[Tolerance requirements] (open access)

[Tolerance requirements]

This report consists of a discussion concerning maximum allowable tolerance dose for personnel working in a contaminated area on an 8 hour per day basis. It is a follow up of a telephone conversation between the Medical Superintendent at Hanford Works and Dr. Robert Lash of Knoxville, Tennessee on April 13, 1943. (CBS)
Date: September 4, 1944
Creator: Norwood, W. D.
Object Type: Report
System: The UNT Digital Library
Hanford Engineer Works, Technical progress Letter No. 17, October 27--November 2 (open access)

Hanford Engineer Works, Technical progress Letter No. 17, October 27--November 2

This report details technical activities of the Hanford Engineer Works for the week of October 27, 1944 through November 2, 1944.
Date: November 4, 1944
Creator: Bugbee, S. J.
Object Type: Report
System: The UNT Digital Library
100-D unit purge (open access)

100-D unit purge

None
Date: June 4, 1945
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Tolerable Concentration of Product in Drinking Water (open access)

Tolerable Concentration of Product in Drinking Water

None
Date: August 4, 1945
Creator: Parker, H. M.
Object Type: Report
System: The UNT Digital Library
CHEMICAL STABILITY OF HIGH TEMPERATURE POWER PILE (open access)

CHEMICAL STABILITY OF HIGH TEMPERATURE POWER PILE

None
Date: February 4, 1947
Creator: Simon, S.L. & Fitzgerald, J.V.
Object Type: Report
System: The UNT Digital Library
Precipitation of Sodium Diuranate from Pitchblende Liquors (open access)

Precipitation of Sodium Diuranate from Pitchblende Liquors

In the treatment of carnotite concentrates, sodium diuranate was prepared by acidifying tricarbonate liquors to eliminate carbon dioxide, and then precipitating the sodium salt by the addition of caustic. Direct precipitation of uranium by the addition of caustic to tricarbonate liquors was used when pitchblende ores were processed, because this procedure was more effective in giving a product with a low molybdenum content. Tests of this method in the laboratory and Pilot Plant indicated that low uranium losses (0.2 to 0.3%) would be encountered with typical liquors if 1.7 to 2.0 lbs of caustic were added for every pound of uranosic oxide in solution. Since losses as high as 3% were incurred in plant operations, further work was undertaken, in an effort to reduce the uranium concentration in the waste liquors.
Date: February 4, 1947
Creator: Brimm, E. O., Dr.
Object Type: Report
System: The UNT Digital Library
Preparation and use of Ammonium Diuranate in the Ether Extraction Process (open access)

Preparation and use of Ammonium Diuranate in the Ether Extraction Process

In the ether extraction process, as originally developed, purified uranium dioxide was obtained by evaporation and calcination of the uranyl nitrate solution, followed by calcination of the resultant UO{sub 3}. It was suggested that an alternate procedure might be developed, involving the precipitation of uranium from the nitrate solution as ammonium diuranate. This material could then be calcined to uranosic acid, or reduced directly to the dioxide. It had already been established that ammonium diuranate could be precipitated completely from uranyl nitrate solutions. Experiments were carried out to determine whether a basic nitrate, analogous to a known sulfate salt, would be formed in the process. Both direct reduction of the diuranate to UO{sub 2} and calcination to uranosic acid were investigated to determine the physical characteristics and residual nitrogen of the resultant brown oxide.
Date: February 4, 1947
Creator: Brimm, E. O., Dr. & Mohr, P.
Object Type: Report
System: The UNT Digital Library
100 Areas technical activities report: Physics, March 1947 (open access)

100 Areas technical activities report: Physics, March 1947

U.M. Staebier reports from the pile areas. Foil tests were conducted at the B pile. A power coefficient test was performed at the D pile; special request materials and reactivity balance are also reported. The new No. 2 horizontal rod of the F pile has been slightly resized. Graphite temperature readings, thermal conductivity calculations, special request materials, and reactivity balance are also reported. General physics are considered. Production tests 105-85-P and 106-1-P are reported. Egg testing at the 305 test pile is discussed. (GHH)
Date: April 4, 1947
Creator: Gast, P. F.
Object Type: Report
System: The UNT Digital Library
Medical and Health Divisions Quarterly Report October 1947 To Jan. 1948 (open access)

