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Buildup of Fission Products in Reactor Fuel and Coolant With 'Unclad' Fuel Material

Description: Concentrations of fission products in the fuel and in the coolant stream of a generalized reactor power plant employing unclad fuel material were calculated using actual fission-product chains and wide ranges of assumed values of escape rate from the fuel and removal rate from the coolant stream. The calculations were made on an IBM 704 digital computer. Some typical results are displayed in the form of graphs to illustrate the effects of the variables. As data on escape rates from fuel and rem… more
Date: October 18, 1961
Creator: Cottrell, W. B. & Mann, L. A.
Partner: UNT Libraries Government Documents Department
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RADIOISOTOPE AND RADIATION APPLICATIONS. Quarterly Progress Report

Description: The study of the formation mechanism of free radicals in polymeric materials was continued. Emphasis was placed on an examination of the effect of structural factors on the efficiency of free-radical site formation in acrylate polymers. Site measurements as a function of dose were made for polymethacrylamide and repeated for polymethacrylic acid. The volatile products from the irradiation of polyacrylic acid. polymethacrylic acid, poly-ter- butylmethacrylate. and polycyclohexyl methacrylate wer… more
Date: July 18, 1961
Creator: Sunderman, D.N. ed.
Partner: UNT Libraries Government Documents Department
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PHASE I REPORT OF DEVELOPMENT TECHNIQUES FOR POWER PRODUCTION FROM MIXED FISSION PRODUCTS

Description: An investigation was made into the various processes for the fixation of mixed fission products as solids in order to determine the extent they could be utilized as heat sources for thermoelectric generators. Generators of up to ten watts can be designed and built with state-of-art'' thermoelectric materials and mixed fission products soon to be available from the ldaho Falls calcination pilot plant. Mixed fission products from other processes and plants to be on stream'' in this decade will be… more
Date: February 18, 1961
Creator: Eaton, D.
Partner: UNT Libraries Government Documents Department
open access

Process improvement transition authorization IP-14-I: D Reactor full pile loading of bumper fuel elements

Description: The purpose of this Process Improvement Transition Authorization (PITA) is to authorize full pile loading bumper fuel elements in the fringe zone will be reviewed and, if desirable, recommendations to curtail fringe loading may be made based on economic considerations.
Date: November 18, 1961
Creator: Benson, J. L.
Partner: UNT Libraries Government Documents Department
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Simplified plutonium conversion expression

Description: An accurate, simplified expression relating Pu conversion to exposure, was found which could be substituted for the lengthy subroutine used to calculate conversions in the Process Optimization Program.
Date: January 18, 1961
Creator: Jensen, R. D.
Partner: UNT Libraries Government Documents Department
open access

Radiochemistry for the rupture of a Zircaloy-2 clad thermocoupled fuel element in KER Loop-1 on May 12, 1961

Description: On the 1600--2400 shift, May 12, 1961, the delayed neutron monitor on KER Loop 1 gave a high coolant activity signal indicating a possible fuel element failure in this loop. KE Reactor was shut down immediately thereafter. This report is being written to summarize the events pertinent to the KE Reactor scram and to discuss the results and significance of data from the analyses of coolant samples taken from the KER Loop-1 System.
Date: August 18, 1961
Creator: Perrigo, L. D.
Partner: UNT Libraries Government Documents Department
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GEH-4-63, 64: Proposal for irradiation of production brazed Zircaloy-2 clad fuel elements

Description: A brazed end closure is currently being used on prototypical NPR fuel elements. The production closure will use a braze alloy composed of 5% Be + 95% Zry-2 to braze the Zircaloy-2 cap to the jacket and to the metallic uranium core. A similar MTR test, a GEH-4-57, 58, used a braze alloy of the composition 4% Be + 12% Fe + 84% Zry-2 which melts at a lower temperature. In this previous test, element GEH-4-57 failed through a cladding defect located at the base of the braze heat affected zone. Beca… more
Date: May 18, 1961
Creator: Tverberg, J. C.
Partner: UNT Libraries Government Documents Department
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Engineering bases for power levels and exposures, October 1961--December 1962

Description: It is the purpose of this document to provide assistance to the Manufacturing Section personnel in determining their future operating plans. In general, the inter-relationship of such engineering parameters as projected flow rates, reactor orificing pattern, fuel element performance, and process limits have been considered. Based on these engineering parameters and related process economics, suggested reactor ``Operating Plans`` are graphically presented in this document. It is emphasized that … more
Date: September 18, 1961
Partner: UNT Libraries Government Documents Department
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Reactor Containment Design Study

Description: Introduction: Sargent & Lundy was authorized on November 1, 1960, to make an economic and technical feasibility study of various reactor containment designs which are being utilized for several power plants now under construction.
Date: May 18, 1961
Creator: Johnson, R. A. & Nelson, I.
Partner: UNT Libraries Government Documents Department
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EXCAVATION OF CONTAINED TNT EXPLOSIONS IN TUFF

Description: The effects of two contained H. E. explosions in volcanic tuff were examined by mining directly into the explosion sites. Ore explosion (516 lb of TNT) increased its initial shot chamber volume of about 9 cu ft by a factor of sbout 5 and produced in addition some 126 cu ft of broken rock. Around this explosion, only natural joints in one direction were filled with carbon to a maximum distance of 42 ft, and no new fractures in other directions were developed. The other explosion (973 lb of TNT) … more
Date: April 18, 1961
Creator: Short, N.M.
Partner: UNT Libraries Government Documents Department
open access

The Effect of Temperature on the Yield Strength of the Polycrystalline Hexagonal Ag-Al Intermetallic Phase

Description: The effect of temperature on the yield strength of the polycrystalline hexagonal Ag--Al intermetallic phase was investigated over the temperature range 77 to 775 deg K. It was found that the curve for yield stress vs temperature for both polycrystalline Ag--33 at.% Al specimens that were heavily cold-worked prior to deformation and those that were recrystallized prior to deformation was parallel to that for prismatic slip in single crystals. Increase of the percent Al in the specimens resulted … more
Date: December 18, 1961
Creator: Tanaka, K. & Mote, J. D.
Partner: UNT Libraries Government Documents Department
open access

Chemical Processing Technology Quarterly Progress Report, July-September 1961

Description: The Idaho Chemical Processing Plant did not operate on fuel recovery during the period since numerous repairs and modifications were being made to the extraction and U concentration equipment, Ba/sup 140/ production continued on schedule; substantial decontamination of the RaLa facility was achieved and desirable replacement or repair of in-cell equipment was accomplished in the interval between two successive runs. Aqueous Zr fuel processing studies continued with the obje tive of adapting the… more
Date: December 18, 1961
Creator: Bower, J. R.
Partner: UNT Libraries Government Documents Department
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12" SODIUM FLOW CONTROLLER. PERMANENT MAGNET COUPLING. MAGNETIC CALCULATION MANUFACTURE AND TEST RESULTS

Description: In order to retain the hermetic feature of the sodium flow controller, magnetic flux linkage of a permanent magnet coupling is used to transmit the torque produced by the operator through the pressure wall. Magnetic calculations, manufacture, and testing of this magnet coupling are described. (M.C.G.)
Date: August 18, 1961
Creator: Flator, H.E.
Partner: UNT Libraries Government Documents Department
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Development of Techniques for Power Production From Mixed Fission Products

Description: "An investigation was made into the various processes for the fixation of mixed fission products as solids in order to determine the extent they could be utilized as heat sources for thermoelectric generators. Generators of up to ten watts can be designed and built with state-of-art'' thermoelectric materials and mixed fission products soon to be available from the ldaho Falls calcination pilot plant. Mixed fission products from other processes and plants to be on stream'' in this decade will b… more
Date: February 18, 1961
Creator: Eaton, D.
Partner: UNT Libraries Government Documents Department
open access

THE PREPARATION OF SOME GERMANIUM HYDRIDES

Description: ABS>The preparation of germanium hydrides, by the dropwise addition of al alkaline solution of hydroborate and germanate to aqueous acid, was studied systematically. As much as 70% of the germanium in solution could be converted to germane, Digermane, trigermane, and a polymeric germane were also obtained, and the infrared absorption spectra of gaseous trigermane and of polymeric germane were recorded. (auth)
Date: May 18, 1961
Creator: Drake, J.E.
Partner: UNT Libraries Government Documents Department
open access

Thermodynamic Data for Water

Description: Thermodynamic data for liquid and gaseous water were compiled and extended to limits of pressure and temperature imposed by Hugoniot, adiabat, and Thomas-Fermi model considerations. The internal energy variation is discussed. (auth)
Date: April 18, 1961
Creator: Howard, J. C.
Partner: UNT Libraries Government Documents Department
open access

Radioisotope and Radiation Applications. Quarterly Progress Report

Description: An evaluation was given of the possible hazards to consumers from radioisotope residues in consumer products. A laboratory demonstration was given of the use of Mn/sup 54/ to facilitate removal of manganese from process feed water. lt was found in the hazards evaluation that the "worst case" of radiation exposure from residual radioisotopes in steel gives a radiation exposure somewhat less than the maximum allowable dose levels for occupational exposure. Initial study indicates that for actual … more
Date: January 18, 1961
Creator: Sunderman, D. N.
Partner: UNT Libraries Government Documents Department
open access

Observations on the Response of a Lithium-Drifted Detector Protons

Description: The response of a lithium-drifted solid state detector was measured for protons and found to be linear up to the highest energy observed, 13.2 Mev. The resolution observed for these protons is 0.81% with a bias of 500 volts and 0.65% with a bias of 250 volts. (auth)
Date: April 18, 1961
Creator: Benveniste, J.; Booth, R. & Mitchell, A. C.
Partner: UNT Libraries Government Documents Department
open access

Criteria for Evaluating Hazards Involved in Proposed Tests On and/or Modifications To the SM-1

Description: Abstract: This technical report elucidates principles of hazards evaluation. The concept of hazards potential is introduced and utilized to show how a reactor system perturbation will influence its nuclear safety. Literature relating to reactor safety is referenced to provide the sources of information required for hazards analysis and show how they influence a hazards evaluation. A checklist of items which should be considered in evaluating a change, test, or modification is presented.
Date: October 18, 1961
Creator: Scoles, J. F.
Partner: UNT Libraries Government Documents Department
open access

Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor

Description: Experimental work concerned with the development of an inexpensive composite fuel plate with a high burnup potential for application in a 500°C sodium environment as Core B of the Enrico Fermi Fast Breeder Reactor.
Date: April 18, 1961
Creator: Cherubini, J. H.; Beaver, R. J. & Leitten, C. F., Jr.
Partner: UNT Libraries Government Documents Department
open access

Thermal stability of PBX-9404, LX03 and LX04

Description: In the Hotcake experiments, PBX-9404 was subjected to various temperature spikes from 202 degrees Centigrade to 268 degrees Centigrade to determine conditions which would result in ignition of the explosive. since that time, measurements have been made of decomposition rates of PBX-9404, LX03, LX04, and pure HMX, at temperatures from about 240 degrees Centigrade to 270 degrees Centigrade. These data have been combined to provide a more accurate definition of the thermal stability of high explos… more
Date: September 18, 1961
Creator: Edwards, A. L.
Partner: UNT Libraries Government Documents Department
open access

The Effect of Temperature on the Yield Strength of the Polycrystalline Hexagonal Ag-Al Intermetallic Phase

Description: The effect of temperature on the yield strength of the polycrystalline hexagonal Ag-Al intermetallic phase was investigated over the temperature range 77 to 775 K. It was found that the curve for yield stress vs temperature for both polycrystalline Ag-33 at .% Al specimens that were heavily cold worked prior to deformation and those that were recrystallized prior to deformation was parallel to that for prismatic slip in single crystals.
Date: December 18, 1961
Creator: Tanaka, Kichinosuko & Mote, Jim D.
Partner: UNT Libraries Government Documents Department
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