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STAINLESS STEEL WASTES. III. LABORATORY STUDIES OF THE RATE OF REMOVAL OF STAINLESS STEEL IONS BY MERCURY CATHODE ELECTROLYSIS (open access)

STAINLESS STEEL WASTES. III. LABORATORY STUDIES OF THE RATE OF REMOVAL OF STAINLESS STEEL IONS BY MERCURY CATHODE ELECTROLYSIS

ABS> The removal rates of iron, nickel, and chromium from synthetic stainless steel waste solutions during electrolysis over a mercury cathode were studied. The loading capacity of the mercury for the stainless steel metals was estimated on the basis of laboratory experiments to be about two% by weight. The laboratory data indicated that, at an electrode potential of --1.80 voits vs S.C.E., 85 ampere-hours per liter of waste removed essentially all of the stainless steel ions from a sulfuric acid solution containing 0.13M metal ions at 35 deg C. (auth)
Date: February 12, 1962
Creator: Anderson, D. R. & Rhodes, D. W.
Object Type: Report
System: The UNT Digital Library
Thermonuclear Division Semiannual Progress Report for Period Ending April 30, 1962 (open access)

Thermonuclear Division Semiannual Progress Report for Period Ending April 30, 1962

Progress is reported on thermonuclear research. Separate abstracts were prepared for 8 of the 10 sections. Design and engineering service reports and notes are given in the remaining sections. (M.C.G.)
Date: September 12, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
National Welfare Standard--Problems and Proposals (open access)

National Welfare Standard--Problems and Proposals

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.
Object Type: Report
System: The UNT Digital Library
The Seniority System in Congress: A Selected Bibliography (open access)

The Seniority System in Congress: A Selected Bibliography

This report provides a bibliography of resources related to the seniority system in Congress.
Date: November 12, 1969
Creator: Kravitiz, Walter
Object Type: Report
System: The UNT Digital Library
[News Script: Art] (open access)

[News Script: Art]

Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date: December 12, 1968
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Object Type: Script
System: The UNT Digital Library
[News Script: Callas] (open access)

[News Script: Callas]

Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date: September 12, 1968
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Object Type: Script
System: The UNT Digital Library
[News Script: Arthritis award] (open access)

[News Script: Arthritis award]

Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date: December 12, 1968
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Object Type: Script
System: The UNT Digital Library
[News Script: Heart] (open access)

[News Script: Heart]

Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date: December 12, 1968
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Object Type: Script
System: The UNT Digital Library
[News Script: Leonards] (open access)

[News Script: Leonards]

Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date: November 12, 1968
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Object Type: Script
System: The UNT Digital Library
Propane Vibrational Analysis (open access)

Propane Vibrational Analysis

Using the group vibratibn method of McMurry, the normal frequencies and coordinates of propane and three of its symmetrical deuterium substituted compounds were obtained. The force constants used were taken from a variety of previous works on hydrocarbons. The results give reasonable agreements with the experimental frequency and mode assignments of others. (auth)
Date: June 12, 1962
Creator: Marshall, G. D.
Object Type: Report
System: The UNT Digital Library
Primary Plant Self-Actuated Relief Valve Operation. Core I, Seed 3. Test Evaluation. Section 2 (open access)

Primary Plant Self-Actuated Relief Valve Operation. Core I, Seed 3. Test Evaluation. Section 2

A test was conducted on August 12 to 13, l961, on the operation of the four reactor coolant loop relief valves and the four purification system relief valves. The results indicated proper operation. (D.L.C.)
Date: January 12, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
HRT-CHEMICAL PLANT RUN 21 SUMMARY (open access)

HRT-CHEMICAL PLANT RUN 21 SUMMARY

The multiple hydroclone system removed l83 grams of corrosion product solids in l814 hours of operation during reactor run 2l. The low removal rate was attributed to plugging of multiclone feed ports that presumably occurred during the latter part of run 20. After modifications to the reactor core and removal of the multiclone unit at the end of run 21, the reactor core was backflushed with the flow direction in the core loop reversed. During this period, the single hydroclone removed 205 grams of solids in 10.5 hours of operation. (auth)
Date: February 12, 1962
Creator: Yarbro, O.O.
Object Type: Report
System: The UNT Digital Library
GETTING MULTICHANNEL ANALYZER DATA IN AND OUT OF THE IBM-7090 FOR PROCESSING (open access)

GETTING MULTICHANNEL ANALYZER DATA IN AND OUT OF THE IBM-7090 FOR PROCESSING

The present method used for handling multichannelanalyzer data at the ORNL 86-Inch Cyclotron is stated. FORTRAN subroutines for reading the analyzer data into the IBM-7090 computer and for printing out the processed data and punching processed data on cards are presented. (auth)
Date: December 12, 1961
Creator: Goodman, C. D.
Object Type: Report
System: The UNT Digital Library
SNAP 2 PRIMARY SYSTEM TEST-OBJECTIVES, SYSTEM DESCRIPTION, AND PROCEDURES (open access)

SNAP 2 PRIMARY SYSTEM TEST-OBJECTIVES, SYSTEM DESCRIPTION, AND PROCEDURES

The SNAP-2 Primary System Test loop fabrication was completed with associated flight prototype components including reactor core and boiler mockups for volume and DELTA P simulation, CRU-IIII NaK pump, compact heater, and expansion compensator. A mobile loading system was designed and fabricated with the capability of cleaning the NaK prior to final loop sealing. Loop descriptions, test objectives, and operating procedures are presented. (auth)
Date: June 12, 1961
Creator: Kikin, G.M.
Object Type: Report
System: The UNT Digital Library
PRELIMINARY DESIGN OF A HYDROGEN-COOLED IN-PILE LOOP FOR THE EGCR (open access)

PRELIMINARY DESIGN OF A HYDROGEN-COOLED IN-PILE LOOP FOR THE EGCR

A discussion is presented concerning the preliminary design and hazards evaluation of a H-cooled in-pile experimental loop for operation in the large double-walled through-tube in the Experimental Gas-Cooled Reactor (EGCR) at Oak Ridge. This loop is designed to permit experimentation with full-scale fuel element configurations up to 8 in. OD, at inlet gas temperatures of 600 to 950 deg F at 300 psig, and experimental power levels up to 500 kw. The results of a preliminary hazards evaluation indicate that a loop of this type can be safely operated in the EGCR. The H flammability hazard is controlled by blanketing all H-filled pipes and components with a sufficient quantity of nonreactive gas, such as He or CO/ sup 2/, to produce a noncombustible mixture for all credible H- release situations. (auth)
Date: July 12, 1962
Creator: Michelson, C.; Culp, A.W. & Neill, F.H.
Object Type: Report
System: The UNT Digital Library
COOLING OF THE HFIR BERYLLIUM REFLECTOR FOLLOWING A REACTOR SCRAM OR AN ELECTRICAL POWER OUTAGE (open access)

COOLING OF THE HFIR BERYLLIUM REFLECTOR FOLLOWING A REACTOR SCRAM OR AN ELECTRICAL POWER OUTAGE

Thermal stresses in the HFIR beryllium reflector were computed for the unlikely case where the reactor is scrammed with a simultaneous loss of coolant flow and for the case following an electrical power outage where the reactor power level and the coolant flow rate are reduced simultaneously. For the case where the reactor is scrammed with a sudden loss of the coolant flow, the resulting maximum tensile thermal stress following the scram is 22,500 psi. In case of an electrical power outage, the maximum tensile thermal stress following a reduction of the fission power level from 100 Mw to 10 Mw with the lowering of the coolant flow rate to 10% of the normal value is 12,800 psi. (auth)
Date: December 12, 1961
Creator: McLain, H. A.
Object Type: Report
System: The UNT Digital Library
An Investigation of the Corrosion Resistance of Brazing Alloys for Austenitic Stainless Steel Fuel Elements for Service in 565 F Pressurized Water (open access)

An Investigation of the Corrosion Resistance of Brazing Alloys for Austenitic Stainless Steel Fuel Elements for Service in 565 F Pressurized Water

Since brazing was the method selected for joining the stainless steel SM- l reactor fuel element, corrosion studies were conducted on various potential brazing alloys to evaluate their resistance under the approximate pressurized- water conditions of the SM-1. The program consisted mainly of testing type 304L stainless steel T'' joints brazed with selected alloys in quiescent, degassed, and deionized autoclaved water at 565 deg F under 1200-psi pressure. In the initial phase of the investigation, tests were limited in duration to l000 hr in order to quickly screen some 18 potential alloys for longer time testing. Based on weight-change data and the metallographic examinations, five of the 18 alloys exhibited sufficient corrosion resistance to warrant further investigation. These alloys were subjected to autoclave tests of 12 and 16 months. In these extended tests, 1 cc O/sub 2/liter and a mixture of 1 cc O/sub 2/liter plus 50 cc H/sub 2/liter, respectively, were added to the water to more closely simulate SM- 1 reactor water conditions and to evaluate the effect of different gaseous additions on the corrosion behavior of the alloys. On the basis of weight-change data and metallographic examination after long-term exposure of the tested stainless steel-base joint; these …
Date: April 12, 1962
Creator: Beaver, R. J.; Leitten, C. F. Jr. & English, J. L.
Object Type: Report
System: The UNT Digital Library

[Photograph 2012.201.B0229.0423]

Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "Eddie Coast, 15-year-old Marlow High School student, receives a pin marking him as the winner of a "greenhand quiz" at a district Future Farmers of America leadership training conference in Waurika."
Date: December 12, 1969
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0235.0553]

Photograph taken for a story in the Oklahoma Times newspaper. Caption: "Police technician Doyle Connelly picks up pellet gun, apparently discarded by robbers."
Date: December 12, 1964
Creator: Taylor, Jack
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0292.0174]

Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "William Dauer, executive vice president and general manager of the Chamber of Commerce of Kansas City, " Metropolitan Approach,"."
Date: November 12, 1963
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0294.0094]

Photograph taken for a story in the Oklahoma Times newspaper.
Date: August 12, 1969
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0316.0564]

Photograph taken for a newspaper owned by the Oklahoma Publishing Company.
Date: August 12, 1968
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0245.0196]

Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "Mayan rain god held by F. Dale Crabtree, right in lower photo, distracts Mrs. Paul Peterson and Thomas Harrison from their own interests."
Date: August 12, 1964
Creator: Miller, Joe
Object Type: Photograph
System: The Gateway to Oklahoma History

[BOX 67.0397]

Photograph is of two firemen controlling a fire hose that is spraying on a structure completely engulfed in flames from the inside and through the roof. Photograph was taken in the night time. Caption: "Are believed responsible for two weekend fires at the Goodland Indian Orphanage campus four miles southwest of Hugo."
Date: April 12, 1960
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History