Medical and Health Divisions Quarterly Report October 1947 To Jan. 1948

This quarterly report discusses the following topics: (1) the metabolic properties of plutonium and allied materials; (2) biological studies of radiation effects; (3) biological effects of radiation from external and internal zones; and (4) health chemistry.
Date: February 4, 1948
Creator: Authors, Various
Object Type: Report
System: The UNT Digital Library
[Office of Hanford Directed Operations events of importance for week ending February 2, 1949] (open access)

[Office of Hanford Directed Operations events of importance for week ending February 2, 1949]

This report details events of importance reported by the Hanford Operation Office for the week ending February 2, 1949.
Date: February 4, 1949
Creator: Schlemmer, F. C.
Object Type: Report
System: The UNT Digital Library
[Office of Hanford Directed Operations events of importance for week ending March 2, 1949] (open access)

[Office of Hanford Directed Operations events of importance for week ending March 2, 1949]

This report details events of importance reported by the Hanford Operations Office for the week ending March 2, 1949.
Date: March 4, 1949
Creator: Schlemmer, F. C.
Object Type: Report
System: The UNT Digital Library
Lithium Isotope Separation by Electrolysis (open access)

Lithium Isotope Separation by Electrolysis

Two approaches to lithium isotope separation have been followed in this research and are described and compared. One is electrolysis in non-aqueous systems at high cathode efficiency. The other is electrolysis in aqueous systems with anode depolarizers.
Date: September 4, 1950
Creator: Kennedy, Joseph W
Object Type: Report
System: The UNT Digital Library
Report for General Research August 7 to October 30, 1950 (open access)

Report for General Research August 7 to October 30, 1950

Investigation of the physical and chemical properties of polonium important to its behavior and for the improvement of the quantity and quality produced is being continued. A sample of polonium is approximatelyf 1 x 10{sup 9} disintegrations per minute was counted in a Logac for 250 days in order to determine the half life. A statistical treatment of the results gave a half life of 138.3562 {+-} 0.446 days. Combined with previous calorimetric determinations a new grand mean of 138.3975 {+-} 0.0091 days resulted. The wavelengths of 138 lines appearing in the spark spectrum between 3050A and 3463A (Region 4) have been tentatively assigned to polonium and have a probable error of less than 0.02A. Thirty six lines in Region 6 (4225A to 5675A) tentatively assigned to polonium have a probable error of less than D D6A. A measurement of the resistivity of polonium has given a value of about 95 microohm centimeters, and although the Hall voltage could not be measured with much precision, it was possible to set a maximum value of 0.03 millivolt. These values indicate the polonium is a metallic conductor rather than a semiconductor. A rugged but compact gauge made of stainless steel with a …
Date: December 4, 1950
Creator: Haring, M. M.
Object Type: Report
System: The UNT Digital Library
Report for General Research January 8, to April 30, 1951 (Alpha - Neutron Volume) (open access)

Report for General Research January 8, to April 30, 1951 (Alpha - Neutron Volume)

An experimental, gamma-sensitive, coaxial radioelectric cell has been tested by the Control Section. It was found to be as precise as the rotating sample gamma counter but much faster and simpler to operate. A gamma-sensitive, radioelectric cell of improved design has been constructed for the 'Y' Section. A neutron sensitive radioelectric cell has been tested over a range of pressures with various filling gases and with several combinations of hydrogenous electrode backings. Neutron to gamma discrimination ratios as high as 2,000 to 1 were obtained, A multiple electrode, alpha radiation, radioelectric cell using coated plastic electrodes gave increased current output, but the electrode life was quite short. Preliminary life tests indicated that aluminum electroscope foil would give excellent electrode life and techniques were worked out for making good electrodes of both aluminum and of gold electroscope foil. The vacuum-pressure gas system has been redesigned and completely rebuilt (p. 5) The fast-neutron scintillation counter is much smaller and lighter than a B-wall proportional counter and a large moderator. The former is more efficient for polonium-beryllium neutron sources but is less efficient for radium-beryllium neutron sources or for polonium sources producing lower energy neutrons The fast neutron scintillation counter would thus be …
Date: January 4, 1951
Creator: Haring, M. M.
Object Type: Report
System: The UNT Digital Library
Recommendations: Recovery of product from 234-5 Building miscellaneous liquid wastes (open access)

Recommendations: Recovery of product from 234-5 Building miscellaneous liquid wastes

None
Date: June 4, 1951
Creator: Cooper, V.R.
Object Type: Report
System: The UNT Digital Library
Compilation of data on 51 ruptured slugs (open access)

Compilation of data on 51 ruptured slugs

The following tabulation includes information on all uranium slug failures which have occurred through September 26, 1951. The four suspect slugs which are listed were discharged from tubes which gave strong indication of containing ruptures. Although no obvious rupture could be found among the slugs from these tubes, the listed pieces exhibited defects which may be incipient ruptures.
Date: October 4, 1951
Creator: O'Keefe, D.P.
Object Type: Report
System: The UNT Digital Library
Pile water modifications at DR and H Areas for increased production facilities (open access)

Pile water modifications at DR and H Areas for increased production facilities

A detailed study was undertaken to investigate the feasibility of modifying the front and rear face piping at DR and H Areas to permit increased production rates. This study is in conjunction with a larger investigation concerning methods of increasing plant production facilities. The results of the subject study indicate that approximately one year would be required for the design, procurement, and delivery of critical materials, and that the estimated construction shutdown time to complete each unit is 50 work days on a three shifts basis. Although the length of time required to perform the proposed construction work is not in line with the planned 30 day shutdown period, it is believed that the 50 days reflected by this estimate is realistic and necessary. A critical material schedule, design schedule, construction schedule and force requirement charts are presented on pages 9 to 13 inclusive.
Date: October 4, 1951
Creator: Andersen, R. K.
Object Type: Report
System: The UNT Digital Library
Technical activities report: Heat, water, and mechanical studies (open access)

Technical activities report: Heat, water, and mechanical studies

Topics in the heat studies section include: front and rear face reflector shields at the C-pile; process tube channel thermocouples; water temperature limits for horizontal rods; slug temperature and thermal conductivity calculations; maximum slug-end cap temperature; boiling consideration studies; scram time limit for Panellit alarm; heat transfer test; slug stresses; thermal insulation of bottom tube row at C-pile; flow tests; present pile enrichment; electric analog; and measurement of thermal contact resistance. Topics in the water studies section include: 100-D flow laboratory; process water studies; fundamental studies on film formation; coatings on tip-offs; can difference tests; slug jacket abrasion at high flow rates; corrosion studies; front tube dummy slugs; metallographic examination of tubes from H-pile; fifty-tube mock-up; induction heating facility; operational procedures and standards; vertical safety rod dropping time tests; recirculation; and power recovery. Mechanical development studies include: effect of Sphincter seal and lubricant VSR drop time; slug damage; slug bubble tester; P-13 removal; chemical slug stripper; effect of process tube rib spacing and width; ink facility installation; charging and discharging machines; process tube creep; flapper nozzle assembly test; test of single gun barrel assembly; pigtail fixture test; horizontal rod gland seal test; function test of C-pile; and intermediate test of …
Date: October 4, 1951
Creator: Alexander, W. K.
Object Type: Report
System: The UNT Digital Library
History of the project as of February 1, 1951 (open access)

