Search Results

open access

The Quantitative Recovery of Plutonium From Laboratory Residues

Description: Report discussing the procedures and experimental data of various plutonium waste recovery methods. The report elaborates on the different methods of collection necessary for different wastes.
Date: March 18, 1953
Creator: Ferguson, W. S.
Partner: UNT Libraries Government Documents Department
open access

High-Speed Saw Tests Power Reactor Fuels Reprocessing Development

Description: The basic scheme for processing power reactor fuels at Hanford includes the removal of inert endfittings ("hardware") from the active sections of the fuels. Within Hanford Laboratories, research and development studies have been in progress on various types of saws which might be used for hardware cutoff. In the initial phase of the program, high-speed saws were investigated; more recently, studies on low speed saws have been conducted. This report summarizes the high speed saw studies and incl… more
Date: November 18, 1959
Creator: Kelly, V. P.
Partner: UNT Libraries Government Documents Department
open access

The Separation of Cerium from the Trivalent Rare Earths Using Hydrogen Peroxide and Sodium Acetate

Description: At the present time, cerium-144 and premtheium-147 are the two fission product rare earths that appear most promising for use as the heat source in isotopic power units. Under proper conditions, cerium and the trivalent rare earths can be extracted from the Purex fission product waste stream as an insoluble sodium-rare earth double sulfate. A reprecipitation as the double sulfate, dissolution of the hydroxide, serves to give almost complete separation from the corrosion products, inert constitu… more
Date: May 18, 1960
Creator: Wheelwright, E. J. & Howard, N. C.
Partner: UNT Libraries Government Documents Department
open access

Filtering Abrasive-Wheel Uranium Cuttings

Description: Extremely radioactive particles result from the abrasive wheel cutting of irradiated fuel elements in the cut-off cell located in the 327 Building. Due to the use of water during the cutting operation these particles are in suspension and must be removed before the liquid can be discharged to the liquid waste tanks in the 340 building. The filters presently employed in the cell total activity discharged to the 340 Building tanks is attributed to the particles which pass these filters. With the … more
Date: September 18, 1959
Creator: Postma, A. K. & McCorrmack, J. D.
Partner: UNT Libraries Government Documents Department
open access

Design Criteria for PRP- Critical Facility Project CAH-842

Description: The PRP Critical Facility is an experimental reactor for use in determination of basic nuclear constants of heterogenous reactors recycling plutonium, and exponential and criticality studies at power levels up to 100 watts and neutron fluxes of about 109 nv. Provision is made for changing reactor lattices using irradiated and unirradiated fuel elements with either a light or heavy water moderator.
Date: December 18, 1959
Creator: Nelson, H. K. & O'Neill, G. L.
Partner: UNT Libraries Government Documents Department
open access

Final Report: Production Test No 105-505-SI. Exposure of Two Different Types of Rubber to Pile Water

Description: In connection with different seals for C & D equipment it appears advantageous that many parts could be made of rubber or other elastic polymers. However, data on the deterioration rate of these materials under irradiation are somewhat scant in the available literature. It appears that for neutrons and pure gamma radiation that a good grade of natural rubber stands up best in all the test reported and because the results of the neutron irradiation are so closely correlated with results from g… more
Date: November 18, 1953
Creator: Cooke, J. P.
Partner: UNT Libraries Government Documents Department
open access

Fuel Core Tester - UT-2

Description: Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Date: July 18, 1960
Creator: Frederick, C. L. & Waldkoetter, G. L.
Partner: UNT Libraries Government Documents Department
open access

Effects of In-Reactor test Loops on PRTR Operation and Program

Description: Recently proposals for justifiable additions to the Plutonium Recycle Test Reactor Complex were presented to the Atomic Energy Commission at their request. In addition to a critical reactivity measuring facility in the fuel element storage basin, the following in-reactor loops were proposed: 1. A high pressure, H2O cooled fuel test loop. 2. A rupture loop to investigate fuel element failures. 3. One or more materials testing loops.
Date: March 18, 1959
Creator: Peterson, R. E.
Partner: UNT Libraries Government Documents Department
open access

Precision Duplication of Metal Parts in Tooling Plastic

Description: A series of experiments has been conducted during the past eighteen months with the objective of degerming the accuracy with which precision parts can be duplicated using a castable tooling plastic as a test shape to be reproduced. A precision ground ground 1/4 inch-thick, 90° steel sector of 4'' radius was chosen. The plastics used in the experiments were the die surfacer mixes of the Devon Cooperation and Ren Plastics, Inc. These were selected for use in the test because of their dimensional … more
Date: August 18, 1959
Creator: Kleinpeter, J. H.
Partner: UNT Libraries Government Documents Department
open access

Once Through Decontamination Studies- Interim Report No. 2

Description: The decontamination of the present Hanford reactors involves a once-through cleaning operation. Considerable interest has been shown in determining the feasibility of this once-through technique for cleanup of certain portions of the NPR system. This is the second interim report of a series that covers tests performed in the 242-B Single Pass Flow Facility. The first was distributed in January, 1960.
Date: February 18, 1960
Creator: Hokenson, J. F. & Perrigo, L. D.
Partner: UNT Libraries Government Documents Department
open access

Equations of State for Stream-Water Mixtures and Some Representative Applications Analysis

Description: The majority of two-phase flow problems involving equations of state are solved by use of point-wise utilization steam table values. In this manner, problems involving the use of the various flow equations of continuity, momentum and energy are generally forced into iterative solutions. Considerable effort towards the development of an analytical expression for the state equation seems indicated so as to simplify the analysis of two-phase problems, particularly the transient cases. The question… more
Date: April 18, 1960
Creator: Love, W. J.
Partner: UNT Libraries Government Documents Department
open access

Technical Investigation of Autoclave Failure

Description: On July 31, 1959, an autoclave ruptured while being used for thermal cycling studies of Plutonium Recycle Test Reactor (PRTR) plutonium-aluminum fuel elements. Since stand-in materials were being used in this test, no contamination was involved. This accident could lead to inference of greater hazards associated with PRTR fuel designs than had previously been postulated. An ad hoc technical investigation committee was appointed by the Manager Reactor and Fuels Research and Development, to stud… more
Date: November 18, 1959
Creator: Wittenbrock, N. G.; Freshley, M. D.; Griggs, B. & Wheeler, R. G.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen