UNT Libraries Government Documents Department - 14 Matching Results

Search Results

Results: 1 - 14
open access

04 nuclear safety: pressure piping crack monitoring detection of metal overstress by acoustic emission. Progress report, July-September 1966

Description: The three main areas of effort have been: (1) definition of the general acoustic response pattern related to the gross aspects of forming and extending a crack in various materials, (2) development of a monitor system prototype concept exclusive of transducers and (3) development of a suitable, high temperature transducer. Tests using double cantilever beam (DCB) specimens of various materials to establish conditions of crack formation and growth have indicated that material ductility is a majo… more
Date: October 28, 1966
Creator: Hutton, P H
Item Type: Refine your search to only Report
open access

9-ANGIE : a Two-Dimensional, Multigroup, Neutron-Diffusion-Theory Reactor Code for the IBM 709 or 7090

Description: The 9-ANGIE, one of a series of reactor neutronic programs for an IBM 709 or 7090 data processing system, solves the time-dependent, multi-group, neutron diffusion equation for one to eighteen energy groups applied to a rectangular mesh superimposed on either an x-y or an r-z plane. It is characterized by its generalities in region description, boundary conditions, etc., without sacrificing simplicity of input preparation and ease of machine operation. The notation, the style, and the format ha… more
Date: October 28, 1960
Creator: Stone, Stuart P.
Item Type: Refine your search to only Report
open access

Determination of Interstitial Solid-Solubility Limit in Tantalum and Identification of the Precipitate Phases

Description: Solid-solubility limits at 1500, 1000, snd 500/sup o/C for carbon, nitrogen, and oxygen in high-punity tantalum were determined by x-ray lattice- parameter methods. For carbon, the solubility was found to be 0.17 at. % at 1500/sup o/C and less than 0.07 at. % at l00/sup o/C. A nitrogen solubility of 3.70 at. % at l500/sup o/C decreased linearly with temperature to 2.75 at. % at 1000/sup o/C and 1.8 at. % at 500/sup o/C. In the case of oxygen, the solubility was found to be 3.65 at. % at 1500/su… more
Date: October 28, 1960
Creator: Vaughan, D.A.; Stewart, O.M. & Schwartz, C.M.
Item Type: Refine your search to only Report
open access

Expansion to 4.0 capacity factor: Purex Engineering Study

Description: The Purex Plant was originally designed to operate at a instantaneous rate of 8-1/3 tons of uranium per 24-hour day on a three-cycle flowsheet. Subsequently, the rate was increased to 26-2/3 T/day and the process changed to a two-cycle flowsheet. Recently, flowsheet changes made for neptunium recovery and replacements of certain critical equipment items have altered the plant`s capacity. The status of the plant is discussed in the Continuity of Operations, Plant Improvement Program, Reference 1… more
Date: October 28, 1960
Creator: Doud, E.
Item Type: Refine your search to only Report
open access

Internal graphite moderator forces study, C and K Reactors

Description: The purpose of this study was to determine the maximum forces that can be imposed by the graphite moderator on prospective VSR channel sleeves. In order to do this, both the origins and modes of transmission of the forces were determined. Forces in the moderator stack that are capable of acting on a block or group of blocks may originate from any of the following primary effects: Contraction of graphite due to irradiation; thermal expansion of graphite; frictional resistance to motion; resistan… more
Date: October 28, 1963
Creator: Cooley, D. E.
Item Type: Refine your search to only Report
open access

Reduction of Plutonium (VI) to Plutonium(III) and (IV) by Sodium Nitrite

Description: The use of anion exchange for final Pu purification in the Redox facility requires the adjustment of Pa(VI) to Pu(IV). Two methods of reduction were investigated: ferrous sulfamate and nitrite. The ferrous sulfamate method was adopted. Data on reduction of Pu(VI) to Pu(IV) and Pu(III) by nitrite are presented. The reduction by nitrite was found to be dependent on nitrite concentration, temperature, acidity, ferric ion concentration, and time, and it is possible to obtain >90% reduction to Pu… more
Date: October 28, 1963
Creator: Colvin, C. A.
Item Type: Refine your search to only Report
open access

SM-2 SINGLE ELEMENT FINAL TEST REPORT

Description: Tests were conducted on an SM-2 control-rod assembly and stationary element to determine channel-to-channel coolant flow distribution and static pressure drops across both the control-rod assembly and stationary element, and to select proper top and bottom core support configurations necessary to bring stationary element channel-to-channel flow distribution within prescribed limits of plus or minus 6% of element average. Results showed control-rod channel-to- channel flow distribution was +7.0%… more
Date: October 28, 1960
Creator: Krause, P.S.
Item Type: Refine your search to only Report
open access

Structural Response and Permanent Displacement Measurements

Description: Measurements and visual observations made during the Hardtack II series of underground shots provide basis for conclusions regarding shock-resistant design of protection for cavities in rock and qualitative prediction of permanent displacements in rock due to nuclear detonations. Vibration measurements on blast-resistant construction in soil provided non-nuclear test results which apply to shock resistant design. With varying soil cover, the compressive mode predominated in arch structures and … more
Date: October 28, 1960
Creator: Sievers, R. H., Jr. & Stacy, A. R.
Item Type: Refine your search to only Report
Back to Top of Screen