History of the project as of February 1, 1951

In 1946, it was recommended, by the district engineer for the War Department, United States Engineer Office, that it was desirable to transfer all of the functions of production to Hanford, a production installation; thereby relieving the Argonne National Laboratory, a research installation, from production duties. This decision was based on the belief by Argonne National Laboratories that the principal problems of production were solved, as a result of a meeting held at Clinton Laboratories, October 25, 1946, during which, Dr. T.S. Chapman discussed with Major F.A. Valente the possibility of Hanford assuming full production responsibility for the product extracted from the irradiation of Special Request. This responsibility was to include the procurement of lithium fluoride, the preparation and canning of the pellets, the irradiation of the slugs, the extraction of the product and its subsequent shipment to the consumer. This report details historical aspects of this program and the P-10 Project.
Date: January 4, 1952
Creator: Reed, G. G. Jr.
Object Type: Report
System: The UNT Digital Library
The use of aluminum sulfate for 100 Areas' process water coagulation (open access)

The use of aluminum sulfate for 100 Areas' process water coagulation

Increases in power levels of the Hanford Piles have resulted in increased demands for process cooling water to the extent that the present filter plants are now operating at or above their design capacity. Further power level increases requiring even more cooling water may demand the operation of the filters considerably above design capacity. It has been proposed that by the use of aluminum sulfate, or filter alum, as a process water coagulant and activated silica as a coagulation aid, the present filter plant capacities could be increased appreciably. In order to investigate the effects of alum-treated water on pile operation, a full-pile production test was authorized in which alum was substituted for the standard ferric sulfate coagulant. This test was started in the 100-F Area on October 10, 1951. The results of the first thirty days of operation were presented in a previous report and served as a basis of the decision to proceed with installation of the activated silica addition facility. This report presents the data, results and conclusions obtained from the start of the test until its termination of December 28, 1951, when the addition of activated silica began.
Date: January 4, 1952
Creator: Woods, W.C.A.
Object Type: Report
System: The UNT Digital Library
100 Areas monthly report, January 1952 (open access)

100 Areas monthly report, January 1952

This document provides the monthly reports for January 1952 through December 1952. These reports detail activities in the 100 areas during this time period. (FI)
Date: February 4, 1952
Creator: Paulovich, K. F.
Object Type: Report
System: The UNT Digital Library
Construction and Calibration of a Fast Neutron Scintillation Spectrometer (open access)

Construction and Calibration of a Fast Neutron Scintillation Spectrometer

None
Date: April 4, 1952
Creator: Guernsey, G. L.; Mott, G. R.; Nelson, B. K. & Roberts, A.
Object Type: Report
System: The UNT Digital Library
Maching Techniques and Prodicers for Uranium, Graphite, Titanium, Zirconium, Thorium, Tantalum, Beryllium, Bismuth, Lithium, and Stellite (open access)

Maching Techniques and Prodicers for Uranium, Graphite, Titanium, Zirconium, Thorium, Tantalum, Beryllium, Bismuth, Lithium, and Stellite

Techniqnes are presented which are applicable in machining materinls such as U, graphite, Ti, Zr, Th, Ta, Be, Bi, Li, and stellite. Included in the general considerations are factors related to machinability of the materials, operating condition of the machines, and the condition of the cutting tools. In addition, industrial hygtene and safety aspects are examined. The techniques for each material are discussed in detail, the greatest attention being focused on uranium.
Date: November 4, 1952
Creator: Davis, Calvin
Object Type: Report
System: The UNT Digital Library
Evaluation of anodic films on process tube exteriors (open access)

Evaluation of anodic films on process tube exteriors

The investigation reported in this document concerns itself with studies of the mechanism of corrosion on the exterior of process tubes and with studies of the protective qualities of anodic films which might prevent corrosion on the exterior of process tubes. Sections of process tubing coated with Aqua-Dag, a colloidal graphite suspension, were included in these tests for comparison purposes as present operating procedures call for the application of Aqua-Dag to the exterior of process tubes for lubrication purposes during the charging of tubes into the piles.
Date: March 4, 1953
Creator: Dalrymple, R. S.
Object Type: Report
System: The UNT Digital Library