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Annual Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968

Description: Annual report with the objectives of evaluating, producing, and maintaining an up-to-date set of basic nuclear data; producing and evaluating multigroup constants; and improving of present day methods of neutronic calculations as related to microscopic and macroscopic nuclear data, for unclassified research sponsored by the U.S. Atomic Energy Commission during FY 1968.
Date: May 24, 1969
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Chemical Development, Quarterly Progress Report, October-December 1953.

Description: Introduction - The work of the Chemical Development Group has included studies on the thermal and radiation stability of organic materials suitable for reactor coolants, the thermal and radiation stability of zirconium hydride, reactor safety devices involving chemical systems, and general analytical development.
Date: June 15, 1954
Creator: Loftness, R. L.
open access

The Chemical Effects of 1 Mev Electrons on BrF3 at 25 degrees C

Description: "An investigation of the chemical effects of 1-Mev electrons on BrF3 at 25 degrees C has been carried out. Pressure measurements taken during the irradiation suggest the presence of Br2 and BrF5 as decomposition products and a fractional distillation of the irradiated liquid confirmed their presence. The extent of decomposition was determined both by fraction distillation and spectrophotometric methods. The radiation effect seemed to reach saturation when approximately 10 per cent of the BrF3… more
Date: October 1, 1954
Creator: Yosim, S. J.
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The Distribution of Tracer Plutonium and Fission Products Between Molten Uranium and Solid Uranium Oxide, Carbide, and Nitride

Description: "A study has been made of the distribution of tracer fission products and plutonium between small samples of molten uranium and solid uranium oxide, carbine, and nitride. The distribution showed the same behavior i general for all three materials: 1. The rare earth elements, Cs, Ba, and Sr were extracted primarily into the solid scrub phase. 2. Zirconium and Nb partially concentrated in the scrub phase. 3. Plutonium, Mo, and Ru tended to remain completely in the metal phase. The distribution… more
Date: September 15, 1954
Creator: Keneshea, F. J.; Saul, A. M. & Young, C. Y.
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Effect of Reactor Irradiation on the Thermal Conductivity of Uranium Impregnated Graphite at Elevated Temperatures

Description: "An experiment to determine the effect of reactor irradiation on the thermal conductivity of uranium-impregnated graphite at elevated temperatures as described. The results show a decrease in the thermal conductivity saturating at [approximately] 60 percent at a temperature of 700 degrees C; at [approximately] 50 percent at a temperature of 1000 degrees C; and at [approximately] 25 percent at a temperature of 1300 degrees C. It was found that after irradiation at a given temperature, exposure… more
Date: April 29, 1954
Creator: Durand, Richard E.; Klein, David J. & Nykiel, Harry H.
open access

Final Safeguards Summary Report for the Piqua Nuclear Power Facility

Description: Summary: This report contains a description of the final design of the Piqua Nuclear Power Facility (PNPF); an outline of the test and operating procedures, and the organization and responsibilities; and a summary of the hazards and safeguards analyses that have been conducted to evaluate the safety of the facility operations.
Date: August 1, 1961
open access

Heat Generation in Thermal Shields

Description: "Heat production resulting from the absorption of gamma ray photons in thermal shields and the leakage of neutrons and photons from ferritic thermal shields are investigated. The gamma rays considered arise from three types of reactor radiation -- thermal neutrons, fast neutrons, and core and reflector gammas. The energy spectra of the fast neutron leakage and absorption have been investigated in some detail because of the significant contribution of fast neutrons to the heating of the concre… more
Date: August 15, 1954
Creator: Heisler, M. & Wetch, J.
open access

Improved Method for Numerically Solving Multi-Group Reactor Equations

Description: "A method for solving multi-group reactor equations which arise in the diffusion approximation is outlined. Considerable work has been done on this problem at KAPL and ORNL. Their approach is to replace the differential equations by difference equations. Complications arise in this method where more than one slowing down medium is present since the fluxes are discontinuous at the interfaces. The primary purpose of this article is to develop an exact integral expression for the neutron flux w… more
Date: September 15, 1954
Creator: Lehman, G. W.
open access

A Pebble-Bed Reactor for Stationary Power Plants

Description: A preliminary study has been made of a solid homogeneous reactor for stationary power plant application. The core consists of graphite spheres impregnated with uranium and thorium, and the coolant is bismuth. This concept possible offers advantages over other solid fuel reactor systems with respect to simplification of core structure, fuel fabrication and fuel handling, and reduction of fuel inventory external to the reactor. From the results of this preliminary study, it appears that the pot… more
Date: May 15, 1954
Creator: Beeley, R. J.
open access

Preparation of a Thorium Slurry

Description: "A study has been made of methods to prepare a fluid containing 1 gram of thorium per milliliter. The methods considered were solutions of thorium salts, suspensions of dry solids in water, and collodial suspensions. Thorium oxide, oxalate, and fluoride were tried in conjunction with one or more surface actants, but it was not possible to attain the required thorium concentration. Thorium hydrosol, produced by peptization of thorium hydroxide and subsequent electrodialysis, gave the necessary… more
Date: April 1, 1954
Creator: Silverman, L. & Trego, K.
open access

Proton Irradiation Effects in Thorium

Description: "Iodide-processed thorium foils were irradiated with 9-Mev protons at temperatures below -140 degrees C. the recover of electrical resistance upon annealing was studied in the range 0 degrees to 75 degrees where tempering curves showed rapid changes taking place. Determinations of the activation energy associated with this process were made and the mean value obtained was 1.22 ev. Correlations of this result have been made with those found previously for copper. From these comparisons, a tenta… more
Date: December 15, 1954
Creator: Meechan, Charles J.
open access

Quarterly Technical Progress Report, AEC Unclassified Programs: Fiscal Year 1968

Description: Quarterly report with the objectives of evaluating, producing, and maintaining of an up-to-dat set of basic nuclear data; producing and evaluating of multigroup constants; and the improvement of present day methods of neutronic calculations as relates to microscopic and macroscopic nuclear data, for unclassified research sponsored by the U.S. Atomic Energy Commission during FY 1968.
Date: May 24, 1969
open access

Reactor Physics, Quarterly Progress Report, August-October, 1953

Description: "A thorough analysis of the data obtained on depleted, natural, and enriched uranium lattices has been made. Consideration of the possible sources of discrepancies between theory and experiment has led to a suspicion of the calculated thermal neutron diffusion lengths. A series of diffusion length measurements in non-multiplying lattices of lead-cadmium alloy has been initiated. An analysis of some early exponential experiments on lattices proposed for a neutron production reactor has been ca… more
Date: December 10, 1953
Creator: Laubenstein, R. A.
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