65 Matching Results

Search Results

Results: 1 - 24 next
open access

Quarterly Progress Report Research and Development Activities Fixation of Radioactive Residues: October - December, 1964

Description: Report presenting research and development activities in the field of radioactive wastes. This particular report is concerned with the fixation of radioactive residues when the failure of a pot liner destroyed the furnace.
Date: April 15, 1965
Creator: Platt, A. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Construction Completion Report: CAI-816, 100-N Reactor Plant

Description: Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.
Date: October 15, 1964
Creator: Buckner, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 2, Consequences of a Primary Coolant Leak

Description: Review of previous work is presented in addition to the results of recent studies concerning loss of primary coolant when the system is cold and pressurized and the problem of supplying adequate cooling following the injection of light water.
Date: November 15, 1960
Creator: Wittenbrock, N. G. & Muraoka, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sampling and Analytical Data on Al-Pu Alloy for PRTR Start-Up Tests

Description: In answer to the question, "How well do we know the composition of the fuel material for the PRTR start-up tests?", the analytical data on the PRTR fuel elements and other fuel elements which were fabricated by similar processes was gathered and analyzed. The results of this analysis are presented.
Date: June 15, 1960
Creator: Bloomster, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Water Chemistry for KER Loop 1- June 29, 1959 to December 31, 1959

Description: One of the primary reasons for operating the high pressure KER loops is to obtain information concerning water quality control characteristics for recirculating water cooled reactors. The KER-1 loop is predominantly carbon steel and approximates the water quality conditions specified for the New Production Reactor (NPR).
Date: June 15, 1960
Creator: Demmitt, T. F. & Wood, E. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Problems of a Small Leak Between the Flow Monitor and Heated Section of a PRTR Process Tube

Description: The result of a leak in a PRTR process tube between the flow monitor and the heated section would be to increase the flow through the monitor, but to decrease the flow through the heated section. The concern for the case of small leaks is whether the increase in flow through the flow monitor is sufficient to cause a high flow tip and a reactor scram for the condition where the flow through the heated section is reduced to the point to cause excessive fuel element temperatures.
Date: March 15, 1960
Creator: Hesson, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Unique Fabrication Processes Applied to Fuel Cladding Materials

Description: The fabrication processes applied to nuclear fuels are subject to severe limitations because of the conditions imposed by the reactor environment. The combined problems of neutrons fluxes, high heat fluxes, corrosion by the coolant , and embrittlement by hydriding or similar reactions may be minimized through establishing rigorous materials and fabrication specifications for fuel and cladding.
Date: March 15, 1960
Creator: Bush, S. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Irradiated Rupture Prototype (IRP) Design

Description: One of the problems involved in the design of NPR is the method to be used for decontamination, Considerable effort has been made in both laboratories and pilot plants in developing and evaluating decontamination processes under ideal conditions. Promising processes must be tested under prototypical conditions of velocity, water quality, manner of make-up, type and degree of contamination, addition of decontaminating solutions, and so on.
Date: February 15, 1960
Creator: Neibaur, G. E. & Stice, N. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Ultrasonic Resin Level Detector

Description: This report describes the development of an ultrasonic instrument for resin level measurements in an ion exchange column.
Date: January 15, 1960
Creator: Hunter, D. O. & Pleasance, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Ionium (Thorium-230) for Radioisotope Preparation (Status Report)

Description: For many years effort has been directed toward the development of means for the practical utilization of the heat evolved from the radioactive decay of certain fission and irradiation products. Fission products, in view of their availability in the plentiful, high-level wastes resulting from the processing of irradiated, nuclear reactor fuels have been most intensively studied for applications where their heat of decay might be converted into useful energy such as electricity for the operations… more
Date: December 15, 1959
Creator: Coppinger, E. A. & Rohrmann, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comments on Engineering Review of PRTR by Atomic Power Equipment Department

Description: On a project of the magnitude and complexity of the Plutonium Recycle Test Reactor is was considered prudent engineering practice to obtain an independant design review by a competent off-site group that had not participated in any way in the development of the design. Accordingly, the Atomic Power Equipment Department of the General Electric Company was requested to make such an engineering review, and an Assistance to Hanford contract authorizing this work was approved by the Atomic Energy Co… more
Date: October 15, 1959
Creator: Reactor and Fuels Researcg and Development Operation Hanford Laboratories Operation
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design Criteria for PRTR High Pressure Loop Project CAH-841

Description: The PRTR pressure loop is an experimental facility to be installed in the Plutonium Recycle Test Reactor, Building 309, for use in testing the feasibility of reactor cooling systems utilizing high pressure water or steam as the coolant. It will furnish operating experience with such systems and serve to test fuel elements and components designed to operate in such environments.
Date: October 15, 1959
Creator: Fox, J. C.; Jakub, M. T. & Kelly, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PRTR High Pressure Loop Hazards Survey of Preliminary Scope Design

Description: Conceptual design studies conducted at HAPO indicate that the improved thermal efficiencies which can be obtained in a high pressure, high temperature, nuclear-electric power plant might reduce unit power costs substantially. The Plutonium Recycle Test Reactor (PRTR) is designed primarily to investigate various facets of plutonium recycle operation. In order to increases the usefulness of the PRTR as an experimental tool, it is desirable to include facilities for testing materials and fuel conc… more
Date: October 15, 1959
Creator: Walkup, P. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Division of Reactor Development Programs Monthly Report- August 1959

Description: Sinterability studies on mixtures of UO2 and PuO2 powders have been continued. All of the censities from previous sintering experiments have been recalculated utilizing a somewhat different water immersion technique. Since densities of pellete obtained by physical dimensions are inaccurate due to chipping, and water immersion does not account for the open porosity, the pellets were coated with clear krylon before being immersed in water. This effectively sealed the open pores. Plots of density … more
Date: September 15, 1959
Creator: McEwen, L.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Division of Reactor Development Programs Monthly Reports-June 1959

Description: Basic Studies. Sinterability experiments in the system UO2-PuO2 have continued, and data are available at one hour hold times across the UO2-PuO2 composition limits. Sintered densities appear to be markedly dependent on pressed densities with densification occurring very rapidly at higher pressing pressures. The following table illustrates the effect of one hour at temperature on final density for pure plutonium dioxide pressed to both 40 and 60 percent of theoretical density.
Date: July 15, 1959
Creator: Lewis, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Division of Reactor Development Programs Monthly Report- May 19599

Description: Plutonium Fuels Development Basic studies. Experiments to determine the effect of plutonium dioxide additions on the sinterability of UO2 have continued. PuO2 has been added to ball milled PWR grade UO2 as a physical mixture, and in the form of the mixed crystal oxide.
Date: June 15, 1959
Creator: Lewis, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Division of Reactor Development Programs Monthly Report- March 1959

Description: Basic Studies. It has been reported previously that mixed crystals of PuO2 and UO2 have a higher sintering rate than UO2 alone. However, results to the contrary were obtained on addition to 1/4, 1/2, 1, 2, 5, and 10 w/o PuO2 to PWR grade UO2. Pellets of the above concentrations were heated for one hour in hydrogen at 100 C intervals from 1000 to 1600C.
Date: April 15, 1959
Creator: Hanford Laboratories Operation Fuels Preparation Department, Irradiation Processing Department
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Water Temperatures for the Columbia River Above the Hanford Reactors, September, 1946 Through December, 1958

Description: The ambient temperature of the Columbia River is of interest to the Aquatic Biology Operation since it provides a basis for controlling the temperatures in various experimental tanks which contain Columbia River organisms and since it provides some indication of whether conditions are favorable for the valuable species of fish living in the river. Since the start-up of the plant, temperatures of the river water have been taken in the several water treatment plants.
Date: April 15, 1959
Creator: Foster, R. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Division of Reactor Development Programs Monthly Report - February 1959

Description: Plutonium Oxide Fuels. Mixtures of PWR grade UO2 containing 10, 20, 30, 40, 50, and 60 w/o PuO2 were sintered in hydrogen for 44 hours at 1600 C to get additional data on solubility in this system. Densities of all the pieces were low, approximately 80 percent of theoretical; however, solid solution formation was complete in every case. The low density material should not affect lattice parameter values, but it did slightly reduce the intensity of the reflections.
Date: March 15, 1959
Creator: McEwen, L.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen