruthenium are discussed and suggestions made for alleviating the problem.
Date: February 21, 1955
Creator: Gill, W. E.
System: The UNT Digital Library
Thermal Annealing Kinetics of Interlayer Spacing Damage in Irradiated Graphite (open access)

Thermal Annealing Kinetics of Interlayer Spacing Damage in Irradiated Graphite

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.
System: The UNT Digital Library
Buckling of an Elliptic Cylinder First Roots of the Zero Order, Modified Mathieu Function (open access)

Buckling of an Elliptic Cylinder First Roots of the Zero Order, Modified Mathieu Function

This paper presents values of the constant B², commonly called the buckling, when 0 vanishes on the surface of a right elliptic cylinder.
Date: July 21, 1955
Creator: Gast, Paul F. & Bournis, Anthony
System: The UNT Digital Library
Purex Cooling Water Disposal Scope Study (open access)

Purex Cooling Water Disposal Scope Study

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.
System: The UNT Digital Library
A Review of the MPC's for Natural Thorium (open access)

A Review of the MPC's for Natural Thorium

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 tabulates the pertinent data and applies them to the calculation of the MPC of thorium.
Date: November 21, 1955
Creator: Healy, J. W.
System: The UNT Digital Library
Induction Melting of Uranium Dioxide Powder (open access)

Induction Melting of Uranium Dioxide Powder

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.
System: The UNT Digital Library
Remote Area Scintillation Monitoring System (open access)

Remote Area Scintillation Monitoring System

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, slow neutron and fast neutron detection. Any type of alarming device desired can be incorporated.
Date: April 21, 1959
Creator: Spear, W. G.
System: The UNT Digital Library
Uranium Cold Extrusion (open access)

Uranium Cold Extrusion

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.
System: The UNT Digital Library
An Aqua Recia Flowsheet for Uranium Dissolution (open access)

An Aqua Recia Flowsheet for Uranium Dissolution

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 acids -- is known to dissolve uranium much more rapidly than nitric acid. This reports present a flowsheet for the rapid dissolution of uranium slugs in dilute agua regia.
Date: July 21, 1959
Creator: Shefcik, J. J.
System: The UNT Digital Library
A Remote Phase Separation Bulb for Highly Radioactive Sample Analyses (open access)

A Remote Phase Separation Bulb for Highly Radioactive Sample Analyses

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.
System: The UNT Digital Library
Stack Effluent Monitor Operation and Maintenance (open access)

Stack Effluent Monitor Operation and Maintenance

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, Department of Commerce, Washington 25, D. C.
Date: July 21, 1959
Creator: Harvey, R. A.
System: The UNT Digital Library
Controlled Temperature Irradiation of Graphite Interim Report No. 4. PT-IP-22A (open access)

Controlled Temperature Irradiation of Graphite Interim Report No. 4. PT-IP-22A

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 experimental details and evaluation of the equipment necessary for the controlled temperature irradiation.
Date: October 21, 1959
Creator: Koyame, K.
System: The UNT Digital Library
Transient Pressures Developed by Sodium-Nitric Acid Reactions (open access)

Transient Pressures Developed by Sodium-Nitric Acid Reactions

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 well known. The unknown factor of interest is the pressure generated by the reaction between the next transfer medium and the acid used for fuel dissolution prior to solvent extraction. The scouting studies discussed in this report were made to determine hydraulic pressures developed when sodium is exposed to cold concentrated nitric acid beneath the liquid surface.
Date: October 21, 1959
Creator: Huck, C. E. & Shefcik, J. J.
System: The UNT Digital Library
The Pilot Plant Operation of a Vertical Tube, Recirculating Dissolver for the Dissolution of Uranium Dioxide in Nitric Acid (open access)

The Pilot Plant Operation of a Vertical Tube, Recirculating Dissolver for the Dissolution of Uranium Dioxide in Nitric Acid

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 with the recirculation of nitric acid, by air lift, technique through beds of reacting uranium dioxide.
Date: March 21, 1960
Creator: Smith, P. W.
System: The UNT Digital Library