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AN 80 MEGAWATT AQUEOUS HOMOGENEOUS BURNER REACTOR. Reactor Design and Feasibility Problem

Description: An 80 Mw aqueous homogeneous burner reactor suitable for producing 20 Mw of electricity at a remote location is described. The reactor fuel consists of a light water uranyl sulfate solution which acts as its own moderator and coolant. The uranium is highly enriched (93% U/sup 235/). The primary considerstions for the design were simplicity and reliability of the components, automatic demand control and safe for any load change, full xenon override not required, possibility of construction within the immediate future, and economic operation not the cortrolling factor. Reasonably complete studies are presented for the reactor physics, safety, stability, chemistry, hent transfer, and operation of the system. (auth)
Date: August 1, 1957
Creator: Chapman, R.H.; Collins, H.L.; Dollard, W.J.; Fieno, D.; Hernandez- Fragoso, J.; Miller, J.W. et al.
Partner: UNT Libraries Government Documents Department

ACCIDENT IN CONTINUOUS-DISSOLVER PILOT PLANT OF FLUORIDE VOLATILITY PROJECT ON MAY 15, 1957

Description: A series of explosions, estimated at five, occurred over a period of ten seconds within the continuous dissolver pilot plant, of the Fluoride Volatility Project on May 15, 1957. The explosive reactions occurred in the dissolver vessels as a result of violent chemical reactions between uranium and an interhalogen mixture. Just what the conditions were which triggered the explosions, have not been definitely established. Nevertheless, based upon the evidence which has been collected, several possible explanations, listed according to probability, are presented. A number of recommendations are included to be followed before operation of the pilot plant is resumed. These recommendations relate to additional laboratory research, equipment design, facility design, and use of a review committee. Safety rules for handling BrF/ sub 3/, BrF/sub 5/, ClF/sub 3/, and Br/sub 2/ are appended. (C.H.)
Date: July 10, 1957
Creator: Strickland, G.; Horn, F.L.; Johnson, R. & Dwyer, O.E.
Partner: UNT Libraries Government Documents Department

CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR OCTOBER, NOVEMBER, AND DECEMBER 1956

Description: A study of mass transfer in a continuous-flow mixing chamber, fluoride volatilization separations process, corrosion testing in fused fluoride systems, behavior of Pu during volatilization of UF/sub 6/, preparation of PuF/sub 6/ by fluorination of PuF/sub 4/, particle size distribution and U content of UF/sub 4/ , stoichiometric behavior of the reaction IF/sub 5/ + F/sub 2/ + I/sub ignition data on stainless steel, were reported. Studies were continued on the analysis of crude green salt from U ore concentrates, fluidized-bed green salt pilot plant, calcination of reactor fuel wastes, reactor chemistry, chemical- metallurgical separation processes, waste processing operations, and the operation of the gammairradiation facility. (W.L.H.)
Date: March 1, 1957
Partner: UNT Libraries Government Documents Department

DESCRIPTION OF ORNL POOL TYPE CRITICAL FACILITY

Description: The Pool Type Critical Facility (PTCF) is a low powered, highly eariched (90 to 95% U/sup 235/) ordinary light water cooled and moderated, beryllium oxide reflected assembly. It is generally similar to the present BSR at ORNL, the principal modification being that the grid plate is arranged to accommodate both ORR and BSR fuel elements. The PTCF is located in the northwest corner of the existing BSR pool. The 9 x 7 lattice provides 63 fuel, control rod, or reflector positions. (W.D.M.)
Date: July 16, 1957
Creator: Bates, A.E.G.
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

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

DESIGN OF MTR FUEL-ELEMENT-SOURCE SHIPPING CASK FOR RAILWAY MOBILE IRRADIATION FACILITY. Progress Report

Description: The gamma -radiation field from a battery of 10 MTR spent fuel elements was calculated and a special shipping cask designed to contain the 10 elements. An internal watercooled tank in the cask holds the 10 elements in the vertical position. Two external air-cooled, finned-tube heat exchangers control the water temperature. The sides of the cask open to convert the cask to a radiation source without changing the position of the elements. A unique feature of the design is a device for closing the sides of the cask by gravity in the event of accident or power failure. This provides a ''fail-safe'' safety feature. (auth)
Date: September 1, 1957
Creator: Brownell, L.E.; Patterson, J. & Purohit, S.N.
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

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

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

The Effects of Nuclear Weapons

Description: This handbook prepared by the Armed Forces Special Weapons Project of the Department of Defense in coordination with other cognizant government agencies and published by the United States Atomic Energy Commission, is a comprehensive summary of current knowledge on the effects of nuclear weapons. The effects information contained herein is calculated for yields up to 20 megatons and the scaling laws for hypothetically extending the calculations beyond this limit are given. The figure of 20 megatons however is not be taken as an indication of capabilities or developments.
Date: June 1, 1957
Creator: Glasstone, Samuel
Partner: UNT Libraries Government Documents Department

Efficiency of Scavenging Devices in Determining Falloug. Progress Report No. 6 March 15 to July 31, 1957

Description: A fall-out sample collector was designed and tested for use in collecting samples at the soil surface. The sampler consists of artificial grass and a stainless steel pot. Results are included from preliminary studies on the scavenging properties of artificial grass. The effects of relative humidity, rain, and wind velocity on the efficiency of scavenging devices were investigated. A comparison was made of Sr/sup 90/ fall-out data from samples collected on gummed film and surface soil samples from various locations. Preliminary experiments were performed for the evaluation of devices used in determining air concentration of radioactive fall-out or other particulate matter. (For preceding period see AECU-3435.) (C.H.)
Date: September 23, 1957
Creator: Rosinski, J.
Partner: UNT Libraries Government Documents Department