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EOCR Control Rod and Driver Fuel Hydraulic Tests

Description: Report discussing the results of experiments on an EOCR prototype control rod, control rod drive, and driver fuel assembly that were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. It includes descriptions of the control rod, control rod drive, and driver fuel assembly together with descriptions of their method of operation.
Date: October 19, 1962
Creator: Harrison, L. J.
Partner: UNT Libraries Government Documents Department
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1.5% boron, stainless steel

Description: A test report on the brittleness of borated steel to be used in the KIWI B-5 shield capsules.
Date: September 19, 1962
Creator: Schreiber, J.J.
Partner: UNT Libraries Government Documents Department
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GETR data package

Description: No Description Available.
Date: September 19, 1962
Creator: Coombe, J.
Partner: UNT Libraries Government Documents Department
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EOCR CONTROL ROD AND DRIVER FUEL HYDRAULIC TESTS

Description: The EOCR prototype control rod, control rod drive, and driver fuel assembly were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. The modifications required were tested to establish the satisfactory performance of the modified components. Flow versus pressure differential measurements were performed on the driver fuel and the contr… more
Date: October 19, 1962
Creator: Harrison, L. J.
Partner: UNT Libraries Government Documents Department
open access

Radiation Effects in Carbons and Graphites

Description: Two simultaneous effects occur during the irradiation of polycrystnlline graphite which account for the observed dimensional instability. The first is a disordering of the crystallites which results in an expansion parallel to the c axis and a contraction parallel to the a axis. This process is highly temperature dependent and at room temperature is the principal effect. The second effect is a nonannealable contraction, which acts primarily in the transverse direction in anisotropic nuclear gra… more
Date: March 19, 1962
Creator: Yoshikawa, H. H.; Woodruff, E. M.; Davidson, J. M.; Helm, J. W. & Nightingale, R. E.
Partner: UNT Libraries Government Documents Department
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Vibrational Analysis of Unfired Horizontal Bayonet Tubes in a Fluidized Bed Calciner

Description: The heat exchanger of the calciner consists of a vessel into which unfired, horizontal, bayonet tubes extend in a fluidized bed. Strain measurements were taken on several of the tubes under simulated operating conditions and the associated dynamic stresses were calculated. Vibrations greater than design limitations for indefinite operation were found to exist. To restrict these vibrations and prevent further tube fatigue cracking, a tube support was installed. Since the installation of the supp… more
Date: October 19, 1962
Creator: Anderson, S.D. & Hirschi, G.W.
Partner: UNT Libraries Government Documents Department
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Slow Cycle Strain Fatigue in Thin Wall Tubing: Preliminary Report

Description: A technique has been developed for slow cycle strain fatigue testing using specimens of thin-wall tubing of the type under consideration for use as super heat fuel cladding. Data on type 304 stainless steel have been obtained under radiation and in the absence of radiation. The strain cycle fatigue life of this alloy at 1200 to 1300 deg F is decreased three fold by the presence of a neutron flux of 1.5 x 10/sup 14/ > 1 Mev. Out-of-reactor data have been obtained on Inconel at 1300 deg F. (auth)
Date: July 19, 1962
Creator: Reynolds, M. B.
Partner: UNT Libraries Government Documents Department
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The Use of Phosphite and Hypophosphite to Fix Ruthenium From High-Activity Wastes in Solid Media

Description: Fission product Ru, normally volatile to the extent of 20 to 60% in evaporation and calcination of simulated high level radioactive wastes at 500 to 1000 deg C, can be 99.9% retained in the solid product by addition of 2 moles of phosphite or hynophosphite per liter of waste. As little as 0.1 mole per liter lowered the Ru volatility during distillation approaching equilibrium by factors which varied from 38 for Darex to 225 for TBP-25 (aluminum) waste solutions. The final products with Purex, T… more
Date: June 19, 1962
Creator: Godbee, H. W. & Clark, W. E.
Partner: UNT Libraries Government Documents Department
open access

RADIOISOTOPE AND RADIATION APPLICATIONS. Quarterly Progress Report No. 13

Description: Research was continued during the report period on the use of isotope neutron sources for producing short-lived radioisotopes. Experiments with a newly constructed betacounting cell are reported in which a 50-curie Be--Po neutron source was used. Study of the radiation chemistry of polymers was continued concerning the effects of polymer structure on free-radical formation. Free-radical formation in several additional polymers was studied. Preliminary work is also reported in an investigation o… more
Date: July 19, 1962
Creator: Sunderman, D.N. ed.
Partner: UNT Libraries Government Documents Department
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Gcr-Orr Loop No. 2 Filter Tests. Part Ii

Description: Tests of Cambridge absolute filters, Model Sl-071, specified for use in the GCR-ORR Loop No. 2 as full-flow, primary coolant fiiters were completed. kD.O.P/ (dioctylphthalate) efficiency tests were performed on three filters in the as-received condition, on two filters following canning and thermal cycling, and on one of the canned fiIters following bsking out. None of the three units met the design criteria of 99.97% efficiency for removal of 0.3 micron particles in the as-received condition. … more
Date: February 19, 1962
Creator: Flint, F. A. & Smith, A. M.
Partner: UNT Libraries Government Documents Department
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Corrosion Behavior of Reactor Materials in Fluoride Salt Mixtures

