Metallurgical Evaluation of the Uranium Rods Rolled for the Chalk River Pile Test (open access)

Metallurgical Evaluation of the Uranium Rods Rolled for the Chalk River Pile Test

Summary: "The laboratory data collected during the metallurgical evaluation of these rods indicate that lower rolling temperatures increased the ultimate and yield strength, the amount of cold work, and the degree of preferred orientation existing in these uranium rods."
Date: September 11, 1952
Creator: Sanderson, M. J. & Hueschen, R. E.
System: The UNT Digital Library
Criticality Conditions for 1.75 Per Cent Enriched Uranium Slugs (open access)

Criticality Conditions for 1.75 Per Cent Enriched Uranium Slugs

Abstract: "A batch of slugs is being prepared for which the U-235 content will be 1.75 per cent, and it is of interest to calculate the minimum number of such slugs required for a critical assembly in water. Using Handbook (CL-697) methods, a critical assembly of these slugs arranged in a lattice with a spacing of 5.5 cm."
Date: September 11, 1952
Creator: Erkman, John O.
System: The UNT Digital Library
Use of the Boiler Neutron Source for Exponential Experiments (open access)

Use of the Boiler Neutron Source for Exponential Experiments

The following report deals with the application of the water boiler neutron source to the exponential experiments in an attempt to speed up lattice testing measurements.
Date: December 11, 1952
Creator: Davenport, D. E.
System: The UNT Digital Library
Results of Critical Mass Studies for Hanford at K-25 (open access)

Results of Critical Mass Studies for Hanford at K-25

Report presenting results of a study regarding the critical masses and nuclear properties of plutonium as well as the use and effects of various tampers.
Date: October 11, 1950
Creator: Gast, Paul F.
System: The UNT Digital Library
Alternating Current and Square-Wave Polarography (open access)

Alternating Current and Square-Wave Polarography

A exploratory study was made of a polarographic technique in which an alternating sine or square-wave potential is superimposed upon the applied d.c. potential of the polarographic scan. Recording of the a.c. component of the polarographic current results in derivative-type waves. It was shown that the technique yields greater sensitivity and greater selectivity than normal polarographic technique.
Date: September 11, 1956
Creator: Hamm, Randall E.
System: The UNT Digital Library
Reduction of Air Borne Contamination UO₃ Plant (open access)

Reduction of Air Borne Contamination UO₃ Plant

Gradual corrosion and mechanical wear of equipment over a period of years has affected the seals and gasketing of the electric pot calcining equipment in the 224-U Building Cell E to such an extent that the desirable vacuum cannot be maintained in the pots. Air contamination has been gradually increasing, and this, together with a lowering of the mask working limits, has made it necessary to require personnel to wear assault masks continuously. Indications are that, with the increased production now required, the level of air contamination will continue to rise unless measures are taken to prevent it. The Manufacturing Department has requested that a project be established to reduce the contamination level. Several items of improvement are listed for consideration including, in general, the electric pot agitation and sealing, semi-automatic pot unloaders, cell ventilation and air locks, and the nitric acid off-gas system and stacks. Because of the urgency of improving the conditions, the project, at first, is to provide for immediate improvements for the electrical pot agitation, the pot cover leakage, and the nitric acid off-gas system and stack. Additional study will be required to determine the extent of the ventilation and semi-automatic unloading improvements required.
Date: May 11, 1956
Creator: Ingalls, W. P. & Sanborn, K. L.
System: The UNT Digital Library
Radiological Sciences Department Quarterly Progress Report Research and Development Activities October-December, 1955 (open access)

Radiological Sciences Department Quarterly Progress Report Research and Development Activities October-December, 1955

This twenty-fifth quarterly report of the research and development activities of the Radiological Sciences Department, Hanford Atomic Products operation, as before, includes some items charged to control but included for general interest. The previous report of this series was numbered: HW-39624, October 11, 1955. Progress is reported in the following studies: a radiobiological-ecological survey of the Columbia River; the toxic effects of continuous low-level exposure to I¹³¹ in pigs; Pu metabolism in miniature pigs and rats; the tissue distribution and retention of Ru¹⁰⁶ and Cs in rats and mice; the radiosensitivity of the intestine of rats; the pulmonary absorption of radioactive particles and the pathological effects of such particles in the lungs of mice; the uptake of I¹³¹ and other fission products from the soil and from air by plants; determinations of the relative biological effectiveness for yeast cells of Po²¹⁰ alpha particles and P³² beta particles; the development of chemical and radiological monitoring methods; the separation of fission products from waste streams; and improvements in instruments for monitoring and low-level radiation counting. The status of the research programs of the department is reviewed.
Date: January 11, 1956
Creator: Parker, H. M.
System: The UNT Digital Library
Backmixing in Pulse Columns II, Experimental Values and Effect of Several Variables (open access)

Backmixing in Pulse Columns II, Experimental Values and Effect of Several Variables

Seven runs were made with the system Penn. Ref. Co. "Supersol" (dispersed) water (continuous) to investigate the effects of pulse frequency, amplitude plate spacing, volume flow ratio, and throughput on backmixing, using the technique of continuous injection of a tracer solution into the packed section. Backmixing was found to be surprisingly insensitive to all the above variables over the range studied with the exception of pulse amplitude and continuous phase flow rate, showing greatest dependence on the later. Backmixing increased with decreasing continuous phase flow rate and increased with pulse amplitude.
Date: August 11, 1953
Creator: Swift, W. H. (Ward Henry), d 1929- & Burger, L. L.
System: The UNT Digital Library
The Resistance of Various Bearing Materials to Chemical Attack by Nitric Acid and Uranyl Nitrate Hexahydrate (open access)

The Resistance of Various Bearing Materials to Chemical Attack by Nitric Acid and Uranyl Nitrate Hexahydrate

The purpose of this study has been to evaluate the chemical resistance of various bearing materials to solutions of nitric acid and uranyl nitrate hexahydrate with views toward selecting the best material to be used as bearings in Purex submerged rotating equipment.
Date: March 11, 1954
Creator: Groves, Norman D.
System: The UNT Digital Library
An Electrical Technique for Ground Water Velocity Measurement (open access)

An Electrical Technique for Ground Water Velocity Measurement

An electrical conductivity technique was developed to determine the dilution-displacement rate of an electrolyte in a well from which data the velocity of the water through the well can be calculated. The electrical current flow between two of the electrodes in a well drops proportionately with the dilution and the displacement of the electrolyte by fresh water entering the well. The drop of electrical current flow over a period of time was applied to a derived equation to obtain a value for ground water velocity. The technique gives results comparable to other methods and some problems of the standard methods of measuring ground water velocity are eliminated. However, a correction factor for porosity of the aquifier must be used in the derived equation. Porosity values are not adequately known in most cases, therefore the ground water velocity figures are generally relative rather than absolute.
Date: April 11, 1955
Creator: Raymond, J. R.
System: The UNT Digital Library
Moderator Evaluation for the K Piles - AGHT (CHF) and 185 W Graphite (open access)

Moderator Evaluation for the K Piles - AGHT (CHF) and 185 W Graphite

This report describes the evaluation of physical properties of AGHT and 185-W graphites that are important to pile construction and operation. On the basis of these data, purified AGHT graphite was allocated to either filler block positions in the central regions of the K piles or to the upper or lower reflectors. This decision was based on the similarities of physical properties between AGHT graphite and the other moderator components. A similar allocation could be made for 185-W graphite for some future pile if it can be successfully purified or if purification is not required.
Date: May 11, 1955
Creator: Sparks, G. R. & Riley, W. C.
System: The UNT Digital Library
The Effect of Temperature on the Neutron Attenuation of Magnetite Concrete (open access)

