74 Matching Results

Search Results

prev Results: 49 - 72 next
open access

Snap-8 Corrosion Program Quarterly Progress Report for Period Ending November 30, 1964

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Snap-8 Corrosion Program. Progress in design, operation, and experimental work is presented. This report includes tables, illustrations, and photographs.
Date: March 1965
Creator: Savage, H. W.; Compere, E. L.; MacPherson, R. E.; Huntley, W. R. & Taboada, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High-Density Concrete for Gamma and Neutron Attenuation

Description: Report issued by the Oak Ridge National Laboratory discussing the development of a high-density concrete. As stated in the abstract, "the basic approach to high-density concrete mix design is reviewed to show that theoretical calculations for concrete mixes do give results that are reliable" (p. 1). This report includes tables, illustrations, and photographs.
Date: March 1965
Creator: Northup, T. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Halogen Collector Test Program

Description: Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date: March 1, 1960
Creator: Arthur D. Little, Inc.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation of an Engineering Demonstration of the Modified Zirflex and Neuflex Processes for the Preparation of Solvent Extraction Feeds from Unirradiated Zirconium-Base Reactor Fuels

Description: Report that investigates the concept of using ammonium fluoride-oxidant systems to dissolve spent U-Zr-Sn reactor fuels in both batch and continuous operation.
Date: March 1964
Creator: Kitts, F. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Lecture Notes on Reactor Shielding

Description: Report issued by the Argonne National Laboratory discussing the shielding of radiation produced by nuclear reactors. As stated in the introduction, "these lectures will be an attempt to discuss the design of a reactor shield and the solution of the associated shielding problems by simple hand-computing methods" (p. 19). This report includes tables, and illustrations.
Date: March 1959
Creator: Grotenhuis, Marshall
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Report on Some Attempts to Cast Centrifugally Fuel Elements of Small Diameter

Description: Report issued by the Argonne national Laboratory discussing centrifugal casting of thin uranium plates. The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated. This report includes tables, illustrations, and photographs.
Date: March 1961
Creator: Yaggee, F. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design and Testing of a High-Heat Flux Electron-Bombardment Heater

Description: Report issued by the Argonne National Laboratory discussing the testing of an electron-bombardment heater. As stated in the abstract, "the applications of electron-bombardment heating to liquid-metal heat transfer and reactor safety experiments are discussed. The design of a high-heat-flux, electron-bombardment heater (EBH) is presented" (p. 7). This report includes tables, illustrations, and photographs.
Date: March 1968
Creator: Carlson, R. D. & Holtz, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Proposal for an Advanced Engineering Test Reactor : ETR II

Description: Report containing "the results of a study which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR or in existing commercial test reactors" (p. 5).
Date: March 17, 1960
Creator: deBoisblanc, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Savannah River Project Site Report: 30,000 KW Prototype Partically Enriched Uranium Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission Idaho Operations Office

Description: Report describing a modified prototype of a nuclear reactor that uses partially uranium-enriched fuel and is cooled by helium. The construction site, site safety aspects, and design and construction costs are included.
Date: March 1959
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary Design 30,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype of an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office contract no. AT(10-1)-925

Description: Report containing the preliminary design for a nuclear reactor plant and its facilities. Includes a description of systems, safety procedures, costs, and a glossary.
Date: March 1959
Creator: Kaiser Engineers
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Summary Report of Analysis of Physics Measurements Performed on SM-1 Core I

Description: Abstract: This technical report contains a comprehensive analysis of the nuclear characteristics of the SM-1 Core I. Comparison of analytical and experimental results for neutron ages and core reactivities of a variety of cases investigated shows that the MUFT III with P-1 slowing down approximation gives the best results. At startup the core reactivity and rod bank worth under various operating conditions are investigated and compared to experiment. Core lifetime was calculated to be 16.8 MWYR… more
Date: March 30, 1962
Creator: Lois, L.; Paluszkiewicz, S.; Fried, B. E. & Beam, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen