42 Matching Results

Search Results

Results: 1 - 24 next
open access

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: August 15, 1963
Creator: Leitz, F. J.
Partner: UNT Libraries Government Documents Department
open access

In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C

Description: Report presenting in-pile loop experiments DD, EE, FF, GG, L-412, L-413, and L-418, which were seven of a series designed to test the radiation corrosion of zirconium, titanium, and stainless steel alloys in solutions under various conditions of radiation intensity, temperature, solution composition, and velocity of flow. Steel specimens exposed in the loop cores showed increases in corrosive attack over that expected out-of-radiation.
Date: August 15, 1963
Creator: Jenks, G. H. & Baker, J. E.
Partner: UNT Libraries Government Documents Department
open access

Nuclear Superheat Quarterly Project Report: Thirteenth Quarter, July-September 1962

Description: From introduction: "This is the thirteenth in a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: May 15, 1963
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
open access

Nuclear Superheat Quarterly Project Report: Fourteenth Quarter, October-December 1962

Description: From introduction: "This is the fourteenth in a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: January 15, 1963
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
open access

Oak Ridge National Laboratory Target Preparation Program

Description: In early 1961 a Target Fabrication Center was established at Oak Ridge National Laboratory to carry out the routine preparation of a wide variety of targets and to provide research and development support to the target program. Although most of the effort concerned enriched stable isotopes, both normal and radioactive materials are also handled. With the aid of rolling mills, resistance-heat and electron-bombardment vacuum evaporation, presses, and electroplating equipment, targets of elements … more
Date: January 15, 1963
Creator: Kobisk , E. H
Partner: UNT Libraries Government Documents Department
open access

Progress Report for February-March 1961 - Chemical Development Section C, Chemical Technology Division

Description: This report summarizes certain activities by the Oak Ridge National Laboratory's Chemical Technology Division, which focused on chemical separation processes relevant to nuclear fuel reprocessing, from February to March 1961. It includes data from experiments exploring the recovery of thorium and uranium from granitic rock, fission product (cesium) recovery, final cycle plutonium recovery by amine extraction, and the separation of transplutoniums from lanthanides.
Date: August 15, 1961
Creator: Brown, K.B.
Partner: UNT Libraries Government Documents Department
open access

Preprocessing of Procedure in the ORACLE-Algol Translator

Description: This report describes the preprocessing stage to be added to the present ORACLE-Algol translator which will enable it to translate programs containing procedures. The Algol 60 procedure is an extremely flexible tool, and its full implementation presents a number of difficulties. Since it is undesirable to undertake major revisions of the existing parts of the translator and impossible to solve all of these difficulties in a processing stage, it was necessary to impose certain restrictions on th… more
Date: May 15, 1961
Creator: Bumgarner, L. L.
Partner: UNT Libraries Government Documents Department
open access

CANE Sequenced Sampler for Project Gnome: Design Proposal

Description: A design is proposed for sampling apparatus to draw a sequence of samples from a filtered gas stream from a contained explosion. The apparatus is to be designed, fabricated, and installed in Project Gnome under the ORNL CANE Problem.
Date: March 15, 1961
Creator: Landry, J.W.
Partner: UNT Libraries Government Documents Department
open access

Calculated Thermal Ionization And Enthalpy of Hydrogen, Nitrogen, And Argon At One Atmosphere Pressure In The 298-20, 000'K Temperature Range

Description: The degree of dissociation and ionization and the enthalpies of hydrogen and nitrogen, and the degree of ionization and the enthalpy of argon are calculated for one atmosphere pressure and temperatures up to 20,000'K. All three gases are more than 93% ionized at 20,000'K, and have enthalpies ranging from 553 kcals for argon to 1074 and 1225 kcals, respectively, for hydrogen and nitrogen.
Date: September 15, 1960
Creator: Bond, Walter Dayton
Partner: UNT Libraries Government Documents Department
open access

Momentum and Heat Transfer to a Fluid Flowing Turbulently in a Pipe

Description: A mathematical model is presented for the prediction of heat transfer coefficients for fully developed turbulent flow of fluids in circular pipes by analogy to the transfer of momentum. There is also presented an empirical velocity distribution equation derived from existing experimental data for use in the analogy model. Heat transfer coefficients for fluids with Prandtl numbers ranging from 0.01 to 100 and Reynolds numbers ranging from 5x10^3 to 10^7 are presented in tabular and graphical for… more
Date: September 15, 1960
Creator: Hefner, R. J.
Partner: UNT Libraries Government Documents Department
open access

Estimate Of Potential Fuel Reprocessing, Revision #30 Part A

Description: The power and estimated reprocessing load are tabulated for existing and proposed for United States and United States-built reactors of 10 Kw or greater thermal power.
Date: March 15, 1960
Creator: Ullmann, J. W.
Partner: UNT Libraries Government Documents Department
open access

High Flux Isotope Reactor: a General Description

Description: Current status of the High Flux Isotope Reactor which is being planned for construction at Oak Ridge.
Date: March 15, 1960
Creator: Cole, T. E.
Partner: UNT Libraries Government Documents Department
open access

High Flux Isotope Reactor - A General Description

Description: This report is issued primarily to make available a general description which reflects the current status of the High Flux Isotope Reactor which is being planned for construction at Oak Ridge National Laboratory.
Date: March 15, 1960
Creator: Cole, T. E.
Partner: UNT Libraries Government Documents Department
open access

Natural Circulation Burn Out Heat Flux For The ORR

Description: Natural circulation flow rate is calculated for the ORR core. From this flow rate, the burn out heat flux is found to be between 22,000 and 35,000 Btu/ft2-hr. It is concluded that under present conditions a positive acting after heat removal system is necessary for 30 mw operation.
Date: February 15, 1960
Creator: Wett, J. F.
Partner: UNT Libraries Government Documents Department
open access

Nuclear Characteristics of BeO-Moderated Cores vs Graphite-Moderated Cores

Description: Multigroup calculations were performed to compare BeO-moderated cores, using various void fractions and core diameters. The core leakages and conversion ratios which were calculated are presented in a series of curves.
Date: January 15, 1960
Creator: Carlsmith, R. S.
Partner: UNT Libraries Government Documents Department
open access

Results of Differential Bed Study of the Kinetics of the Absorption of UF6 on Sodium Fluoride

Description: One step in the Volatility process for power reactor fuel reprocessing involves the absorption and subsequent desorption of UF6 from NaF pellets in fixed beds. In 1958 an experimental study of the kinetics of absorption of HF on NaF beds was made. The purpose of this work was to extend the study to the kinetics of UF6 absorption on NaF. The results should be useful in the design and operation of the Volatility process.
Date: January 15, 1960
Creator: Groves, F. R.
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

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

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

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
Back to Top of Screen