825 Matching Results

Search Results

Results: 1 - 24 next
open access

Steam-Cooled Reactor Feasibility Study: Steam Water Reactor (SWR), Volume 2 (Sections 7 and 8)

Description: Report containing appendices accompanying a steam-cooled reactor feasibility study that include details of the study design related to three categories of fuel element designs: 7-rod cluster, 19-rod cluster, and concentric tubes. Power and coolant cycle, heat transfer and fluid flow, reactor orientation, fuel element design, pressure tube insulation, radioactivity, and the boiling-super heating reactor are described. Details of the Babcock & Wilcox Company evaluations and design diagrams are al… more
Date: August 15, 1958
Creator: East Central Nuclear Group
Partner: UNT Libraries Government Documents Department
open access

Steam-Cooled Reactor Feasibility Study: Steam Water Reactor (SWR), Volume 1 (Sections 1-6)

Description: Report presenting the results of an investigation of the technical feasibility and economic attractiveness of a 200 MWₑ power reactor using natural uranium fuel, a heavy water moderator, and a high pressure and temperature stream coolant. A representative of the reactor design is described along with a reference design selected from a number of design variations. A parametric survey of possible steam-cooled D₂0-moderated reactor designs is included. Mechanical design studies are presented of cr… more
Date: August 15, 1958
Creator: East Central Nuclear Group
Partner: UNT Libraries Government Documents Department
open access

Technical Information, Preliminary Hazards Summary Report, Volume 2, Part B: License Application

Description: Report describing the reactor design, nuclear plant design, existing power generation facilities, and plant organization of the Carolinas–Virginia Tube Reactor. Mechanical design, the primary plant system, primary plan auxiliary systems, reactor and primary plant control and instrumentation, and containment of vapors are discussed.
Date: July 15, 1959
Creator: Carolinas Virginia Nuclear Power Associates, Inc.
Partner: UNT Libraries Government Documents Department
open access

Problem Statement - Treatment of Declad Wastes for Disposal

Description: It is proposed that decladding wastes be converted to dry solid "packages" suitable for ultimate storage in a dry environment. Low temperature solidification of Sulfex and Zirflex decladding wastes by addition of lime, plaster of paris, portland cement, drying agents, etc. seems feasible. A similar treatment of Darex decladding wastes probably should be preceded by chloride removal and nitrate destruction. Calcination may be a preferable alternative for Darex wastes.
Date: December 15, 1959
Creator: Roberts, J. T. & Tomlin, W. E.
Partner: UNT Libraries Government Documents Department
open access

Description of a Proposed Program: Dynamic Analysis of Radiochemical Plant Components

Description: A study is proposed to analyze the solvent extraction operation in order to produce a method of calculating steady state contactor performance for optimizing new flow sheets, and to describe the transient effects in the operation in order to better understand the limitations of the steady state model, to establish quantitative criteria for control, and to provide models for future application to computer controlled plants.
Date: December 15, 1959
Creator: Whatley, M. E. (Marvin E.), 1926-
Partner: UNT Libraries Government Documents Department
open access

Status Report of the Soluble Poison Shim Control for the HFIR

Description: A number of chemicals have been investigated for their possible use as a soluble poison for the HFIR shim control. A preliminary flowchart was drawn and some heat generation calculations in Zircaloy-2 and boric acid poison solution were made.
Date: December 15, 1959
Creator: McLain, H. I.
Partner: UNT Libraries Government Documents Department
open access

Containment Vessel Cost and Buckling Considerations

Description: The economics of various types of reactor containment are briefly discussed. Charts [?] suitable for feasibility cost estimates are presented for spherical and cylindrical pressure vessels. Approximate limitations on cylindrical pressure vessel height imposed by buckling considerations for snow, wind and vessel weight loads are also presented.
Date: September 15, 1959
Creator: Robinson, G. C.
Partner: UNT Libraries Government Documents Department
open access

Estimate of Potential Fuel Reprocessing, Revision #29 - Part A

Description: The power and estimated reprocessing load for existing and proposed United States and United States-built reactors of 10 Kw or greater thermal power.
Date: September 15, 1959
Creator: Ullmann, J. W.
Partner: UNT Libraries Government Documents Department
open access

PRFR Pilot Plant: An Evaluation of Equipment Performance During the Processing of Irradiated Natural Uranium in April 1959

Description: The Power Reactor Fuel Reprocessing complex and the equipment performance during the processing of irradiated natural uranium fuel are described. Equipment performance was generally satisfactory for rates up to 400 kg or uranium per day. =Three cases in which equipment malfunctioning significantly affected the process, and the scheduled modifications, are discussed.
Date: September 15, 1959
Creator: Matherne, J. L.
Partner: UNT Libraries Government Documents Department
open access

A Preliminary Study of the Dynamics of Solvent Extraction Cascades. I, Program for Digital and Analog Simulation

Description: Understanding of the dynamics of process systems usually leads to improved control. For systems of nuclear interest, the trend of improvement is likely to approach 'total automation' and computer control. To improve understanding of process dynamics in one specific field the present study is dealing with solvent extraction equipment. Specifically, mathematical models are being developed for applying both digital and analog computer to the transient behavior of extraction cascades.
Date: September 15, 1959
Creator: Updike, O. L. & Whatley, M. E. (Marvin E.), 1926-
Partner: UNT Libraries Government Documents Department
open access

Additional Information on Eurochemic Air Sampling System

Description: Additional information relative to the proposed Eurochemic Air Sampling System is given. The original questions are listed with the answers for convenience.
Date: September 15, 1959
Creator: Shank, E. M.
Partner: UNT Libraries Government Documents Department
open access

Induction Of Chemical Reactions In A High Frequency Discharge VII: Kinetics Of Carbon Dioxide Decomposition

Description: A simple system was selected for the study of electric discharges to bring about chemical changes in gases. Two such systems are N2-O2 and NH2. It is hoped that the present study will bring about a better understanding of these systems and add to a clarification of ideas and concepts with respect to the field of radiation chemistry.
Date: May 15, 1953
Creator: Wilde, Kenneth A., 1929-2017; Zwolinski, Bruno J., 1919-2010 & Parlin, Ransom B.
Partner: UNT Libraries Government Documents Department
open access

Report To The Atomic Energy Commission On The Van De Graaff Project No.AT-(40-1)-231 At The University Of Florida, Gainesville, Florida, March 15, 1953

Description: The scope of the project is the completion of the Van de Graaff electrostatic generator at the University of Florida, the construction of auxiliary equipment necessary in carrying out research with the generator, and the use of the generator and the auxiliary equipment for accurately measuring the elastic and inelastic scattering of protons and deuterons by various nuclei.
Date: March 15, 1953
Creator: Stanson, D. C.
Partner: UNT Libraries Government Documents Department
open access

A Stable Numerical Solution For Transient Heat Flow

Description: An implicit finite difference formula for the numerical integration of the heat conduction equation is described. It is shown to offer considerable saving in computing time compared to previously used methods for some types of problems.
Date: January 15, 1953
Creator: Leppert, George
Partner: UNT Libraries Government Documents Department
open access

Organic Coolant Reclamation. First Quarterly Progress Report for December 15, 1958 - March 15, 1959

Description: In research on developing a suitable method for organic coolant reclamation, several lines of attack are being followed simultaneously. Model compounds have been utilized in initial experiments. For the vapor phase hydrogenation-cracking study, apparatus has been constructed and several catalysts screened. A nickel on kieselguhr catalyst has been shown to be active in converting biphenyl to a mixture of benzene and toluene. Liquid phase hydrogenation techniques are under study for partial reduc… more
Date: April 15, 1959
Creator: Wineman, Robert J.; Gudzinowicz, Benjamin J.; Lopiekes, D. V. & Scola, D. A.
Partner: UNT Libraries Government Documents Department
open access

Radioactive Trash Disposal at Los Alamos

Description: This report will attempt to described the methods used at Los Alamos for the disposal of solid radioactive waste material. The principal contaminant is plutonium which is a long lived alpha emitter, because of the high toxicity of this element it is necessary to dispose of such contaminated trash by burial in disposal pits. Although the methods discussed in this report are felt to be adequate for low level alpha activity, a different approach tot he problem would have to b e taken if high level… more
Date: September 15, 1958
Creator: Enders, John W.
Partner: UNT Libraries Government Documents Department
open access

Cost of Containment Features for Boiling Water Reactors for Argonne National Laboratory

Description: An analysis of the cost of containment features for nuclear power plants utilizing boiling water reactors was made. The two plants chosen for comparison were the Experimental Boiling Water Reactor at ANL and a hypothetical large scale nuclear power plant with an electrical capacity of 180 Mw. In order that a cost analysis could be made for the plant designs general arrangement drawings were prepared for each of the alternate arrangements considered.
Date: October 15, 1957
Partner: UNT Libraries Government Documents Department
open access

Feasibility of Establishing a National Burial Ground for Radioactive Waste in the Northeastern United States

Description: A search has been made within a 125-mile radius of Erie, Pennsylvania, to discover a possible site for a national land burial ground to receive and bury low and intermediate level radioactively contaminated waste. The new burial facility would serve a sixteen state section of the northeastern United States. Estimated unit burial costs and computed transportation charges indicate that a centrally located site within the section is both feasible and desirable. It will be necessary to make complet… more
Date: July 15, 1956
Creator: Morgan, James M., Jr. (James Markus), 1923- & Renn, Charles E. (Charles Easterday), 1905-
Partner: UNT Libraries Government Documents Department
open access

Reactions of Metals with Oxygen and Steam. Final Report for June 15, 1958 - February 15, 1959

Description: Titanium, zirconium, and Zircaloy can spontaneously ignite under relatively mild conditions. The effect of temperature, oxygen concentration and pressure, and the nature of the diluent on the spontaneous ignition of titanium, zirconium, and Zircaloy were investigated.
Date: February 15, 1959
Creator: Littman, Fred E. & Church, Frank M.
Partner: UNT Libraries Government Documents Department
open access

Mass Transfer by High Temperature Liquid Sodium. Interim Progress Report 2

Description: Experiments were carried out in thermal convection loops in which sodium was induced by thermal convection to flow past a number of accurately weighed corrosion specimens located at close intervals throughout the entire temperature range existing within the loop. The specimens were accurately weighed prior to and following the test, and the weight changes were used as a measure of local mass transfer. Operating conditions, dimensions, materials, and temperature distributions are tabulated. (For… more
Date: October 15, 1958
Creator: Holman, W. R. (William Reid), 1918-
Partner: UNT Libraries Government Documents Department
open access

Heat Transfer from Spent Fuel and Blanket Subassemblies During Transfer from Reactor to Decay Storage Facility. Technical Memorandum No. 2

Description: During the transfer of spent fuel and blanket subassemblies from the reactor to the decay storage the subassemblies must be moved through an inert gas The heat generation due to the decay of fission is sufficiently large that provisions must be made for cooling the subassembly when in the gas The transfer equipment was designed for conduction radiation and natural convection cooling only. Various steps in the transfer process are explained and computations on heat generation and transfer are gi… more
Date: May 15, 1957
Creator: Kintner, L. L.
Partner: UNT Libraries Government Documents Department
open access

Relations Governing Low Cycle Fatigue : a Summary of the Pertinent Literature

Description: The information available to date on low-cycle fatigue, resulting from either repeated mechanical straining (strain cycling) or from repeated temperature changes under restraint (thermal cycling and thermal shock), their relation to static and conventional fatigue properties, and their fundamental significance is assembled. In spite of the small amount of data accumulated on the effects of the numerous variables involved in low-cycle fatigue these data appear to conform to certain significant r… more
Date: May 15, 1958
Creator: Sachs, George, 1896-1960 & Taber, A. P.
Partner: UNT Libraries Government Documents Department
open access

Velocity and Temperature Distributions About a Horizontal Cylinder in Free Convection Heat Transfer : Final Report

Description: Measurements were made at one set of conditions of the velocity and temperature distributions about a singe, one-inch diameter, cooled horizontal cylinder immersed in a volume-heated liquid. The results, when expressed on a dimensionless basis recommended by Hermann, were in good agreement with predictions based on vertical plated geometry.
Date: September 15, 1958
Creator: Sesonske, Alexander, 1921-
Partner: UNT Libraries Government Documents Department
Back to Top of Screen