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HRT-CHEMICAL PLANT RUN 21 SUMMARY

Description: 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… more
Date: February 12, 1962
Creator: Yarbro, O.O.
Partner: UNT Libraries Government Documents Department
open access

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

Description: 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 investigatio… more
Date: April 12, 1962
Creator: Beaver, R. J.; Leitten, C. F. Jr. & English, J. L.
Partner: UNT Libraries Government Documents Department
open access

Summary report for 1990 inservice inspection (ISI) of SRS 100-L reactor tank

Description: The integrity of the SRS reactor tanks is a key factor affecting their suitability for continued service since, unlike the external piping system and components, the tanks are virtually irreplaceable. Cracking in various areas of the process water piping systems has occurred beginning in about 1960 as a result of several degradation mechanisms, chiefly intergranular stress corrosion cracking (IGSCC) and chloride-induced transgranular cracking. The primary objective of this inspection was to det… more
Date: July 12, 1991
Creator: Morrison, J. M. & Loibl, M. W.
Partner: UNT Libraries Government Documents Department
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Oxidation of alloys targeted for advanced steam turbines

Description: Ultra supercritical (USC) power plants offer the promise of higher efficiencies and lower emissions. Current goals of the U.S. Department of Energy’s Advanced Power Systems Initiatives include coal generation at 60% efficiency, which would require steam temperatures of up to 760°C. This research examines the steamside oxidation of alloys for use in USC systems, with emphasis placed on applications in high- and intermediate-pressure turbines.
Date: March 12, 2006
Creator: Holcomb, G. R.; Covino, B. S., Jr.; Bullard, S. J.; Ziomek-Moroz, M. & Alman, D. E.
Partner: UNT Libraries Government Documents Department
open access

LIFE ESTIMATION OF HIGH LEVEL WASTE TANK STEEL FOR F-TANK FARM CLOSURE PERFORMANCE ASSESSMENT - 9310

Description: High level radioactive waste (HLW) is stored in underground carbon steel storage tanks at the Savannah River Site. The underground tanks will be closed by removing the bulk of the waste, chemical cleaning, heel removal, stabilizing remaining residuals with tailored grout formulations, and severing/sealing external penetrations. The life of the carbon steel materials of construction in support of the performance assessment has been completed. The estimation considered general and localized corro… more
Date: January 12, 2009
Creator: Subramanian, K; Bruce Wiersma, B & Stephen Harris, S
Partner: UNT Libraries Government Documents Department
captions transcript

[News Clip: Gas leak]

Description: Video footage from the KXAS-TV/NBC station in Fort Worth, Texas, to accompany a news story.
Date: May 12, 1978, 6:00 p.m.
Duration: 2 minutes 12 seconds
Creator: KXAS-TV (Television station : Fort Worth, Tex.)
Partner: UNT Libraries Special Collections
open access

Geothermal research at the Puna facility. Technical progress report

Description: Research progress is reported. A conceptual model of the reservoir was developed comprising two production zones of different characteristics: the upper zone producing liquid while the lower zone produces vapor. Preliminary studies were carried out at the HGP-A facility on the flocculation behavior of silica under various conditions. (ACR)
Date: December 12, 1985
Creator: Chen, B.
Partner: UNT Libraries Government Documents Department
open access

Estimated steady-state compositions of supernatant liquid during sludge washing

Description: Steady-state hydroxide, pH, carbonate and bicarbonate levels have been estimated for supernatant liquids during sludge washing and storage. These compositions were needed in order to prepare synthetic solutions for determining inhibitor requirements. The steady-state pH was plotted versus the nitrate concentration and fitted to a logarithmic expression of the form, pH = 10.23 [times] [NO[sub 3][minus]][sup 0.0178] where [NO[sub 3][minus]] is the concentration of nitrate in moles/liter. Similar … more
Date: November 12, 1991
Creator: Hobbs, D. T.
Partner: UNT Libraries Government Documents Department
open access

The Corrosion of Various Stainless Steels in Synthetic Waste Solutions

Description: Technical report describing the tests on types 309, 316, and 347 stainless steel. These steels were tested for a total of 779 to 828 hours in three different synthetic waste solutions. Results shoe that the best all-around corrosion resistance to the test conditions was exhibited by 316 stainless steel, but in one solution 347 stainless steel was more resistant. [From Abstract]
Date: February 12, 1951
Creator: English, James L.
Partner: UNT Libraries Government Documents Department
open access

Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, July 1, 1980-September 30, 1980

Description: Objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for … more
Date: December 12, 1980
Partner: UNT Libraries Government Documents Department
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Final report -- IP-153-I, Hagan coagulant aid as a substitute for separan

Description: The demand for filtered water will be increased when I and E slugs are charged into the reactors. Some of the filter plants are near their ultimate capacity. One of the quickest ways of obtaining increased amounts of filtered water for production use is to restore to normal process service certain filters which are now isolated for exclusive drinking water use. These drinking water filters are isolated because the process water filters are being treated with Separans, a material which has not b… more
Date: September 12, 1958
Creator: Conley, W. R.
Partner: UNT Libraries Government Documents Department
open access

Summary report for 1990 inservice inspection (ISI) of SRS 100-L reactor tank

Description: The integrity of the SRS reactor tanks is a key factor affecting their suitability for continued service since, unlike the external piping system and components, the tanks are virtually irreplaceable. Cracking in various areas of the process water piping systems has occurred beginning in about 1960 as a result of several degradation mechanisms, chiefly intergranular stress corrosion cracking (IGSCC) and chloride-induced transgranular cracking. The primary objective of this inspection was to det… more
Date: July 12, 1991
Creator: Morrison, J. M. & Loibl, M. W.
Partner: UNT Libraries Government Documents Department
open access

Estimated steady-state compositions of supernatant liquid during sludge washing

Description: Steady-state hydroxide, pH, carbonate and bicarbonate levels have been estimated for supernatant liquids during sludge washing and storage. These compositions were needed in order to prepare synthetic solutions for determining inhibitor requirements. The steady-state pH was plotted versus the nitrate concentration and fitted to a logarithmic expression of the form, pH = 10.23 {times} [NO{sub 3}{minus}]{sup 0.0178} where [NO{sub 3}{minus}] is the concentration of nitrate in moles/liter. Similar … more
Date: November 12, 1991
Creator: Hobbs, D. T.
Partner: UNT Libraries Government Documents Department
open access

Radiometallurgical examination of direct cast core fuel elements, PT-IP-93, (RM-318)

Description: This report discusses two of the direct cast core I & E fuel elements irradiated in C Reactor under PT-IP-93 which were received at the Radiometallurgy Laboratory for examination during July 1959. One of the elements was badly warped and distorted while the other of the same series had remained relatively unchanged. Both pieces had received an average exposure of 689 MWD/T. Warp and diameter measurements show that the one element had warped approximately .040 in. and had become distorted in two… more
Date: November 12, 1959
Creator: Teats, R.
Partner: UNT Libraries Government Documents Department
open access

Properties of fiber composites for advanced flywheel energy storage devices

Description: The performance of commercial high-performance fibers is examined for application to flywheel power supplies. It is shown that actual delivered performance depends on multiple factors such as inherent fiber strength, strength translation and stress-rupture lifetime. Experimental results for recent stress-rupture studies of carbon fibers will be presented and compared with other candidate reinforcement materials. Based on an evaluation of all of the performance factors, it is concluded that carb… more
Date: January 12, 2001
Creator: DeTeresa, S J & Groves, S E
Partner: UNT Libraries Government Documents Department
open access

The role of Hydrogen and Creep in Intergranular Stress Corrosion Cracking of Alloy 600 and Alloy 690 in PWR Primary Water Environments ? a Review

Description: Intergranular attack (IGA) and intergranular stress corrosion cracking (IGSCC) of Alloy 600 in PWR steam generator environment has been extensively studied for over 30 years without rendering a clear understanding of the essential mechanisms. The lack of understanding of the IGSCC mechanism is due to a complex interaction of numerous variables such as microstructure, thermomechanical processing, strain rate, water chemistry and electrochemical potential. Hydrogen plays an important role in all … more
Date: July 12, 2004
Creator: Rebak, R B & Hua, F H
Partner: UNT Libraries Government Documents Department
open access

Creep deformation and rupture behavior of type 304/308 stainless steel structural weldments

Description: The creep deformation and rupture of type 304/308 stainless steel structural weldments at 593/sup 0/C (1100/sup 0/F) was experimentally investigated to study the comparative behavior of the base metal and weld metal constituents. The tests were conducted in support of ORNL's program to develop high-temperature structural design methods applicable to liquid-metal fast breeder reactor (LMFBR) system components that operate in the creep range. The specimens used were thin-walled, right circular cy… more
Date: May 12, 1977
Creator: McAfee, W. J.; Richardson, M. & Sartory, W. K.
Partner: UNT Libraries Government Documents Department
open access

DWPF MATERIALS EVALUATION SUMMARY REPORT

Description: To better ensure the reliability of the Defense Waste Processing Facility (DWPF) remote canyon process equipment, a materials evaluation program was performed as part of the overall startup test program. Specific test programs included FA-04 ('Process Vessels Erosion/Corrosion Studies') and FA-05 (melter inspection). At the conclusion of field testing, Test Results Reports were issued to cover the various test phases. While these reports completed the startup test requirements, DWPF-Engineering… more
Date: September 12, 1996
Creator: Gee, T.; Chandler, G.; Daugherty, W.; Imrich, K. & Jankins, C.
Partner: UNT Libraries Government Documents Department
open access

Production reactor process tube film composition and radionuclide inventory studies. Status report

Description: The discharge of radioactivity from Hanford production reactors to the Columbia River has been studied for a number of years. The primary purposes of these studied have been to learn of the factors influencing production reactor effluent radioactivity concentrations and to develop methods for lowering the discharge concentrations of these radionuclides. In 1962 the Coolant Systems Development Operation (CSDO) began work on this program to determine the in-reactor film compositions and the inven… more
Date: February 12, 1963
Creator: Perrigo, L. D.
Partner: UNT Libraries Government Documents Department
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Corrosion of Zircaloy-2 by pH 10 LiOH in heated crevices

Description: Both the inner and outer tubes of the N-Reactor fuel elements will have self supports spot welded to the lateral heat-transfer surface of the element. A crevice a few mils thick will exist around the weld between the support tab and the cladding. Because of the heat flux through the cladding at this point and the insulating effect of the support tab, the temperature in this crevice will be higher than that on the free surface away from the support. This can result in boiling in the crevice lead… more
Date: November 12, 1963
Creator: Dickinson, D. R.
Partner: UNT Libraries Government Documents Department
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