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Measurements Through a Hot Cell Window Using Optical Tooling

Description: S>Optical tooling has been evaluated for the measurement of physical dimensions of radioactive parts through hot cell windows. Instruments were set up outside of a four foot thick lead glass window and by means of a grid plate which had been accurately scribed, a ''contour map'' or calibration chart of the window variations was recorded. Although the window was not specially selected, the readings were within 1.0% of the true dimension without using correction factors. One of the calibration ch… more
Date: July 18, 1958
Creator: Abbatiello, A. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EVALUATION OF FISSION GAS ADSORPTION TRAPS FOR ORNL-MTR-44 LOOP EXPERIMENT

Description: A method of predicting the performance of fission gas adsorption traps containing activated charcoal is presented. This method is applied in the evaluation of the fission gas traps designed for use in the ORNL-MTR44 loop experiment. The method should also be applicable in evaluating fission gas traps contained in other reactor experiments. (auth)
Date: July 18, 1958
Creator: Adams, R. E. & Browning, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Direct Maintenance Practices for the Homogeneous Reactor Test

Description: The Homogeneous Reactor Test is designed for maintenance to be performed while the parts of the reactor are partinlly or completely submerged in water to reduce radiation levels. Tools with long handles permit the operator, standing above the equipment, to disconnect flanged joints, air lines, electrical and instrument leads, etc., in a minimum time. The techniques and tools employed to accomplish these various operations and to minimize intermixing of the contaminated process fluids with the s… more
Date: April 18, 1958
Creator: Beall, S. E. & Jurgensen, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental Behavior of Pentaborane-Air Combustion Products During Expansion in a Convergent Divergent Nozzle

Description: "In order to evaluate the post combustion behavior of boric oxide, pentaborane-air mixtures, burned to completion at a combustor pressure of 3 atmospheres, were expanded through a 7.1-inch-long convergent-divergent nozzle having a 4-inch-diameter throat and an exit-to-throat area ratio of 1.68. The experimentally determined thrust performance was in good agreement with the ideal equilibrium performance at stagnation temperatures of 3300 deg R and lower. The boric oxide vapor at the combustor ex… more
Date: February 18, 1958
Creator: Branstetter, J. Robert & Setze, Paul C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental behavior of pentaborane-air combustion products during expansion in a convergent-divergent nozzle

Description: Report presenting an evaluation of the postcombustion behavior of boric oxide using pentaborane-air mixtures burned to completion at a combustor pressure of 3 atmospheres expanded through a convergent-divergent nozzle. Results regarding the symmetry of flow in nozzle, behavior of liquid boric oxide in nozzle, abrupt condensation phenomena, effect of abrupt condensation on performance, and effect of oxide films are provided.
Date: February 18, 1958
Creator: Branstetter, J. Robert & Setze, Paul C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Unit Operations Section Monthly Progress Report, September 1958

Description: The feasibility was demonstrated of the use of liquidorganic scintillators in contact with an alpha emitting aqueous phase for the measurement of interfacial area in a mixer. The transpiration flow of pure water reduced the corrosion by a factor of 60 of a porous nickel tube by FeC1/sub 3/. One continuous DRUHM reaction study was made in which poor product consolidation resulted from a less than optimum sodium feed rate. In Fluorox run FBR-19, an over-all material balance of 102% and a UF/sub 6… more
Date: November 18, 1958
Creator: Bresee, J. C.; Haas, P. A.; Watson, C. D. & Whatley, M. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Blending UNH streams of different uranium enrichments

Description: The cost and feasibility of blending UNH streams of different uranium enrichments at HAPO was evaluated on a preliminary basis. Cases studied were blending 37.5% enriched UNH with depleted E metal UNH to yield a 0.947% enriched end product, and blending depleted E metal UNH with the depleted natural uranium to yield 0.7115% enriched end product. A reasonable degree of feasibility is indicated for such a blend program at HAPO.
Date: April 18, 1958
Creator: Campbell, B. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Investigation of Two Bluff Shapes in Axial Free Flight Over a Mach Number Range From 0.35 and 2.15

