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ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. GCRE-I HAZARDS SUMMARY REPORT. ADDENDUM III

Description: The hazards evaluation was modified to reflect certain changes made to the equipment as a result of operating experience. These changes included: the addition of a startup interlock circuit; the modification of a startup interlock circuit; several minor modifications to the control rod actuators; and the addition of the tube-sheet cooling system. (M.C.G.)
Date: May 1, 1960
Partner: UNT Libraries Government Documents Department
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APPR-1 STARTUP ANALYSIS

Description: The Army Package Power Reactor (APPR-1) control system was analyzed to find its response to a startup accident. The system was found to be adequate, at 0.086%/sec rod withdrawal, for operation of at least twice the rated power. (C.J.G.)
Date: July 19, 1960
Creator: Stone, R. S.
Partner: UNT Libraries Government Documents Department
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HAZARDS SUMMARY REPORT FOR THE ARMY PACKAGE POWER REACTOR SM-1, TASK XVII

Description: The SM-1 is described and the various hazards are reviewed. Because of the reactor's location near the nation's capital, containment is of the utmost importance. The maximum energy releace in any possible accident is 7.4 million Btu which is completely contained within a 7/8-in.-thick steel cylindrical shell with hemispherical ends. The vapor container is 60 ft high and 32 ft in diameter and is lined on the iside with 2 ft of reinforced concrete which provides missile protection and is part of … more
Date: May 1, 1960
Creator: Rosen, S.S. ed.
Partner: UNT Libraries Government Documents Department
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Recent Developments in Magnet Design and Fabrication Procedures (BSR Type Magnets)

Description: The techniques of design and fabrication of red magnets for the Bulk Shielding Reactor II are presented. An experimental model, designed to eliminate the can and its associated air gap, is described. Data on magnet performance are included. (C.J.G.)
Date: July 1, 1960
Creator: Tallackson, J. R. & Santoro, R. T.
Partner: UNT Libraries Government Documents Department
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SL-1 ANNUAL OPERATING REPORT FOR FEBRUARY 1959-FEBRUARY 1960

Description: The pericd from February, 1959, when CE assumed operative responsibility of the SL-1 Reactor Plant, to February, 1960 is covered. The operations of the year are summarized; the reactor, instrumentation, mechanical, electrical, and facility systems are evaluated; health and safety, and the operational costing program are discussed. (auth)
Date: May 1, 1960
Creator: Canfield, R. T.; Crudele, J. S.; Vallario, E. J.; Young, R. G. & Rausch, W. P.
Partner: UNT Libraries Government Documents Department
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Instability Studies With EBR-I, Mark III

Description: The results of instability studies suggest that the operational characteristics of the fully ribbed and rigid Mark III loading are governed by feedback processes that guarantee safe and stable operation under normal operating condiiions. No evidence of positive reactivity effects was noted for the fully-ribbed rigid core. Logical extrapolations of full-power full-flow test data indicate that the reactor could be brought into a resonant condition for power levels exceeding 1000 Mw. Strong nonlin… more
Date: December 1, 1960
Creator: Smith, R. R.; Boland, J. F.; McGinnis, F. D.; Novick, M. & Thalgott, F. W.
Partner: UNT Libraries Government Documents Department
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REACTOR DEVELOPMENT PROGRAM PROGRESS REPORT FOR DECEMBER 1960

Description: Research and development are reported on the following reactors: water- cooled, EBWR, BORAX-V, sodium-cooled, EBR-1, and EBR-II. General studies were also made on nuclear superheating, reactor safety, and nuclear technology. (For preceding period see ANL-6269). (W.L.H.)
Date: January 16, 1960
Partner: UNT Libraries Government Documents Department
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ABWR QUARTERLY PROGRESS REPORT, JANUARY 1 TO MARCH 31, 1960. VOLUME I. SL- 1 OPERATIONS AND EVALUATION . VOLUME II. SL-1 HEALTH PHYSICS AND SAFETY

Description: The Stationary Low Power Reactor No. 1 is a three Mw boiling water reactor designed to demonstrate the feasibility of a nuclear reactor to supply electrical power and space heat for remote sites. In addition to performance evaluation the facility provides training for military personnel. The reactor was operated for 1159 hr during the quarter for a total core burnup of 20.3%. Power generation was 103.7 Mwd for a total power accumulation of 466.9 Mwd. Eight malfunctions occurred during the quart… more
Date: May 25, 1960
Creator: Canfield, R. T.; Rausch, W. P.; Vallario, E. J.; Young, R. G. & Henderson, S. K.
Partner: UNT Libraries Government Documents Department
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SM-1 Reactor Vessel Penetrated Gasket Design and Test Report

Description: Mechanical compression tests were performed on gasket test specimens machined to the cross-sectional dimensions of a stainless steel (Type 304) ring type gasket to be installed in the SM-1 reactor pressure vessel. Testing the mechanical properties of the gasket specimens under varying loads, and subsequent sectioning and inspection of specimens for adequacy of welded and brazed joints, gave the following results: (1) a penetration scheme involving five 0.070-in. diam. holes, spaced 1/4 in. cent… more
Date: June 10, 1960
Creator: Gebhardt, F. G.
Partner: UNT Libraries Government Documents Department
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SUMMARY OF REACTOR DESIGN INFORMATION FROM THREE YEARS' OPERATION OF A SMALL PWR

Description: Reactor design information obtained from 3 years' operation of a small pressurized-water reactor, the SM-1 (formerly APPR-l), is presented and discussed. The SM-1 reactor, designed to produce 10 Mw(t) power, employs fully enriched uranium fuel in the form of UO/sub 2/ dispersed in stainless-steel fuel plates. The reactor is cooled by water at 1200 psia and mean temperature of 44) deg F. Core-physics measurements were performed of temperature coefficient, pressure coefficient, rod calibration, s… more
Date: September 1, 1960
Creator: Gallagher, J.G.
Partner: UNT Libraries Government Documents Department
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CALCULATED REACTIVITY CHANGES PRODUCED BY THE OSCILLATION OF AN EPITHERMAL NEUTRON ABSORBER IN THE BULK SHIELDING REACTOR

Description: An attempt is made to ascertain the optimum working conditions of a pile oscillator and to compare this method with the danger coefficient technique from the point of view of minimum amount of resonance absorption which can be detected. The space-time behavior of the absorption properties of the sample is described by means of a delta -function and the reactor kinetic equations are obtained by using a single mode expansion of the flux. The results are applied to a bare reactor model equivalent … more
Date: April 1, 1960
Creator: Perez-Belles, R
Partner: UNT Libraries Government Documents Department
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SM-1--RESEARCH AND DEVELOPMENT QUARTERLY REPORT FOR APRIL 1 TO JUNE 30, 1960

Description: With the exception of a brief period of slightly elevated chloride level in the secondary blowdown, water-chemistry conditions during the period were satisfactory. During the period, the reactor was shut down for end-of-core-life testing and rearrangement. A set of specifications covering all electronic and electromechanical mechanisms required to control the SM-1 reactor through the rod- drive motors and clutches was prepared and issued. Installation of instrumentation for plant response and s… more
Date: September 20, 1960
Creator: Bergman, C. A.; Brown, W. S. & Hasse, R. A. et al.
Partner: UNT Libraries Government Documents Department
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A STUDY OF TECHNIQUES AND THE DEVELOPMENT OF EQUIPMENT FOR DECANNING EBR-II FUEL ELEMENTS

Description: Remotely operated, semi-automatic machines, designed to effect the mechanical disassembly (i.e., decanning) of spent fuel elements from the Experimental Breeder Reactor-II, were developed. The machines described are laboratory models which successfully decanned simulated fuel elements. They are electrically or pneumatically operated and are capable of decanning three fuel elements per minute without the routine use of manipulators. Each machine is made up of functional units which are sequentia… more
Date: January 1, 1960
Creator: Simon, J.P.
Partner: UNT Libraries Government Documents Department
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Some Calculations for a Plutonium-Fueled Zpr-Iii

Description: Calculations of critical size, reactivity coefficients, and delayed neutron fractions are described for mockups of a plutonium-fueled EBR-I (Mark IV) and five possible metal-fueled power reactors. The calculations for critical size were performed using the SNG transport-theory code. The reactivity coefficients were estimated by SNG calculations or by one-group perturbation- theory desk calculations. The delayed-neutron fractions were estimated by an approximate method, which starts with a calcu… more
Date: September 1, 1960
Creator: Baker, A. R.
Partner: UNT Libraries Government Documents Department
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SPECIFICATIONS AND FABRICATION PROCEDURES FOR SM-1A CORE II CONTROL ROD FUEL ELEMENTS

Description: Stainless steel-base fuel components of thin plate-type construction and containing a dispersion of UO/sub 2/ were successfully employed in powering the Army Package Power Reactor. The component is designed for radioactive service in pressurized water and consists of sixteen composite fuel plates Joined into an integral unit or assembly by brazing. Specifications covering loading, materials, and processing are presented. A list of applicable drawings and the process flow diagram are included. (… more
Date: May 13, 1960
Partner: UNT Libraries Government Documents Department
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A LUNAR POWER PLANT

Description: A concept of a nuclear power plant to be assembled on earth and operated on the moon is presented. The two principal design objectives are reliability and high specific power. Wherever there is an incompatibility between these two objectives, the decision favors reliability. The design is based on the premise that the power plant must be designed on the basis of current technology and with a minimum amount of research and development. The principal components consist of a fast reactor in a dire… more
Date: December 1, 1960
Creator: Armstrong, R.H.; Carter, J.C.; Hummel, H.H.; Janicke, M.J. & Marchaterre, J.F.
Partner: UNT Libraries Government Documents Department
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Anticipated heat generation rate of MGCR-III fuel element as a function of enrichment

Description: The DR-1 Loop, located in the C test hole of the DR Reactor, provides a high temperature, recirculating gas-cooled facility for the irradiation of experimental fuel elements. The loop is being utilized currently by General Atomic, a Division of General Dynamics, to evaluate fuel elements in support of their work on the Maritime Gas-Cooled Reactor Program, a program which is directed at the development of a ship propulsion unit consisting of a gas-cooled reactor driving a closed cycle gas turbin… more
Date: June 2, 1960
Creator: Bunch, W. L.
Partner: UNT Libraries Government Documents Department
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THE MANUFACTURE OF CENTRIFUGALLY CAST ALLOY FUEL SLUGS (MARK-II FUEL LOADING FOR EBR-I)

Description: The fabrication of the Mark-II fuel loading for EBR-I, consisting of a U- 2 wt.% Zr alloy, is described. Fuel slugs measuring 0.383 in. in diameter were centrifugally cast to size in massive Cu molds. The resulting microstructure was characterized by a fine grain size and a completely random grain orientation not easily obtained in wrought fissile material of comparable composition, even after heat treatment. Reproducibility of the desirable as-cast structure and physical properties of the fuel… more
Date: July 1, 1960
Creator: Yaggee, F.L.
Partner: UNT Libraries Government Documents Department
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SM-1A PROJECT--TECHNICAL MANUAL: CHEMISTRY

Description: A manual is given of the equipment and procedures used in the Army Reactor (SM-1A) to control the water purity and makeup. In addition to a description of the primary purification control system, a discussion is presented of the water chemistry control procedures for the auxiliary systems (e.g., the spent-fuel pit, the shield tank, and the waste disposal system). (T.F.H.)
Date: September 29, 1960
Creator: Chupak, J.
Partner: UNT Libraries Government Documents Department
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THE INTERNAL FEEDBACK OF EBR-I MARK-III

Description: No Description Available.
Date: February 1, 1960
Creator: Carter, J. C.; Sparks, D. W. & Tessier, J. H.
Partner: UNT Libraries Government Documents Department
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