Search Results

open access

Sensitivity to VSR failure: K pipe break accident

Description: Reactor effects of failure of a safety rod to scram can be considered in two major respects: The reduction in total safety system strength which will affect the amount of ``prompt drop`` and subsequent flux decay rate of the average neutron flux-level; and the change in local flux distribution due to the absence of the particular rod which fails to enter the reactor. The purpose of this memorandum is to describe the physical effects involved and to indicate the approximate magnitude of both reactor-wide and localized changes in event of failure of a VSR simultaneous with a K Reactor riser accident.
Date: September 12, 1969
Creator: Meichle, R. H.
Partner: UNT Libraries Government Documents Department
open access

Consistent Properties of Composite Formation Under a Binary Relation

Description: In this paper we study the properties of a relation, H, between two sets, X and Y, H ⊆ X x Y. We wish to determine when the existence of H between some elements of X and Y implies the existence of H between other composite elements of X and Y. The aim is to characterize a relation by its extension or restriction to composite elements.
Date: August 12, 1969
Creator: Schwebel, John C & McCormick, Bruce H
Partner: UNT Libraries Government Documents Department
open access

National Welfare Standard--Problems and Proposals

Description: This report attempts to present some of the factors which must be examined and the issues which must be decided in considering a proposal for national welfare standard, as well as a summary of the arguments which can be made for and against the adoption of national standard.
Date: February 12, 1969
Creator: Fullerton, William D.
Partner: UNT Libraries Government Documents Department
open access

Nonuniform Aluminum Corrosion Program

Description: The purpose of this document is to summarize the status of the current non-uniform aluminum corrosion program. Also included are justifications for and descriptions of program activities which could continue through FY-1971.
Date: February 12, 1969
Creator: Sheppard, D. O. & Larrick, A. P.
Partner: UNT Libraries Government Documents Department
open access

FAST FLUX TEST FACILITY CONCEPTUAL FACILTY DESIGN DESCRIPTION FOR THE INERT GAS CELL EXAMINATION FACILITY NO. 71

Description: The purpose of this Conceptual Facility Design Description (CFDD) is to provide a technical description of the Inert Gas Cell Examination Facility such that agreement with RDT on a Conceptual Design can be reached . The CFDD also serves to establish a common understanding of the facility concept among all responsible FFTF Project parties including the Architect Engineer and Reactor Designer. Included are functions and design requirements, a physical description of the facility, safety considerations, principles of operation, and maintenance principles.
Date: December 12, 1968
Partner: UNT Libraries Government Documents Department
open access

Hanford isotope production capabilities for single pass reactors

Description: This report is a summary of several studies made by the author during 1967, and early 1968, while providing technical assistance to the Advanced Concepts and Planning Section. An attempt has been made to reduce the data to a usable form which will enable the reader to estimate the production of a particular isotope and the production of weapons grade plutonium that accompanies the co-product loading for different Uranium-235 concentrations of the driver fuels. It should be emphasized that the production data shown in this document do not constitute an engineering study of the loading. As the safety analysis has not been performed and only minimal hydrokinetics have been studied, it is imperative that the use of the data contained in this report be used only for planning and estimating work. if any particular loading were to become a reality, a detailed engineering study would be required for that loading. Although the B Reactor has been deactivated it is included in the report along with the C and K Reactors. Hence, it is possible to make estimates of the capabilities of the entire Hanford single pass reactor complex. Although Oralloy fuel for the Hanford reactors for isotope production has not been fully developed, there are several cases included for each isotope. If the state of the art is advanced in the future these preliminary calculations could possibly serve as a base point.
Date: December 12, 1968
Creator: Miller, R. L.
Partner: UNT Libraries Government Documents Department
open access

Roundness of Molded Detonator Heads

Description: The magnitude of the deviations from roundness of molded detonator heads, caused by the geometry of the part and by different materials, was investigated to provide a scientific basis which can be used to predict dimensions and tolerances of size and roundness for new heads. Injection presses were used to mold detonator heads to precision tolerances. Twenty parts were molded under optimum conditions in two different molds using both DAP filled with long glass fibers and DAP filled with asbestos. Each of the parts was analyzed for size and roundness, and the data were analyzed statistically. The results indicate: 1. Geometry is highly significant. 2. Material is highly significant. 3. Geometry and material do not interact. 4. Geometry affects magnitude of deviation from roundness. 5. Geometry affects magnitude of shrinkage.
Date: December 12, 1968
Creator: Wendeln, D. E. & Waldfogle, E. A.
Partner: UNT Libraries Government Documents Department
open access

HAPO tritium production facilities study - 1958 - study reports numbers 1 and 2

Description: Start of the development of new processes to extract mint can be a gradual program. The most promising of early results lies in the area of Isotopic Purification. Steps have been initiated to start development work on separation and purification of mint gas by chromatography. This method has the added advantage over columns as three gases, hydrogen, deuterium and mint may be separated in one operation. Should it appear that this method may fail, a second approach would be development of a packed column. Even with a change of the basic extraction process, isotopic purification is required and the improvement of such facilities would serve to provide the product at a reduced initial capital cost as well as reduced extraction cost. Work can proceed at the same time with development of a dissolution process. As noted in Appendix I, a unit extraction savings in the order of 20 percent can be expected since, in the most simple form, expensive furnace pots would be replaced by inexpensive crucibles.
Date: November 12, 1968
Creator: Kesel, G. P.; Koontz, W. H.; Smiset, O. V. & Denollander, W. R.
Partner: UNT Libraries Government Documents Department
open access

Compact thermoelectric converter. Quarterly progress report, July 1, 1968- -September 30, 1968. Phase II-C

Description: Declassified 30 Aug 1973. An initial analysis of experimental heatup data was compiled to determine the success of module experiments designed to triple the voltage power ratio of standard TEM-9 modules. Accomplishment of this design improvement is extremely significant in the development of tabular module systems having lower power applications. With the increased voltage to power ratio, power conditioning devices will not be required to step up the module output voltage to a more usable level. Heatup data from TEM9AE S/N-1, employing 0.030-inch lead telluride washers and 0.0015-inch mica insulators, correlate very closely with performance calculations. A study was initiated to determine an optimum design for a module to be internally fueled using cobalt60. In addition, alterations to the calculation model TEMOD were made to handle the effects of gamma heating within the lead telluride washers. An experimental test program was defined which would verify the validity of the mathematical model. Additional analytical work was accomplished to correlate predicted axial heat transport rates of heat pipes with experimental data. A study of sodium heat pipe performance data revealed that a sonic vapor velocity can occur in the region between evaporator and condensor sections of the heat pipe to produce a limit to the axial heat transfer rate. Evaluation of niobium contacts show them to be considerably more compatible with p-type lead telluride than iron contacts. However, the niobium does not yield absolute electrical stability and, as a result, no further work beyond the present analysis is contemplated. Six modules containing solid tungsten conductors were placed on test at elevated temperatures. Although degradation rates measured were the lowest yet recorded for modules employing TEGS-2P material, for temperatures above 1100 deg F the most stable operation is achieved through the substitution of TEGS-3P.material for TEGS-2P material. (auth)
Date: October 12, 1968
Partner: UNT Libraries Government Documents Department
open access

Production test authorization 145 loading adjustment to increase spectrometer utilization

Description: The objective of the test described in this report is to authorize loading KE Reactor tubes 4396, 4397, 4398, 4496, 4497, 4498, 4596, 4597, and 4598 with 0.947 enriched fuel in support of the X-2 level Battelle Northwest neutron spectrometer, when the spectrometer will be in use.
Date: June 12, 1968
Creator: Guthrie, G.D.
Partner: UNT Libraries Government Documents Department
open access

C Reactor fuel failures tubes 2562 and 3361

Description: C Reactor experienced two severe fuel failures, one in process tube 2562 on 10-27-67, and one in process tube 3361 on 12-27-67, both resulting in major efforts to effect their removal. The intent of this document is to present a summary of the action taken for the removal of the failed elements.
Date: April 12, 1968
Creator: Marx, E. R.
Partner: UNT Libraries Government Documents Department
open access

Marihuana: Derivation, Use, And Effects

Description: This report is about derivation, usage, effects of Marihuana.
Date: April 12, 1968
Creator: Hogan, Harry
Partner: UNT Libraries Government Documents Department
open access

Dissolver operation and metal transfer

Description: This report provides data on daily dissolver operation and metal transfers. Sodium hydroxide and sodium nitrate requirements are also given.
Date: October 12, 1967
Creator: Beaulieu, O. F.
Partner: UNT Libraries Government Documents Department
open access

Status of special reactor-process tube loadings, July 1, 1967

Description: The attached pages show that status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials. For further description of column headings and the current discharge goal exposure plan refer to Document DUN-1048.
Date: July 12, 1967
Creator: Walton, R. P.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen