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Engineering Test Reactor Critical Facility Control System Manual

Description: This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).
Date: June 23, 1961
Creator: Meichle, F. A.
Partner: UNT Libraries Government Documents Department
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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients

Description: Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps

Description: Fourth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept

Description: Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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Extruded Ceramic Nuclear Fuel Development Program. Final Report

Description: Urania rods 6-in. long and 0.475-in. in diameter were extruded and sintered to densities exceeding 94% of the theoratical urania density. The rods dropped freely through a straight metal tube 8-in. long with an internal diameter 0.004-in. greater than the diameter of the rods. All properties of the extruded and sintered rods relevant to their use as a nuclear fuel material were at least equal to the corresponding properties of pressed and sintered urania pellets. Extruded and sintered urania rods can be produced with standard ceramic-industry machinery. From preliminary estimates it appears that extrusions may be produced more cheaply than pellets. (auth)
Date: January 23, 1961
Partner: UNT Libraries Government Documents Department
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Activity Build-Up Control by High pH Coolant. A Literature Survey

Description: A survey was made of unclassified literature dealing with the control of activity build-up in pressurized water reactors by high-pH coolants. Survey results indicate that a high-pH coolant is desirable for control of induced radioactivity build-up in pressurized water reactors containing significant amounts of stainless steel and that no significant hazards are introduced by adoption of a high-pH coolant. Lithium hydroxide was found to be the most acceptable agent for coolant pH control. Strong-base-form mixed-bed resin is effective in maintaining both coolant pH and coolant purity. (auth)
Date: January 23, 1961
Creator: Bergen, C. R.
Partner: UNT Libraries Government Documents Department
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The Zirflex Decladding of Tube-in-Tube Type Fuel Elements

Description: Pilot unit Zirflex dissolutions were carried out on near prototypical tube-in-tube type elements clad in oxidized Zircaloy. The runs were made with the elements horizontal and at simulated large scale operating conditions. No significant difference was noted between the actual decladding achieved in these experiments and that which was predicted from prior studies on similarly oxidized elements with somewhat different geometries. No gas blanketing nor diffusion effects were observed. Initially, preferential attack was noted on areas where oxide film had been scratched or handled. However, near the end of a run a random distribution of undissolved cladding existed; 90% of the cladding was removed in 6.5 hours. (auth)
Date: February 23, 1961
Creator: Smith, P. W.
Partner: UNT Libraries Government Documents Department
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Feasibility Study of a New Mass Flow System. Quarterly Report No. 4, March 1, 1961 to May 31, 1961

Description: Activities are reported on development work on a mass flow system capable of measuring externally the properties of homogeneous flow, slurries, highly corrosive fluids, and multi-phase fluids. In the proposed system, the fluid passes through an S-shaped tube wherein measurements of the angular momentum and density yield mass flow directly. (B.O.G.)
Date: June 23, 1961
Creator: Haffner, J.W.
Partner: UNT Libraries Government Documents Department
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A STUDY OF RESONANCES OF THE Z-7r SYSTEM

Description: Recently a T = 1 resonance in the {Lambda}-{pi} system called Y{sub 1} has been observed with a mass of 1385 MeV. Two types of resonances have been predicted that might relate this observation to other elementary-particle interactions: (1) P 3/2 resonances in the {Lambda}-{pi} and {Sigma}-{pi} systems predicted by global symmetry, corresponding to the (3,2/ 3/2) resonance of the {pi}-N system, (2) a spin-1/2 Y-{pi} resonance resulting from a bound state in the {bar K}-N system. The position and the width of the observed Y{sub 1} resonance agree with both theories, but since the spin and parity have not yet been determined, they cannot distinguish between the two theoretical interpretations.
Date: May 23, 1961
Creator: Alston, M.H.; Alvarez, L.W.; Eberhard, P.; Good, M.L.; Graziano,W.; Ticho, H.K. et al.
Partner: UNT Libraries Government Documents Department
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LOW FREQUENCY AMPLIFIER IH-130-1

Description: The design of a transistorized d-c coupled amplifier having very good gain stability and low drift of the output d-c level is described. Low-frequency input signals from a low-impedance source are amplified by the system to an approximate peak-to-peak amplitude of 4 v. (J.R.D.)
Date: October 23, 1961
Creator: Llacer, J.
Partner: UNT Libraries Government Documents Department
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RADIOISOTOPE AND RADIATION APPLICATIONS QUARTERLY PROGRESS REPORT. SECTION I. USE OF INTRINSIC RADIOACTIVE TRACERS FOR PROCESS CONTROL. SECTION II. RADIATION-INDUCED GRAFT-POLYMERIZATION STUDIES

Description: Research was continued in the areas of intrinsic radioactive tracers for industrial process control and the influence of structural factors in radiation- induced graft polymerization. The use of in-process isotope neutron soarces to produce short-lived radiotraces is discussed. A 10c Po--Be neutron source was obtained for exploratory experiments. The design and construction of a neutronsource storage shield and an activatioa-cell holder are underway. The effect of structural factors oii the eIficiency of free-radical site formation in acrylate and methacrylate polymers was emphasized. Site measurements versus dose were made for poly-n-hexylmethacrylate. Two additional methods for measuring free-radical conceiitrations, a chemical method employing diphenylpicrylhydrazyl and hydroquinone and a method based on molecular-weight decreases, were developed. The grafting studies were continued. (M.C.G.)
Date: October 23, 1961
Creator: McFarling, J.L.; Gluck, P.; Kircher, J.F.; Sunderman, D.N.; Sliemers, F.A.; Luttinger, M. et al.
Partner: UNT Libraries Government Documents Department
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THE EFFECTS OF INTERNAL HEAT GENERATION ON POT CALCINATION RATES FOR RADIOACTIVE WASTES

Description: Methods by which the radial deposition mechanism was determined in experiments with simulated waste solutions are reviewed. Based on this mechanism, an expression for the rate of solid deposition with internal heat generation was developed by a combined heat and material balance. A sample calculation for Purex waste showed that a moderate heat generation rate of 5000 Btu/hr/ft/sup 3/ would decrease the time to fill a 12-in.-dia calcination vessel from 78 to 55 hr. For the calcination stage of the process in which the deposited solids are heated in the absence of a liquid phase, a solution was developed for the equation of heat transfer with the temperature profile from the solid deposition stage as an initial condition. For the example Purex waste with a heat generation rate of 5000 Btu/hr ft/sup 3/, less than 15 min would be required for calcination, compared to about 8 hr in experiments with simulated wastes. (auth)
Date: October 23, 1961
Creator: Perona, J.J.
Partner: UNT Libraries Government Documents Department
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Calculation of Doppler Coefficient and Other Safety Parameters for a Large Fast Oxide Reactor

Description: Several safety parameters are calculated for a large, fast, Na-cooled, oxide-fueled reactor. The Doppler coefficient is studied as regards its effect on the reactivity during a power excursion, and its dependence on the neutron spectrum, on the concentrations of U/sup 238/, Pu /sup 239/ , a nd Pu/sup 240/, on spatial temperature and power distributions, and on temperature. Other parameters studied include the Na temperature coefficient of reactivity, and the reactivity insertion caused by total Na loss; reactivity coefficients caused by thermal expansion of fuel and steel cladding; the excess operating reactivity; and the reactivity caused by a fuel slump. The effects of a Be reflector on neutron lifetimes are determined. The safety aspects are balanced against economic considerations. (T.F.H.)
Date: March 23, 1961
Creator: Greebler, P.; Hutchins, B. A. & Sueoka, J. R.
Partner: UNT Libraries Government Documents Department
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A MODULAR, LOW-COST, SODIUM-HEATED STEAM GENERATOR

Description: A proposed design and development program for a potentially economical, high-performance, sodium-heated steam generator is described. The concept employs modular units grouped together to provide for any combined power level desired. Fabrication expense is shown to be reduced by the reduction in heat transfer area requirements. This reduc, tion is achieved through improved heat transfer coefficients which exist under supercritical steam conditions. The testing of two small units ( approximates 18 Mw total) is shown to be sufficient to verify performance for any size unit because of the modular concept employed. (auth)
Date: October 23, 1961
Partner: UNT Libraries Government Documents Department
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Feasibility Study of a New Mass Flow System : Quarterly Report No. 4 Covering the Period from March 1, 1961 to May 31, 1961

Description: This is the fourth quarterly report that documents a system of mass flow that can record measurements of homogeneous flow, slurries, highly corrosive fluids and multiphase fluids, additionally considering pressure drops, measuring external to the flow, ruggedness and reliability.
Date: June 23, 1961
Creator: Haffner, J. W.; Stone, C. A. & Genthe, William K.
Partner: UNT Libraries Government Documents Department
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Analog to digital converter system for temperature monitoring -- B, C, D, DR, F, and H reactors

Description: This document discusses a proposal that certain presently installed reactor process water outlet temperature data logging equipment in subject reactors to be replaced with new functionally simplified equipment of a more adequate design. The primary purpose of the proposed installation is to replace existing equipment which is obsolete and in three reactors is worn out to the point where the equipment is out of service frequently for periods of time up to 8 hours or more. The new equipment will provide reliable process tube temperature information for use in the functions of reactor control and product accountability. Based upon anticipated incremental production gains resulting from use of the new equipment, the amortization period for the project is calculated at 2.7 years.
Date: March 23, 1961
Creator: Ballowe, J. W.
Partner: UNT Libraries Government Documents Department
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Critical mass control specifications: Hoods 7-C and 9-B

Description: This report discusses the critical mass control specifications for Hoods 7-C and 9-B have become obsolete due to needed storage within the confines of Hood 9-C, and equipment modifications. Nuclear safety in Hood 7-C and 9-B depends almost entirely on controlling the mass and geometry of the plutonium compounds not confined by the processing equipment. Generally, the processing vessels and associated piping are designed and arranged in the hood to be critically safe at full operating capacity. This safety is not assured, however, if plutonium masses outside of the equipment exceed certain proportions of geometry and mass. For those cases where always safe geometry confinement cannot be assured, administrative controls are established.
Date: January 23, 1961
Creator: Smith, R. E.
Partner: UNT Libraries Government Documents Department
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Owner-operator process and functional requirements interim modifications for improved coolant backup 100-B, C, D, DR, F, and H Reactors, Project CGI-905. Revision 1

Description: This document defines the user,s process and functional requirements which shall be used as the basis for the preparation of the design for Project CGI-905, Interim Modifications for improved Coolant Backup 100-B, C, D, DR, F, and H Reactors. The objective in making these modifications is to provide improved reliability and adequacy in the last ditch reactor cooling systems for current and short-range forecast conditions. Performance requirements for the last ditch cooling system are based on the reactor cooling System criteria set forth in Document HW 66929. These performance criteria require that the last ditch cooling system be independent of both the primary and secondary cooling system, including piping to the reactor manifold, and that it must be capable of providing shutdown flow indefinitely, assuming instantaneous loss of power to the primary system and concurrent failure of the secondary system to provide its rated flow. The purpose of this document is to define the process requirements of the modifications and additions to the last ditch cooling systems and to outline the functional descriptions of the proposed equipment.
Date: October 23, 1961
Creator: Schack, M. H. & Tupper, W. J.
Partner: UNT Libraries Government Documents Department
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Error analysis of the TAI equation

Description: There is a certain tolerance of error implicit in any calculation based upon measured physical data. Occasionally, the error is explicitly recognized by attaching a plus or minus variation to the calculated quantity. More often, however, the error is simply neglected. The present analysis was performed to quantify the error implicit in a typical TAI (Trip-After-Instability) limit calculation. This error results from the precision of measurement of each of the parameters used in the calculation of the TAI limit. Though not specifically considered, the results of this work could be used to establish the required minimum level of accuracy of the tube outlet temperature monitoring equipment. Further, some of the generalized equations could probably be programmed into the ROL (Reactor Operating Limits) to indicate how far each Panellit gauge could be ``rolled`` without exceeding a fixed minimum TAI limit. Since the examination of these other possibilities is beyond the scope of this report, they are left as suggestions for future work only.
Date: October 23, 1961
Creator: Cremer, B. R.
Partner: UNT Libraries Government Documents Department
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Biology Division Semiannual Progress Report for Period Ending August 15, 1961

Description: Members of the Biology Division presented 168 lectures during the period February to August 1961, compared with 116 for each of the two preceding reporting periods. Of these, 96 were before professional societies at home and abroad, and 28 were presented as part of the Traveling Lecture Program.
Date: October 23, 1961
Partner: UNT Libraries Government Documents Department
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Low Frequency Amplifier IH-130-1

Description: A tranistorized d.c. coupled amplifier having very good gain stability, as well as very low drift of the output d.c. level, has been designed. Low frequency input signals with an amplitude of .04 to 2 volts peak-to-peak, approximately, coming from a low impedance source (voice soil of a speaker system) are amplified to an approximate peak-to-peak amplitude of 4 volts. The output is intended to drive a load of the order of 100 kohm.
Date: October 23, 1961
Creator: Llacer, Jorge
Partner: UNT Libraries Government Documents Department
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