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EEN-333, revised getter flash procedure

Description: EWR No. VTE-188--Tubes processed by flashing getters immediately prior to seal-off from vacuum systems are compared for total residual gas pressure to tubes processed by flashing getters after tubes were sealed off vacuum systems. Comparisons of residual pressures determined from current flows in the cold cathode ion gauge.
Date: June 28, 1960
Creator: Brown, W.C.
Partner: UNT Libraries Government Documents Department
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Reactivity Absorbed by Xenon-135 in the SRE

Description: Abstract: The measurement and calculation of the reactivity absorbed by Xe135 as functions of time after shutdown for the SRE are described.
Date: January 28, 1960
Creator: Woodruff, R. W.
Partner: UNT Libraries Government Documents Department
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Evaluation and Design Heavy Water Moderated Power Reactor Plants

Description: From introduction: This report has been prepared to present the details of the heavy water cooled power reactors, including cost estimates, plant design studies, and other work directly related to the current status of D2O reactors.
Date: April 28, 1960
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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TEST OF HRT-CP MULTICLONE NO. 1 FOLLOWING REMOVAL FROM REACTOR CELL

Description: The multiple hydroclone unit, or multiclone, installed in the reactor cell prior to run 20, in an effort to increase the solids removal rate of the hydrcclone system, was removed after 4500 hr of operation (end of HRT run 21). Examination and tests of this unit after removal indicated an accumulation of about 100 g of solids in the feed chamber and partial plugging of one to three hydroclone feed ports. The plugged hydroclones would permit flow from the underflow pot to the overflow stream and … more
Date: June 28, 1960
Creator: Yarbro, O O
Partner: UNT Libraries Government Documents Department
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Optimization Studies on Paste-Fueled Fast Reactors

Description: The reference design is an unmoderated, sodium-cooled reactor using a paste fuel of uranium monocarbide in sodium. The core is a cylinder 5 ft in diameter and 5 ft in height. An 18-in. thick breeding blanket surrounds the core, and an 18-in. thick graphite reflector surrounds the blanket. Various changes were made in the reference core to uncover any possible modifications for cost reductions and to evaluate the consequences of certain design modifications which might occur. Cases were studied … more
Date: December 28, 1960
Creator: Zetterbaum, J. M. & Kerlin, T. W.
Partner: UNT Libraries Government Documents Department
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Chemical Techinology Division, Unit Operations Section Monthly Progress Report, April 1960

Description: Experiments showed that 30% tributyl phosphate will not extract acid- deficient species of uranyl nitrate. Flooding throughputs for the Mark I stacked- clone contactor ranged from 600 cc/min organic at zero aqueous to 60 cc/min organic at 1950 cc aqueous. A large electronic vibrator of 5000-lb thrust was found somewhat inferior to pneumatic vibration for compacting oxide fuels into stainless-steel tubes. Tests were started on the use of fixed-bed CuO oxidizers for removing hydrogen contaminatio… more
Date: July 28, 1960
Creator: Whatley, M E; Haas, P A; Horton, R W; Ryon, A D; Suddath, J C & Watson, C D
Partner: UNT Libraries Government Documents Department
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HIGH-TEMPERATURE COMPATIBILITY OF Al$sub 2$O$sub 3$-, BeO-, AND METAL- COATED UO$sub 2$ PARTICLES WITH GRAPHITE AND COKE

Description: The compatibility of carbon and graphite matrices with UO/sub 2/ particles coated with Al/sub 2/O/sub 3/, BeO, nickel, niobium, and nickel- chromium alloy was investigated at several temperatures up to 3OOO deg F in flowing helium. Two different carbonaceous fillers and binders were used. As expected, the 2 to 8- mu metal coatings were badly damaged by reaction with carbon at temperatures as low as 17OO deg F. Both oxide coatings were completely destroyed after 6 hr at 3000 deg F. Considerable … more
Date: November 28, 1960
Creator: Gerds, A.F. & Smalley, A.K.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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Bubble Chamber Safety Meeting

Description: A description is given of bubble chambers in use and those in the design stages. Safety factors in the design and operation of a bubble chamber are discussed. Data are presented on fatige and rupture tests on glass. Data are contained on the effects of liquid helium on the tensile properties of various stainless steels. (C.J.G.)
Date: June 28, 1960
Creator: Harrer, J. M.
Partner: UNT Libraries Government Documents Department
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Isotopic Analysis of Boron as Trimethyl Borate