Description: Memorandum presenting a fineness-ratio-2.71 right circular cylinder and a fineness-ratio-4.0 circular cylinder with a rounded nose and a flared afterbody tested in free flight over a range of Mach and Reynolds numbers. Time histories, cross plots of force coefficients, rolling velocity, and longitudinal-force coefficient are presented for both cylinders.
Date: March 18, 1958
Creator: Coltrane, Lucille C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Investigation of Two Bluff Shapes in Axial Free Flight Over a Mach Number Range From 0.35 to 2.15

Description: Report presenting testing of a fineness-ratio-2.71 right circular cylinder and a fineness-ratio-4.0 circular cylinder with a rounded nose and flared afterbody over a range of Mach and Reynolds numbers. Time histories, cross plots of force coefficients, rolling velocity, and longitudinal-force coefficient are provided for the two cylinders.
Date: March 18, 1958
Creator: Coltrane, Lucille C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ELECTROLYSIS CELL FOR RECOMBINATION STUDIES

Description: A small, laboratory-sized loop was designed for steady-state radiolytic gas recombination studies. It consists of an electrolysis cell, which simulates the radiolytic gas formed in a reactor, and a bomb for containing slurry under test. The electrolysis capacity of the system is adequate for the study of slurries having recombination rates as high as 10 moles/hr/liter of slurry at the proposed slurry reactor operating conditions. (auth)
Date: September 18, 1958
Creator: Culver, R.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tabular Summary of Zircaloy-2 in-Pile Rocking Autoclave Corrosion Data

Description: A tabular resume of the data from 37 in-pile Zircaloy-2 rocking autoclave corrosion experiments performed since August 1954 is presented. Included are data concernin,; solutions used on the specimens before and after the reactor eKposure, sample treatment prior to irradiation conditions during exposure, data on oxygen consumption and specimen weight losses, and miscellaneous data. (J.R.D.)
Date: June 18, 1958
Creator: Davis, R.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Status of Subcontract Work on Effects of Radiation on Solvent Extraction Processes

Description: The results of the Stanford Research Institute studies of the effects of radiation on solvent extraction processes are summarized, and a desirable direction for future work is indicated. Studies performed to date have shown that: (1) nearly all of the irradiation-induced increase in time required for TBP- -Amsco--aqueous phase separation is due to formation of a polymer, of unknown chemical structure; (2) uranium retention by the TBP-- Amsco phase during stripping operations is due approximatel… more
Date: June 18, 1958
Creator: Davis, W., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aerodynamic and inlet-flow-field characteristics at a free-stream Mach number of 3.0 for airplanes with circular fuselage cross sections and for two engine locations

Description: Report presenting an experimental investigation of several airplane configurations at Mach 3.0 in a continuous flow tunnel. The configurations had circular fuselage cross sections and a sweptback wing and either two nacelles or two side inlets.
Date: March 18, 1958
Creator: Dryer, Murray & Luidens, Roger W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production Test IP-98-I revised tube charge pattern for graphite annealing: Interim Report

Description: Graphite shrinkage of 0.60 inches (approximately 30 per cent) has been observed at F Reactor in the region of maximum graphite distortion. A reduction of graphite distortion at B Reactor of 0.60 inches in the top-center and 0.32 inches in the top-far region also has been observed. Analysis of the vertical traverse data indicates that continued graphite annealing with resultant decrease in graphite distortion might be anticipated although perhaps at a reduced rate. No significant detrimental eff… more
Date: December 18, 1958
Creator: Graves, S. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effect of Forging Temperature and Heat Treatment on the Performance of Inconel 700 Buckets at 1625 Degrees F in a J33-9 Turbojet Engine

Description: Report presenting an investigation to determine the effects of forging temperatures and solution treatments on the engine performance of Inconel 700 buckets. The buckets were tested in a J33-9 turbojet engine at 1625 degrees F in 20-minute cycles. Testing demonstrated that the buckets are capable of operating for more than 450 hours at rated speed.
Date: February 18, 1958
Creator: Gyorgak, C. A.; Springsteen, D. F. & Johnston, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SUMMARY OF UO$sub 2$-STAINLESS STEEL DISPERSION ELEMENT IRRADIATION EXPERIMENTS