Description: Molten fluoride salts, because of their radiation stability and ability to contain both Th and U, offer important advantages as high-temperature fuel solutions for nuclear reactors and as media suitable for nuclear fuel processing. Both applications have stimulated experimental and theoretical studies of the corrosion processes by which molten salt mixtures attack potential reactor materials. Corrosion experiments with fluoride salts which were conducted in support of the Molten-Salt Reactor E … more
Date: September 19, 1962
Creator: DeVan, J. H. & Evans, R. B., III
Partner: UNT Libraries Government Documents Department
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An Evaluation of the Uranium Contamination on the Surfaces of Alclad Uranium-Aluminum Alloy Research Reactor Fuel Plates

Description: Reported radioactivity in the Low-Intensity Test Reactor (LITR) water coolant traceable to uranium contamination on the surfaces of the alclad uranium-- aluminum plate-tyne fuel element led to an investigation to determine the sources of uranium contamination on the fuel plate surfaces. Two possible contributors to surface contamination are external sources such as rolling-mill equipment, the most obvious, and diffusion of uranium from the uranium-aluminum alloy fuel into the aluminum cladding.… more
Date: March 19, 1962
Creator: Beaver, R. J.; Erwin, J. H. & Mateer, R. S.
Partner: UNT Libraries Government Documents Department
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PREPARATION AND FABRICATION OF ThO$sub 2$ FUELS

Description: Dense partricles of ThO/sub 2/-UO/sub 2/ were prepared by a sol-gel process and vibratorily compacted into metal tubes to a density approaching 9.0 g/ cc. The steps in this method are all simple and can be carried out behind shielding, which is necessary for refabricating U/sup 233/ fuels. The sol-gel process consists of preparing a hydrous thoria sol, adding the U/sup 233/ as nitrate solution, evaporating to a gel, and finally calcining to almost theoretically dense oxide particles at orly 115… more
Date: June 19, 1962
Creator: Ferguson, D.E.; Arnold, E.D.; Ernst, W.S. Jr. & Dean, O.C.
Partner: UNT Libraries Government Documents Department
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SM-1 Reactor Vessel Cover and Flange Stress Analysis

Description: The maximum stress calculated for the SMl-1 reactor vessel closure studs occurs during operation at full power. This value is 27,180 psi of which 19,800 psi is tension and 7380 psi bending. This stress does not include a stress concentration factor for effect of threads. It was eonservatively assumed the studs were initially tightened to a code allowable stress of 20,000 psi as specified in the ASME Code rather than the lesser stress obtained by the normal operating procedure. The maximum calcu… more
Date: February 19, 1962
Creator: Sayre, M. F.
Partner: UNT Libraries Government Documents Department
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MOLTEN-SALT REACTOR PROGRAM PROGRESS REPORT FOR PERIOD FROM MARCH 1 TO AUGUST 31, 1961

Description: The Molten Salt Reactor Experiment design, component development, and engineering analysis is discussed. Materials studies for the Molten-Salt Reactor Program including metallurgy, in-pile tests, chemistry, engineering research, and fuel processing are described. (M.C.G.)
Date: January 19, 1962
Partner: UNT Libraries Government Documents Department
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Measurement of Xenon Poisoning in the HRT

Description: Measurements obtained during three periods of HRT operations indicated that the xenon poison fraction was approximately 0.010. The technique used was based on mass spectrographic analyses of the stable xenon isotopes in the reactor off-gas stream. Models proposed to explain the measurements show that xenon, which is formed primarily by decay of iodine adsorbed on the pipe walls, is held up on the walls, out of the circulating stream, for an average period of about eight hours. (auth)
Date: April 19, 1962
Creator: Burch, W.D.
Partner: UNT Libraries Government Documents Department
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Symbols for Instrument Flowsheets and Drawings. A Recommended System for Application to ORNL Instrument Work

Description: Details concerning a recommended system of flow-plan symbols and drawings are given. The system is designed to identify the function of all major instrument components and to show schematically the operation of the instrument relative to the particular process. The system is used for identification and designation. (J.R.D.)
Date: June 19, 1962
Creator: Adams, R. K.; Davis, D. G.; Hyland, R. F. & Lieberman, B.
Partner: UNT Libraries Government Documents Department
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Use of phosphite and hypophosphite to fix ruthenium from high-activity wastes in solid media

Description: Fission product Ru, normally volatile to the extent of 20 to 60% in evaporation and calcination of simulated high level radioactive wastes at 500 to 1000/sup 0/C, can be 99.9% retained in the solid product by addition of 2 moles of phosphite or hypophosphite per liter of waste. As little as 0.1 mole per liter lowered the Ru volatility during distillation approaching equilibrium by factors which varied from 38 for Darex to 225 for TBP-25 (aluminum) waste solutions. The final products with Purex,… more
Date: June 19, 1962
Creator: Godbee, H. W. & Clark, W. E.
Partner: UNT Libraries Government Documents Department
open access

Reorificing proposal D Reactor

Description: No Description Available.
Date: October 19, 1962
Creator: Hollifield, P. J.
Partner: UNT Libraries Government Documents Department
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Review of reactor graphite distortion problems

Description: The purpose of this document is primarily to discuss the effects of current retubing programs on the graphite moderator of the K Reactors. A secondary purpose of this report is to present general information related to graphite arrangement and keying patterns at the other operating reactors and to review, in a limited way, the types of graphite distortion observed at these reactors.
Date: November 19, 1962
Creator: Coughren, K. D.; Kempf, F. J. & Munro, C. A.
Partner: UNT Libraries Government Documents Department
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