Description: Boron-impregnated polyethylene tape was irradiated in the Engineering Test Reactor Critical Facility to study the effect of boron as a burnable poison in reactor fuel. Isotopic analysis of the boron was performed with a conventional CEC Model 21-103 mass spectrometer. The tape was distilled off and the residual boron was converted to trimethyl borate. The reaction mixture was analyzed without separation. Good precision was obtained with samples containing less than 0.5 mg. boron. Features of th… more
Date: January 28, 1960
Creator: Abernathey, R. M.
Partner: UNT Libraries Government Documents Department
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AN IMPROVED NUCLEAR MEASURING PRINCIPLE. Quarterly Progress Report No. 3 Covering the Period from December 1, 1959 to March 1, 1960

Description: The scintillation counter has proven to be a very valuable research tool, but urfortunately, its ability to meet necessary stability requirements has restricted its use in industrial applications. Several techniques are being investigated which cancel out reasonable variations in detector sensitivity, resulting in improved stability. The general technique consists of alternately measuring the intensity transmitted through the sample and through a calibrated absorber, and difference in intensity… more
Date: March 28, 1960
Creator: Burgwald, G.M.
Partner: UNT Libraries Government Documents Department
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LEACHING OF TAMALPAIS DEBRIS

Description: From Tamalpais debris crushed to <53 mu , 5.5, 19.6, and 12.5 f the alpha, beta, and gamma activities, respectively, were leached in 72 hr at room temperature by a 100 to 1 weight excess of ground water from the Nevada test site. The extracted alpha-activity material was> 97% Pu/sup 239/ and < 3% Am/sup 241/, and the gamma was 92% Ru/sup106/, 4.7% ZrNb/sup 95/, and 3.1% Cs/137/. The beta activities could not be identified. The ground water leached 10 to 20 times as high a percentage of activity… more
Date: January 28, 1960
Creator: Bond, W. D. & Clark, W. E.
Partner: UNT Libraries Government Documents Department
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An Improved Nuclear Measuring Principle : Quarterly Progress Report No. 3 Covering the Period from December 1, 1959 to March 1, 1960

Description: This report is the third in a series of quarterly reports discussing the concept and progression of an improved method in nuclear measuring than the usage of the scintillation counter. This report indicates that in a chopped double beam system, commutation of the detector current permits selection of optimum response time and size of radioactive sources.
Date: March 28, 1960
Creator: Burgwald, G. M. & Stone, C. A.
Partner: UNT Libraries Government Documents Department
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Inventory radioactive liquid waste to ground 200 Areas, 1945--1959

Description: Since startup in January 1945 through December 1959, 4 {times} 10{sup 9} gallons of radioactive liquid wastes have been discharged to cribs and trenches at HAPO by the Chemical Processing Department facilities in the 200 Areas. These wastes contained approximately 2.5 {times} 10{sup 6} curies of beta emitters. The Scavenged Waste Recovery Program was completed in 1957 and Redox Plant process changes were made during the latter part of 1958. These changes resulted in significant reduction in the… more
Date: July 28, 1960
Creator: Brown, G. D. & McConiga, M. W.
Partner: UNT Libraries Government Documents Department
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Contoured I&E sleeves

Description: The feasibility of contoured I&E cans for production use has been demonstrated using our present flat base I&E sleeve (HW-37187). Studies by Process Engineering and Quality Control have shown that only a material savings would result from the use of only the contoured I&E can. Consideration was then given to the use of contoured sleeves (H-3-16879) to improve the contact areas and the resulting heat transfer during fuel assembly.
Date: June 28, 1960
Creator: Burgess, C. A.
Partner: UNT Libraries Government Documents Department
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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.
Partner: UNT Libraries Government Documents Department
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Engineering bases for power levels and exposures - April, 1960, thru December, 1960

Description: It is the purpose of this document to provide assistance to the Manufacturing Section personnel in determining their future operating plans. In general, the inter-relationship of such engineering parameters as flow, reactor orificing, rupture performance, etc. has been considered. The effect of these engineering parameters are summed up in our recommendations for {open_quotes}Operating Plans{close_quotes} shown graphically in this document. It is to be emphasized that these plans do not reflect… more
Date: April 28, 1960
Creator: Graves, S. M.
Partner: UNT Libraries Government Documents Department
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Analysis of E-N loadings

Description: Three E-N loaded tubes were dissolved, sampled and analyzed, starting November 9, 1960. The results of these analyses and an explanation of the methods used are the subject of this report. Each tube loading received an identification code in each facility in which it was processed. All of these codes are listed for future reference. Each batch of slugs was dissolved in a preflushed dissolver. When complete solution was indicated by a leveling off of the specific gravity, two 1 ml samples were t… more
Date: December 28, 1960
Creator: Zimmer, W. H.
Partner: UNT Libraries Government Documents Department
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