Description: A search of the literature to obtain information concerning enriched UO/ sub 2/-- stainless-steel dispersion type fuel elements has disclosed five programs which have pertinent information. The primary aim of the search was to discover maximum burn-ups and temperatures for safe use of this type of element. Tests were labeled a failure if swelling, cracking or fission-product release resulted from the irradiation. Moderate swelling or blisters without the other indications was called a slight fa… more
Date: March 18, 1958
Creator: Haynes, V.O.; Neill, F.H. & Schaffer, L.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MOLTEN SALT HEAT TRANSFER

Description: The experimental system used in the determination of turbulent forced- convection heat-transfer coeificients with molten salts is described, and the results of the experimental program are detailed. The salts studied have been the mixtures NaNO/sub 2/-NaNO/sub 3/--KHO/sub 3/, LiF --NaF --KF and s with the LiF--NaF-KF mixture in Inconel tubes are explained in terms of an interfacial film. A nonwetting phenomenon is postulated to describe the decreased heat transfer in the NaF--ZrF/sub 4/-UF/sub … more
Date: February 18, 1958
Creator: Hoffman, H.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

C-Pile pigtail failure

Description: This document provides conclusions made concerning inlet line (pigtail) rupture effects on the Hanford reactors.
Date: July 18, 1958
Creator: Jones, S. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE APPLICATION OF THE CHIP AND SHOT METHODS TO THE PREPARATION OF HOMOGENEOUS ALLOYS

Description: Chip method experiments were performed for the preparation of Th - 9 wt.% U, U - 10 wt.% Nb, and Al--16 wt.% U - 0.2 wt.% B alloys. The work on Th-9 wt.% U indicated that the technique was applicable with oniy slight impairment of mechanical properties and slight increase of oxygen content. Experiments on U-10 wt.% Nb to produce a more corrosion-resistant alloy were not successful. The potential use of the chip method in fabricating alloys with a burnable poison such as boron appeared feasible.… more
Date: September 18, 1958
Creator: Kneppel, D.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PHASE III-FOREIGN REACTOR-FUEL SAMPLE IRRADIATION OF U$sub 3$O$sub 8$-Al DISPERSIONS. IRRADIATION REQUEST ORNL-MTR-35

Description: The integrity and suitability of 35 vol.% U/sub 3/ O/sub 8/ dispersion in Al as a fuel for foreign reactors were determined. The fuel was exposed in the beryllium reflector of the MTR. Sample fabrication and conditions of exposurne are described, and the results are tabulated. (J.R.D.)
Date: October 18, 1958
Creator: Leitten, C.F. & Kucera, W.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CHEMICAL INDICATIONS OF HRT MISBEHAVIOR IN RUN 17-A

Description: The cause and significance of the changes in chemical composition of the HRT fuel and changes in reactivity during operation, particularly in run 17A, were investigated. It was concluded that a rise in reactor power level causes deposition of U, Cu, and Ni in some hydrolytic process within the core circulation system in a region which is at a position between zero and average nuclear importance. The deposition requires several minutes to several hours and is relatively easily reversiable when t… more
Date: September 18, 1958
Creator: McDuffie, H.F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SHIELDING-RESEARCH AREA AT BATTELLE

Description: The design and constructlon of the shielding facility at Battelle are described. This facility consists of an open pool with a fission plate, an instrument bridge and tower, a control room, and radiation-detection instruments. The shielding pool is located at the end of the thermal column of the Battelle Research Reactor (BRR). The fission plate is 28 in. in diameter and contains approximately 3.5 kg of U/sup 235/. The plate was fabricated from three pieces of highly enriched U and clad with ab… more
Date: September 18, 1958
Creator: Morgan, W.R.; Epstein, H.M.; Anno, J.N. Jr. & Chastain, J.W. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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