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Report on discussion of Pinex experiment with J-12 group at Los Alamos

Description: Plans for participation in Operation Hardtack include performance of a Pinex experiment on three barge-based events: Nutmeg, Hickory, and Juniper. The J-12 group at Los Alamos has been planning for a group of similar experiments. Inclusion of Pinex in the Hardtack diagnostic program occurred considerably later; also, J-12 has successfully carried out two Pinex experiments during Operation Plumbbob. This visit was made to take the fullest possible advantage of their experience to date. Discussion of the experiment at these meetings is summarized under five convenient headings: Detector; Pinhole and Collimator Assembly; Alignment; Data Analysis; and Recovery.
Date: December 30, 1957
Creator: Boyrie, E.; Chesterman, A. & Clark, A.
Partner: UNT Libraries Government Documents Department

STATUS AND FUTURE REQUIREMENTS FOR THE URANIUM-233 POWER REACTOR PROGRAM

Description: The status of thorium and uraniumn-233 technology for power reactor applications is reviewed. In the areas of fuel cycle, reactor design snd reactor operational problems, information was s developed on current status of techology, current and planned research and developrent programs, need for additional resesrch and developmet, and time schedule of required kilograms of U-23 over the next five years to carry out the research and development now being planned, and the further work believed desirable in the longer term. (auth)
Date: December 11, 1957
Creator: Mash, D.R. & Ottenberg, A.
Partner: UNT Libraries Government Documents Department

DESIGN AND PERFORMANCE CHARACTERISTICS OF MAGNETIC JACK-TYPE CONTROL ROD DRIVE

Description: The magnetic jack is a hermetically sealed, step-motion linear motor which saiisfies the need for a reliable, lowcost, nuclear reactor conirol rod drive. It is especially applicable for operation under adverse conditions peculiar to pressurized water-cooled reactors. The jack consists of a pressure shell, four sets of external magnet coils, and one internal moving part ivhich imparts linear motion to rod extensions of the control rod. The desired motion is achieved by energizing and de-energizing the various coils in a given sequence. An electromagnetic position indicator registers the position of the drive rods, thereby loeating the position of the control rod in the reactor core. Two magmetic jacks were operated under simulated boiling water reactor operating conditions for 3150 hours (18,300 ft total rod travel, 2210 scrams) and 13 0 hours (7,700 ft total rod travel, 1000 scrams), respeetively. There were no mechanical malfunctions and no significant wear was observed on the components. The position of the rod was indicated to an accuracy of 0.05 in. Complementary information includes detailed formulas and work sheets for calculating magnetic circuits and component drawings for two alternate magnetic jack designs. (auth)
Date: December 1, 1957
Creator: Young, J.N.
Partner: UNT Libraries Government Documents Department

DEVELOPMENT OF ULTRASONIC TECHNIQUES FOR INSPECTING EXPERIMENTAL BOILING WATER REACTOR CAST URANIUM ALLOY CORES AND FUEL PLATES

Description: An ultrasonic test technique was developed for the inspection of fuel plates, uranium alloy cores, amd fuel plates in subassemblies for the Experimental Boiling Water Reactor (EBWR). For these tests a special scanner was designed and fabricated. The equipment could serve as a research tool as well as being used for inspecting numerous items of diversified lengths and shapes. A transmission technique was used at am ultrasonic frequency of 5 megacycles. The mechanical motion of the inspecting transducers was synchronized to a helix recorder so as to provide a permanent two-dimensional recording on electrosensitive paper. It was possible to detect piping, shrink, porosity, inclusions and microinclusions in the uranium alloy castings. In the completed fuel plates, a nonbond area of 1/8 of an ineh in diameter could be located. With the construction of a special two-arm probe, fuel plates installed in subassemblies were successfully tested by a transmission technique. (auth)
Date: December 1, 1957
Creator: Beck, W.N. & McGonnagle, W.J.
Partner: UNT Libraries Government Documents Department

DESIGN AND DEVELOPMENT OF A 1/2-INCH TITANIUM TO STAINLESS FLANGE

Description: The gas lift pump has not been considered here as a prinme mover for circulating coolant through a primary circuit, in view of the complexity which would arise in designing such a pump to overcome the head losses associated with the secondary large volumetric flow rates. The purpose of this investigation was merely to make a preliminary study of the general character of a heavy liquid metal gas-lift, to compare its operation with that of water, and to obtain some idea of the relationship of efficiency to flow rate. (A.C.)
Date: November 27, 1957
Creator: Draper, B.D. & Roller, H.C.
Partner: UNT Libraries Government Documents Department

Definitive scope of a facility for E-Metal product segregation at the UO{sub 3} Plant Project CG-767

Description: E-Metal production is scheduled to start through the UO{sub 3} Plant in July of 1958. E-Metal is defined in HW-46138 as uranium metal enriched with U-235 to a level selected to be always-safe for non-metallic uranium forms, i.e. for compounds encountered during solvent extraction or calcination. Currently E-metal as selected contains 0.94% U-235 prior to irradiation. Planning of a segregation facility requires that the mixing of E-Metal with normal uranium be minimized, thereby preventing costly downgrading. Segregation of E-Metal through existing facilities would require extensive cleanout and flushing. Production scheduling with present demonstrated capacity would make this method impossible. The Redox Plant will produce E-Metal on an intermittent basis. It is expected that normal operating production of E-Metal through the Redox Plant will be quantities of 100 to 200 tons. Production through the UO{sub 3} Plant will follow on this same intermittent basis. During the first two quarters of FY `59 the UO{sub 3} Plant production of E-Metal is forecast at not greater than 100 tons per quarter. Following this initial period the E-Metal production is forecast to run 135 to 200 tons per quarter for the next three to four years. It is the purpose of this document to establish a scope and design criteria for a facility providing segregation of E-metal in the UO{sub 3} Plant until the continuous calciners have demonstrated sufficient capacity to process all production. The two new tanks required for this project may be obtained from excess vessels available on-site. In order to complete this facility by July, 1958, it will be required that existing on-site equipment and materials be adapted for all possible applications.
Date: November 4, 1957
Creator: Gustafson, L. D.
Partner: UNT Libraries Government Documents Department

A STUDY OF CORE FUEL SYSTEMS FOR A FAST BREEDER POWER REACTOR

Description: The first phase of a program aimed toward the development of materials and a core-subassembly design for the second core of the Fermi Reactor is outlined. The ground rules established by APDA for the study were based upon the performance requirements of the reactor plant with some modification to permit hlgher power generation and upon a value of Pu produced of about per g. Consideratlons of various factors led to the selection of the dispersion or cermet fuel as havlng the most potential for the Core II application. The fuel selected was a 30 vol. % dispersion of UO/sub 2/ in U--10 wt. % Mo or gamma- phasetype alloy, zirconium clad, in a flat-plate-subassembly design. The plant economics for subassembly designs of the fuel systems were evaluated at a core power level of 616 Mw. (W.D.M.)
Date: November 1, 1957
Creator: Fawcett, S.L. ed.
Partner: UNT Libraries Government Documents Department

Pressurized Water Reactor Program Technical Progress Report for the Period July 15, 1954 to August 26, 1954

Description: This progress report has 2 parts. Part 1 PWR Engineering covers the following topics: (1) power plant analysis and systems; (2) power plant components and component materials and tests; and (3) reactor and auxiliaries. Part 2 PWR Development covers: (1) fuel element development; (2) metallurgy of core materials; (3) materials application development; (4) chemistry development; (5) irradiation effects; and (6) reactor physics.
Date: October 31, 1957
Partner: UNT Libraries Government Documents Department

SHOCK AND VIBRATION IN NAVAL REACTORS

Description: The problem of designing a reactor to withstand the shocks and vibration incident to shipboard service in Naval craft consists of three principal parts. First the loads must be defined in some rational manner, then the responses of the various reactor structures to these loads must be predicted, and finally the responses must be compared to some damage criteria to determine whether the design is adequate or not. A brief discussion of each of these major parts is given, and then a specific example is worked through to illustrate what is involved in the whole process. (auth)
Date: October 31, 1957
Creator: Mains, R.M.
Partner: UNT Libraries Government Documents Department

Transient Heat Transfer in Reactor Coolant Channels

Description: An analysis is presented of the transient behavior of a generalized cooiant channel neglecting temperature dependent reactivity changes. The analysis is applicable to forced convection cooling of heterogeneous reactor fuel elements or electrically heated simulation thereof. Derivations are given for cases of variation of coolant inlet temperature and of heat generation. An approximation is also developed applicable to thin fuel elements. From this, solutions are obtained for cases-of impulsive, step, linear, and step-exponential variations of inlet temperature, and, of impulsive and uniform variations of heat generation. The solutions presented will be of use during preliminary stages of design of new heterogeneous reactor concepts (when the use of computing machines may not be warranted), and, in the design and interpretation of transient experiments simulating reactor fuel channels. (auth)
Date: October 31, 1957
Creator: Stein, R. P.
Partner: UNT Libraries Government Documents Department

DIMENSIONALLY STABLE ALLOYS. Interim Report

Description: The development of dimensionally stable alloys for high temperature reactor application is discussed. Cold pressing followed by sintering was determined to be the most satisfactory method. Evaluation of alloys by alpha - beta thermal cycling indicated the superiority of U--Mo and U--Nb alloys. A few specimens containing small additions of Mo, Nb, and Si were irradiation tssted in the Materials Testing Reactor. Of these, the Nb alloy (1.6 wt.% Nb) appeared to be most stable. The Mo alloys were somewhat less satisfactory and the alloys containing Si were not stable. (auth)
Date: October 30, 1957
Creator: Eiss, A.L. & Kalish, H.S.
Partner: UNT Libraries Government Documents Department

MEASUREMENT OF BEAM CURRENT IN THE BEVATRON BY INDUCED VOLTAGES (thesis)

Description: The Bevatron uses a system of electrodes through which the internal proton beam passes in order to continuously measure the magnitude and radial position of the beam. The bunched circulating beam induces a periodic voltage on the electrodes. This signal is amplified and displayed on an oscilloscope and also converted to direct current for operation of a recorder. Two types of electrode systems are used. The first is a large hollow box to provide beam magnitude signals for specialized monitoring and for primary calibration. The second system consists of two sets of smaller electrodes. One set provides beam radial-position information for tracking control, and the other provides beam magnitude information for magnitude control and for general distribution to experimenters associated with the Bevatron. A telemetering radio link is used to relay beam information to those in other areas. Problems associated with handling the beam signal are discussed, and the design principles involved in detection, amplification, and isolation of the signal are described. Calibration techniques, signal distribution facilities, and control features are also given. The systems described are stable and provide the desired information with a minimum of maintenance and operational difficulty. (auth)
Date: October 28, 1957
Creator: Lavrischeff, J.T.
Partner: UNT Libraries Government Documents Department

THE DEVELOPMENT OF COMPOSITE CONTROL RODS FOR WATER-COOLED POWER REACTORS

Description: The phrase "composite control rod" is used to describe a hafnium-tipped titanium-boron control component with a titanium cladding. Blades for such cortrol rods were successfully prepared in cooperation with the Battelle Memorial Institute by a picture-frame rolling technique. The rolling packs, which are machined from type 304 stainless steel, contain slntered titanium boron and wrought hafnium core materials in a commercially pure titanium envelope. Such packs are evacuated, sealod off, and rolled at 16O0 F with a total reduction of 3/1 using 20% reduction per roll setting. Postfabrication treatments include mechanical removal of the stainless steel envelope, flat annealing, machining, and stress relief annealing. Data on the mechanical properties, corrosion performance, thermal cycling resistance, and irradiation damage resistance of composite control rod components are presented. This information strongly indicates that composite control rods will perform satisfactorily in water-coolod reactors. (aut)h
Date: October 15, 1957
Creator: Ray, W.E.
Partner: UNT Libraries Government Documents Department

AN EVALUATION OF HEAVY WATER REACTORS FOR POWER

Description: Reference designs for pressurized and direct-boiling D/sub 2/O reactors were prepared for electrical outputs of 20, 100, and 250 electrical Mw. A number of possible core designs were considered and those utilized which seemed most appropriate to give low-cost power. The technology and costs available today were employed in the preparation of the over-all plant designs. The Consolidated Western Steel Division of U. S. Steel Corporation assisted by preparing a comprehensive report on the design of large pressure vessels and containment vessels. Zr-clad U fuel elements were used as the study basis, but the effect of using UO/sub 2/ and stainless steel cladding was also considered. The principal results found were: (1) Over a wide range of operating conditions snd economic situations, enriched U (up to perhaps 1.4% U/sup 235/) is presently more economic to employ in D/sub 2/O reactors than is natural U. (2) In the longer range, the use of natural U may become more economic as Zr fabrication costs decrease, continuous charge-discharge devices are developed to permit longer exposure levels, and pressure-vessel technology advances so that the large critical masses and core diameters required are not such sn economic penalty on the natural U. The results agree quite well with the data and discussions of the Canadians. (auth)
Date: October 1, 1957
Creator: Herron, D.P.; Newkirk, W.H. & Puishes, A.
Partner: UNT Libraries Government Documents Department

HAZARD SUMMARY REPORT ON THE ARGONNE LOW POWER REACTOR (ALPR)

Description: The over-all design of the Argonne Low Power Reactor is presented. Detailed design data are given as well as information concerning the hydrology, seismology, and meteorology of the building site (NRTS). In addition, a description of the reactor instrumentation and control, mechanical design, heat transfer, and related physics are presented. A full description of the power plant, including the steam and electrical systems, is also given, as well as the operating procedure for both normal and emergency conditions. Over-all reac tor safety is evaluated. Diagrams and graphs are included. (J.R.D.)
Date: October 1, 1957
Creator: Smaardyk, A. ed.
Partner: UNT Libraries Government Documents Department

ON THE DESIGN OF A VERY HIGH-SPEED COMPUTER. Report No. 80

Description: The feasibility of constrncting a digital computer about one hundrnd times faster than present computers, such as ILLIAC, using transistonized circuits and other presently avnilable components and techniques is reported. The results of two design studies are discussed. One involves a minimum of buffer storage in the form of transistor registers, and the other involves a moderrts ammount of buffer storage in the form of a small-capacity, high-speed, random-access buffer memory. Tbe former design is emphasized because its equipment requiremente can be presentiy met. Two controls are used, arithmetic control and advanced control, as well as buffer storage for instructions and operands, and by such meaan various units of the computer are kept in simultaneous operation. The relative speed of the proposed computer compared to that of existing machines depends upon the problem. For problemas dominated by arithmetic operations, it is estimated that the proposed computer will be 100 to 200 times faster than computers such as ILLLAC. For problem dominated by logical and combinatorial operations, the gain in speed will be at least 50times. The computer has a random-access word-arraagement memory of 8192 words of 52 units each with an access time of 1.5 mu sec. The arithmetic unit is designed so that the digite of a multiplier are sensed and acted upon in such a way that the ase of the adder is reduced. Also, ''carry registers'' are used in this unit, and carriers are assimilated only wben neocssary. The computer wiil have an average multiplication time between 3.5 and 4 mu sec, addition times of 0.3 mu sec, and division times of7 to 20 mu sec. The computer, aside from- input-outpat facilities, will contain approximately 15,400 transistors, 34,000 diodes. and 12,000 resistors. The basic circuits built Lfom these transistors have operation times of 5 to40 x 10/sup ...
Date: October 1, 1957
Creator: Gillies, D.B.; Meagher, R.E.; Muller, D.E.; McKay, R.W.; Nash, J.P.; Robertson, J.E. et al.
Partner: UNT Libraries Government Documents Department

ON THE DESIGN OF A VERY HIGH-SPEED COMPUTER. Report No. 80

Description: A summary of a study on the feasibility of constructing a computer about a hundred times faster than present computers using presently available components amd techniques is presented. (W. L.H.)
Date: October 1, 1957
Creator: Gillies, D.B.; Meagher, R.E.; Muller, D.E.; McKay, R.W.; Nash, J.P.; Robertson, J.E. et al.
Partner: UNT Libraries Government Documents Department

PERFORMANCE AND POTENTIAL OF NATURAL CIRCULATION BOILING REACTORS

Description: A parametric study of the potential and performance of natural circulation boiling nuclear reactors is presented. Analyses are based on engineering data and correlation extrapolations obtained from boiling studies at Argonne. Graphs are used extensively to show interrelationships of power density, system pressure, average core coolant density, core height, riser height, channel hydraulic diameter, recirculation flow rate, and exit steam volume fraction. Interesting aspects of reactor design and their diameter, recirculation flow rate, and exit steam volume fraction. Interesting aspects of reactor design and their effects on performance are discussed briefly. (auth)
Date: October 1, 1957
Creator: Flinn, W.S. & Petrick, M.
Partner: UNT Libraries Government Documents Department

REACTOR PROJECTS BRANCH QUARTERLY PROGRESS REPORT FOR JULY, AUGUST, SEPTEMBER 1957

Description: Spert--I-- A brief resume of A'' core experiments is presented and the results of some of the static measurements with the B'' core are shown. It was found that four usable cores are possible with the removable-plate B'' fuel assemblies. The measurements made to date have been with a 24 fuel plate/ assembly, 32 assembly core, and include rod worth, flux distribution, temperature coefficient and preliminary void coefficient studies. Spert--II-- The construction contract was let amd construction started in August. Spert--III -- The control system circuit drawings are essentially complete. Data Reduction and Interpretation-- The progress made in reducing the large raw data backlog from the Spert I A'' core experiments is shown. Work is continuing on the calculation of reactivity behavior during a transient, with the principal area of investigation being that of a boiling or slightiy subcooled experiments. The use of other calculational procedures as a check on the reactivity behavior work is being investigated. Theoretical-- The critical masses for the various possible B'' cores were calculated, and agree quite well with the experimentally determined values. Some machine calculations of the temperature and void effect with the 32 assembly core were made, but no direct comparison with empirical values is yet possible. Two theoretical formulations, one a refinement of the Fuchs' model for reactor self-shutdown which seeks to explain the initial reactor transient behavior, and one which endeavors to show that the shutdown mechanism for reactor periods longer than 50 msec can be ascribed to moderator density changes, were evolved. Instrumentation--The primary activities of the Instrumentation section were directed toward completion of all modification, maintenamce, installation, and calibration of instrumentation necessary for performing static and transient tests on the Spert--I B'' core. Engineering-- Various modifications were made of the Spert--I reactor, including a new mechanism for clamping the ...
Date: October 1, 1957
Creator: Bright, G.O. ed.
Partner: UNT Libraries Government Documents Department

NUCLEAR BATTERY-THERMOCOUPLE TYPE THIRD QUARTERLY REPORT for JULY 1, 1957 TO SEPTEMBER 30, 1957

Description: A second thermoelectric generator consisting of unitized rings of thermopiles was designed and constructed. Three and four rings were asserabled into generators and tested. A maximum efficiency of 0.67% was obtained. At a DELTA T of 400 deg C, an efficienty of 0.56% was obtained; the theoretical maximum for the materials used is 0.83%. (auth)
Date: September 30, 1957
Creator: Blanke, B.C.
Partner: UNT Libraries Government Documents Department