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Atom Arrangements in Some Iron-Aluminum Solutions, Report No. 1

Description: "Short-range order coefficients were measured at 300 and 400°C for iron-aluminum alloys containing 14.8, 18.2, and 20.0 atomic per cent aluminum. These alloys exhibited a strong preference for unlike near neighbors. The short-range order was greater at the lower temperature and increased as the Fe 3Al composition was approached."
Date: July 12, 1962
Creator: Houska, C. R. & Averbach, B. L.
Item Type: Refine your search to only Report
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Automatic Temperature Control of Irradiation Capsules by a Variable Binary Gas Mixture

Description: Temperature control was achieved by varying the gas mixture, and therefore the thermal conductivity, in a gas annulus surrounding the irradiation capsule. Control systems were used for over one year and maintained capsule temperature to e due to uraniu 10 l F. The system may be used equally satisfactorily with either fueled or nonfueled capsules. The reliability of the system was extremely high, and all maintenance was limited to the readily accessible instrumentation. (auth)
Date: September 12, 1962
Creator: Drescher, R. C. & Johnson, D. E.
Item Type: Refine your search to only Report
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Carbon Transport and Corrosion in High-Temperature Gas-Cooled Reactors

Description: It is noted that in high-temperature He-cooled graphite reactors, sufficiently high levels of gaseous impurities can lead to transport and corrosion effects. The possible effects of these reactions in graphite-moderated reactors designed to operate at a He-coolant pressure of a about 20 atm. were investigated. Results are included on C transport, steam-graphite reactions, and deposition of C on surfaces. (J.R.D.)
Date: April 12, 1962
Creator: Zumwalt, L. R.; Burnette, R. D. & Riedinger, A. B.
Item Type: Refine your search to only Report
open access

Design scope of the Z Plant Metal Control Facility, Project CGC-944

Description: The steadily increasing plutonium production rates in the 234-5 Building has resulted in a large increase in the number of PR cans that are now being handled in the building. This has resulted in the available receiving and storage places for PR cans being taxed beyond their full capacity thereby necessitating the storage of PR cans within the building corridors. Accordingly, the ten-year business plan for the 234-5 Building, as documented in HW-65000, included a program for providing new recei… more
Date: March 12, 1962
Creator: Haberman, H.D.
Item Type: Refine your search to only Report
open access

Examination of rupture from 1372-H (RM 454)

Description: A production fuel element which failed in tube 1372-H on March 12, 1962 at 263 MWD/T exposure was transferred to the Radiometallurgy Laboratory for examination to determine the cause of failure. The fuel geometry was 0 III N-B and the parent Lot was KZ-135 D. The failure was the result of mechanical damage to the cladding and cap at the male end prior to irradiation. A scrape or gouge at the male end reduced the cladding thickness drastically so that water entry to the uranium occurred after an… more
Date: September 12, 1962
Creator: Gruber, W. J.
Item Type: Refine your search to only Report
open access

Fire Tests of Precast Cellular Concrete Floors and Roofs

Description: From Abstract: "The results of an investigation of lightweight, precast cellular concrete planks are given. Fire tests were made of two floor and five roof specimens made up of these planks. Variables, included density of the cellular concrete, thickness and span of the planks, reinforcement, and cover for the latter."
Date: April 12, 1962
Creator: Ryan, J. V. & Bender, E. W.
Item Type: Refine your search to only Report
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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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
open access

PL-3 Phase I Task 3 Research and Development Report

Description: Abstract: This technical report summarizes the results of research and development tasks performed during Phase I of this contract and presents recommendations for future development work. Work is reported in the areas of plant assembly and relocation, housings and footings, waste heat dissipation, instrumentation, refueling systems, waste disposal, shielding, core nuclear thermal and hydraulic studies, gaseous waste processing (BWR), and critical experiments on a 5 x 5 array of Type 3 fuel ele… more
Date: March 12, 1962
Creator: Humphries, G. E.
Item Type: Refine your search to only Report
open access

PLUTONIUM HANDLING FACILITIES FOR RADIOGRAPHY

Description: Since any radiography must be performed in an enclosed system, an enclosed glove box was constructed to facilitate radiographic operations. Tests show that no significant detail is lost in radiographing dense materials greater than 0.020 inch through 0.120 inch of aluminum using energies in the 1 Mev range. (auth)
Date: April 12, 1962
Creator: Dighton, A. L.; Sampson, J. C. & Stump, W. D.
Item Type: Refine your search to only Report
open access

Poison compensation with the xenon override

Description: The feasibility of operation with an enriched core to ``override`` the xenon transient and thus reduce minimum downtime has been reasonably well established. The principle economic disadvantage of the present technique is associated with the use of boron splines for compensating the reactivity effect of the core during normal operation. The boron-containing spline parasitically absorb the excess neutrons produced in the core thus wasting these surplus neutrons during the operation when the enri… more
Date: June 12, 1962
Creator: Owsley, G. F.
Item Type: Refine your search to only Report
open access

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

Description: 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 ind… more
Date: July 12, 1962
Creator: Michelson, C.; Culp, A.W. & Neill, F.H.
Item Type: Refine your search to only Report
open access

The Preparation and Properties of Molybdenum(IV) Bromide

Description: From abstract: "The preparation of pure molybdenum(IV) bromide was accomplished conveniently by the reaction between molybdenum(III) bromide and liquid bromine at ca. 55°. Molybdenum(IV) bromide was found to be soluble in liquid bromine, and this property was utilized to separate and purify the molybdenum(IV) bromide. The solution of MoBr4 in bromine was a poor electrical conductor. No evidence was found for the formation of MoBr4 from MoBr3 and bromine vapor at 2-4 atm. and temperatures from 1… more
Date: June 12, 1962
Creator: Carnell, P. J. H. & McCarley, R. E.
Item Type: Refine your search to only Report
open access

PREPARATION OF (Th,U)C$sub 2$ FUEL PARTICLES FOR THE HTGR

Description: A process that was developed for the preparation of particles of thorium- uranium dicarbide is described. Granulated particles composed of powdered UO/sub 2/, ThO/sub 2/, and carbon were suspended in a bed of graphite flour and heated to convert the oxides to dicarbides. The particles were then melted to densify and spheroidize them, the graphite flour keeping them separated so that they would not flow together. (auth)
Date: November 12, 1962
Creator: Goeddel, W. V. & Shoemaker, H. E.
Item Type: Refine your search to only Report
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