The Effect of Temperature on the Neutron Attenuation of Magnetite Concrete

Comparison of experimentally determined relaxation lengths to the value calculated from the concrete composition.
Date: December 11, 1958
Creator: Wood, D. E.
System: The UNT Digital Library
Conversion of Mica-Window G-M Tube Lead-Pig Counters to Scintillation Detection (open access)

Conversion of Mica-Window G-M Tube Lead-Pig Counters to Scintillation Detection

Because of the excessive vertical fragility and high replacement costs of mice-window G-M tubes used in vertical and horizontal lead-pig shelf counters, it was requested that a simple system of conversions to reliable scintillation detection be accomplished.
Date: May 11, 1959
Creator: Spear, W. G. & Crouch, G. D.
System: The UNT Digital Library
Examination of Zirconium Exposed to 190 MWD/AT (open access)

Examination of Zirconium Exposed to 190 MWD/AT

A production test composed of preformed zirconium samples was prepared by R. S. Kemper of the Physical Metallurgy Unit⁽¹⁾ to determine the effect of exposure time and the influence of prior mechanical cold work on changes occuring [sic.] during irradiation. The first section was delivered to Radiometallurgy Unit is April, 1954, for examination after an exposure of 190 MWD/AT.
Date: February 11, 1955
Creator: Kelly, W. S.
System: The UNT Digital Library
In-link Alpha Monitor Prototype Performance (open access)

In-link Alpha Monitor Prototype Performance

This report summarizes the operational experience and the data obtained on the 2AW Purex type process stream. The performance of an in-line alpha monitor for continuously monitoring Plutonium in Purex Process waste streams is described. The instrument has a lower limit of measurement of 1 x 10⁻⁶ grams of Plutonium per liter and can measure concentrations as high as 7.9 x 10⁻² grams/liter.
Date: October 11, 1955
Creator: Hildreth, N. T.
System: The UNT Digital Library
Purex Pulse Generator Operation (open access)

Purex Pulse Generator Operation

A large (size 2) Purex pulse generator was installed in the 321 Building Tan Farm to pulse solutions in the prototype Purex HA Column. Flow sheet considerations indicated a need for information on leakage rates with various size weep holes in the pulse generator piston. In addition to leakage tests, experiments were conducted to determine the air required under the piston to hold the column contents away from the pulse generator piston thereby preventing leakage during shut down and the determine the time required to bleed the air trapped in the pulse leg when the column is first filled. [...] Leakage past the piston was not appreciably affected by pulse frequency. [..] Bleeding the air out of the pulse leg under start-up conditions, even with the piston weep hole plugged, was rapid. The longest time required to bleed the pulse leg was 36 minutes, which included a column-filling time of 30 minutes.
Date: May 11, 1955
Creator: McCarthy, P. B.
System: The UNT Digital Library
Radiological Sciences Department Quarterly Progress Report Research and Development Activities April - June, 1955 (open access)

Radiological Sciences Department Quarterly Progress Report Research and Development Activities April - June, 1955

This report constitutes the Quarterly Progress Report covering April-June 1955, for the Health Instruments Division research and development activities. Most of the studies described concern the biological fate, environmental transport of radioactive effluents, or development of instrumentation for radiation detection.
Date: July 11, 1955
Creator: Parker, H. M.
System: The UNT Digital Library
Mechanization of Nondestructive Tests (open access)

Mechanization of Nondestructive Tests

The objective of this report is to set forth the design of automatic mechanical equipment developed for use with HAPO nondestructive test instruments.
Date: April 11, 1955
Creator: Quinian, F. B.
System: The UNT Digital Library
The Nuclear Safety of Fissile Materials (open access)

The Nuclear Safety of Fissile Materials

Whenever fissile materials are handled in significant quantities such as in fuel element fabrication, separation processes, or in exponential and/or critical experiments a potential criticality hazard exists. The usual procedure which is followed by those persons conducting critical mass experiments is to either place the potential reactor in a heavily shielded cell or to conduct the experiments remotely in which case distance provides a measure of safety in the event of an unscheduled radiation outburst. In considering potential critically incidents, especially for the personnel not specifically engaged in critical mass studies, it is very likely that at the time of the incident neither the conditions of shielding nor distance will prevail for the personnel involved.
Date: 1959-02-11?
Creator: Clayton, E.D.
System: The UNT Digital Library
Investigation of the Causes of Weld Rejects (open access)

Investigation of the Causes of Weld Rejects

Weld rejects have accounted for a large percent of the total rejects in the production of fuel elements, and consequently, the investigation of the causes of these rejects was a desirable undertaking. Although previous investigations had made possible a satisfactory standardization of the welding process, it was felt of value to more sharply define the causes of weld rejects and to facilitate the control of these causes.
Date: October 11, 1955
Creator: Otterbein, G. L.
System: The UNT Digital Library
Cofit - A 709 Program for Determining Extrapolation Length from Horizontal Traverse Data (open access)

Cofit - A 709 Program for Determining Extrapolation Length from Horizontal Traverse Data

A program has been prepared for the 709 computer which will determine extrapolation length from horizontal traverses measurements taken in an exponential pile. The flux across the pile is assured to fit a cosine function of the form y = A cos B (X-C)
Date: August 11, 1959
Creator: Matsumoto, D. D.
System: The UNT Digital Library
Development of a Welding Process for Spire-Can Fuel Elements (open access)

Development of a Welding Process for Spire-Can Fuel Elements

The components for the present aluminum clad, Al-Si bonded, internally and externally cooled (I & E), uranium fuel elements are composed of impact extruded cans and spire caps as shown in Figure 1. This type of component requires two impact extrusions; however, in December, 1957, J. E. Ruffin proposed another design of component in which there was only one impact extrusion. For this component, Figure 2, the spire was impact extruded as a part of the can.
Date: March 11, 1960
Creator: Hanson, G. R.
System: The UNT Digital Library
Zircaloy Process Tube Monitoring (open access)

Zircaloy Process Tube Monitoring

The large scale application of Zircaloy-2 pressure tubes for structural use either in or out of reactor service, is without precedent. For more common materials, there normally are adequate data and long operating histories on which to base design and service limits. In the absence of such information for Zr-2, several investigative programs have been devised to provide much of the information from which design and service limits may be defined for Zr-2 pressure tubes. These investigations encompass in-and-out-of-reactor creep and stress-rupture testing, pre-and-post irradiation testing, and bust strength, as well as the effect of flaws or defects (from both fabrication and service origins) on burst strength and fracture characteristics. Already creep and stress rupture testing of unirradiated Zircaloy-2 is well advanced, and some experimental pre-irradiation burst testing has been carried out and will be extended rapidly as improved equipment becomes available. One irradiated KER tube sample has been burst tested and the requirement for post irradiation burst testing equipment have been defined.
Date: April 11, 1960
Creator: Pankaskie, P. J.
System: The UNT Digital Library
Corrosion of Type 202 Stainless Steel in High Temperature Water (open access)

Corrosion of Type 202 Stainless Steel in High Temperature Water

The chromium-nickel-manganese alloys are a group of austenitic stainless steels which were developed during the Korean War to conserve nickel. These alloys are very similar to their corresponding 300 Series grades in mechanical, physical and corrosion properties. A portion of the nickel in the 300 Series grades has been replaced by approximately 2% manganese for each percent of nickel replaced. Two compositions, AISI 201 and AISI 202, are recognized as standard grades. Two other compositions, AISI 204 and AISI 204-L, have been produced in limited quantities to replace AISI 304 and AISI 304-L. Experience with the 200 Series steels indication they are every bit as good as the grades for which they were once alternates. In some shapes, such as rod and sheet, the cost per pound is considerably lower than the corresponding 300 Series grades.
Date: December 11, 1959
Creator: Larrick, A. P.
System: The UNT Digital Library