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Fission Product Release from UO2 and by High Temperature Diffusion and Melting in Helium and Air.

Description: The experimental demonstration of fission product release from over heated reactor fuel is necessarily subject in many respects to the arbitrary conditions imposed by the experimenter. Since an almost infinite latitude exists in the choice of materials, atmospheres, gas, velocities, temperatures etc., some allowance for an extrapolation to alternate conditions is definitely in order. The conditions imposed in this study are best described as those most likely to maximize fission product release… more
Date: February 8, 1961
Creator: Parker, G. W.; Creek, G. E. & Martin, W. J.
Partner: UNT Libraries Government Documents Department
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Comparison of Radiation-Induced Graft Copolymerization Untilizing Electron Accelerators and Isotope Sources as Radiation Initiators

Description: "Graft polymers were made by Co60 mutual irradiation of mixtures of styrene and methyl acrylate in contact Teflon. These graft copolymers were analyzed by infra-red absorption and their composition determined. The composition of the graft copolymer formed from styrene and methyl acrylate was different from that which is predicted by the copolymer composition equation."
Date: May 8, 1961
Partner: UNT Libraries Government Documents Department
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The Influence of Isotopic Composition on the Maximum in the Cosmic Ray Energy Spectra

Description: "The previously found maximum in the cosmic radiation energy spectrum is discussed, and the possibility that it arises in part from a misinterpretation of the data due to oversimplifying assumptions about the composition of the beam is examined. The importance that lack of recognition of isotopic composition may have is pointed out, and it is clear that this importance is strongly dependent on the measurements made and on the cut-off rigidity."
Date: May 8, 1961
Creator: Appa Rao, M.V.K. &
Partner: UNT Libraries Government Documents Department
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Preliminary Design of a 10-Mw(t) Pebble-Bed Reactor Experiment

Description: The objectives of this study have been to examine the problems of the pebble-bed reactor concept and to conceive a design of a facility for investigating the feasibility of this type of reactor. The design must provide for adequate leaktightness of the contaminated-gas system and adequate maintenance of contaminated components, the most vital feasibility questions of the concept.
Date: May 8, 1961
Creator: Fraas, A. P.; Carlsmith, R. S. & Corum, J. M.
Partner: UNT Libraries Government Documents Department
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Recommended high-tank temperatures for maintenance of high-tank backup support. Revision 1

Description: This document consists of information about the cooling systems of Hanford Production Reactors. It is the purpose of this letter, written May 8, 1961, to update recommendations of high-tank temperatures required to insure acceptable high-tank backup support. It does not appear practicable to relate the somewhat arbitrary standards of reference for backup support to process operating limits, i.e., reactor power levels, particularly as a mandatory requirement. For this reason, we have chosen at t… more
Date: May 8, 1961
Creator: Greager, O. H.
Partner: UNT Libraries Government Documents Department
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Ultrasonic and resistance welding of ZR supports to ZR fuel element cladding

Description: Tube-tube type fuel elements require support devices to maintain concentricity both between the element components and between element and process tube. A variety of support devices have been conceived. all require welding of a tab or other attachment device to the Zircaloy clad. Ultrasonic and resistance welding were evaluated for this application. Investigation showed ultrasonic welding to be not acceptable in its present state. Resistance welding proved satisfactory. This paper will briefly … more
Date: August 8, 1961
Creator: Steinkamp, W. I.
Partner: UNT Libraries Government Documents Department
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Hazards Evaluation of the SM-1 Penetrated Gasket

Description: Abstract: This technical report describes the as-constructed SM-1 penetrated gasket designed for SM-1 Core and Flow Instrumentation (Task XIV). This report supplements APAE No. 79, The Summary Hazards Report for Task XIV, and evaluates the effects of a postulated failure of this gasket. The effects of failure on the Maximum Credible Accident are determined and conclusions and recommendations for the use of this gasket are made.
Date: September 8, 1961
Creator: Coombe, J. R.; Gebhardt, F. G. & James, B.
Partner: UNT Libraries Government Documents Department
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International Practical Temperature Scale of 1948: Text Revision of 1960

Description: Report is a text revision of the International Temperature Scale of 1948; the numerical values of temperatures remain the same. The adjective "Practical" was added to the name by the International Committee on Weights and Measures. The scale continues to be based upon six fixed and reproducible equilibrium temperatures to which values have been assigned, and upon the same interpolation formulas relating temperatures to the indications of specified measuring instruments. Some changes have been m… more
Date: September 8, 1961
Creator: Stimson, H. F.
Partner: UNT Libraries Government Documents Department
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Steady State and Transient Thermal and Hydraulic Analysis of SM-2 Termination Report

Description: Abstract: Thermal characteristics of the SM-2 core were analyzed at steady state and loss of flow conditions. For steady state operation, the steady state code STDY-3 was used. For transients during a loss of flow accident, ART-02, a one-dimensional code, was used. This analysis indicates the SM-2 core is safe from burnout under steady state operation at design power level (28 tMW) because (1) no nucleate boiling exists, and (2) the minimum burnout ratio is above 2.0. The core is safe from burn… more
Date: September 8, 1961
Creator: Segalman, I. & Bradley, P. L.
Partner: UNT Libraries Government Documents Department
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The Synthetic Liquid Fuel Potential of Louisiana

Description: Report documenting the suitability of Louisiana for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.
Date: October 8, 1961
Creator: Ford, Bacon, and Davis
Partner: UNT Libraries Government Documents Department
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Processing data for coextruded fuel elements in ETR, KER and MTR Loops

Description: The following data represents processing conditions used in fabricating prototypic (except for supports) natural and enriched NPR element assemblies and K-type I&E{sup 2} for the following production tests: ETR, 6{times}6 Loop; GEH-10, Nos. 52, 53, 54 and 55; KER Loops; PT-377; MTR Loop; GEH-4, Nos. 68, 69 and 70. The purpose in documenting the data is to provide a permanent record of processing conditions and dimensions which may be referred to for post irradiation analysis and possible future… more
Date: November 8, 1961
Creator: Robinson, R. K.
Partner: UNT Libraries Government Documents Department
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