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REMOTE DISSOLUTION AND ANALYTICAL PROGRAM FOR IRRADIATED THORIUM

Description: A remote dissolution and analytical program for irradiated thorium is given. The aluminum jacket on the slug was dissolved with 6M nitric acid and 0.005M mercuric nitrate. After a water wash, the thorium dissolution was accomplished with concentrated nitric acid made 0.04M in hydrofluoric acid. Weighing, dissolving, and sampling were done remotely in the multicurie cell at the Idaho Chemical Processing Plant. Handling techniques for weighing and dissolving the slugs are described. Transferring … more
Date: July 14, 1961
Creator: Huff, G. A.; Doggett, I. L.; Fletcher, R. D. & Jacobson, M. E.
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report, November 1961

Description: Openation of a 6-in.-dia foam separation column with Sr/sup 89/ tracer and dodecylbenzenesulfonate as a surfactant and foaming agent was continued. The catalytic oxidation of H/sub 2/, CO, and CH/sub 4/ was studied using a nickel- chromepalladium ribbon catalyst. A Mark I prototype fuel assembly was sheared to within 1.5-in. of the end by modifying the gas hydraulic system of the shear. The force required to shear a highly carburized Mark I fuel assembly ductile tubing. Demonstration of the mec… more
Date: May 16, 1962
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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Irradiation of Metal-Fiber-Reinforced Thoria-Urania. Final Report- Metallurgy Program 6.2.4

Description: Randomly oriented fibers of either molybdenum or niobium were incorporated into hot-pressed pellets of 10, 30, and 50 wt% UO/sub 2/ in ThO/sub 2/ to improve thermal conductivity and thermal shock resistance. Pellets, 9.5 mm in diameter and 9.5 mm in length, were irradiated in NaK capsules, both bare and jacketed with Zircaloy-2, with the annulus between pellet and jacket filled with lead or helium. They were irradiated to burnups ranging up to 34 500 Mwd/T (1 0 x 10/sup 21/ fiss/cc) at central … more
Date: December 1, 1961
Creator: Neimark, L. A.; Kittel, J. H. & Hoenig, C. L.
Partner: UNT Libraries Government Documents Department
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Stress Corrosion of Type 304 Stainless Steel in Simulated Superheat Reactor Environments. [Part] 1. Informal Aec Research and Develoment Report 568-Tio-2

Description: A fuel jacket failure that occurred in May 1961 in the Type 304 stainless steel clad fuel element exposed in the Vallecitos Boiling Water Reactor superheated steam loop (SADE) was attributed to chloride stress corrosion cracking. In order to better understand the failure, a test program was carried out to try to reproduce the rapid stress corrosion attack in the simulated superheat reactor environment of the CL-1 superheat facility. The methods of corrosion testing under heat transfer condition… more
Date: February 26, 1962
Creator: Gaul, G. G.; Pearl, W. L. & Siegler, M.
Partner: UNT Libraries Government Documents Department
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The Preparation and Irradiation Behavior of Chemically-Nickel Plated Aluminum-Jacketed Fuel Elements

Description: Nickel plated aluminum was considered as a jacketing material for nuclear fuel elements as early as 1954, and both static and dynamic corrosion tests were carried out by Argonne National Laboratories and by Atomic Energy of Canada Ltd., employing demineralized water at temperatures of from 260 to 316{degree}C. Results generally indicated that the nickel had excellent corrosion resistance; however, difficulties were experienced in achieving satisfactory continuity and adhesion of the plate; subs… more
Date: September 5, 1961
Creator: Jacky, G. F.
Partner: UNT Libraries Government Documents Department
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Design and fabrication of target elements for PT-645-D

Description: Target elements were designed and built to fit into 1.25% U{sup 235} driver elements. These targets had an aluminum -- 0.583% lithium alloy core enriched to 63.5% in Li. The targets had a coextruded aluminum jacket as a tritium barrier and a Zircaloy jacket as a corrosion barrier to the 300 C reactor water.
Date: March 9, 1964
Creator: Tverberg, J. C.
Partner: UNT Libraries Government Documents Department
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Potential limitations of Al-Si bonded fuel elements

Description: Tests in which aluminum-jacketed, Al-Si bonded uranium fuel elements were baked at various temperatures have shown there is a time-temperature relationship for Al-Si layer decomposition. For heat transfer and secondary coolant barrier considerations, the extent of bonding layer deterioration during fuel element irradiation is important. Under present reactor operating conditions, Al-Si bonded fuel elements show evidence of internal bond deterioration, and to a lesser degree, external bond deter… more
Date: July 14, 1960
Creator: Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
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KER-3 operating report test K-3-13, PT-1P-363-A. Irradiation of ZR-2 jacketed enriched single tube fuel elements in the KER Loops

Description: The objective of the test was to evaluate the behavior during irradiation of nominally 1.739 inch OD, 1.074 inch ID, Zircaloy-2 jacketed single tube fuel elements with brazed end closures at operating conditions somewhat more severe than those expected for N Reactor fuel element outer tubes. The test elements were fabricated with the Be-Zr alloy brazed end closure planned for use on N Reactor fuel elements. Iron supports were used to minimize process tube scratching during charge-discharge.
Date: June 12, 1961
Partner: UNT Libraries Government Documents Department
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Fuel failure Lot KY-928-Q D Reactor

Description: On February 13, D Reactor sustained a bumpered enriched fuel element failure in process tube 3289. The element failed in the twenty-first position from the rear of the charge and was from lot KY-928-Q. Visual examination of the failed element indicated the failure mechanism to be cleavage of the uranium core. This conclusion was substantiated in part by the appearance of ``worm tracks`` in the aluminum jacket. The fuel failure was detected approximately three hours after the reactor had resumed… more
Date: February 25, 1966
Creator: Newell, L. J.
Partner: UNT Libraries Government Documents Department
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Parameter studies on the effect of pulse shape on the dynamic plastic deformation of a hexagon

Description: Results of a parameter study on the dynamic plastic response of a hexagonal subassembly duct subjected to an internal pressure pulse of arbitrary shape are presented. Plastic distortion of the cross section and large-deformation geometric effects that result in redistribution of the internal forces between bending and membrane stresses in the hexagon wall are included in the analytical model. Correlation procedures are established for relating permanent plastic deformation to simple properties … more
Date: October 1, 1973
Creator: Youngdahl, C. K.
Partner: UNT Libraries Government Documents Department
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Production test IP-226-A: Irradiation of enriched seven-rod cluster elements with twenty and thrity mil Zircaloy-2 jackets

Description: Seven enriched seven-rod cluster elements, three with thirty mil Zircaloy-2 jackets and four with twenty mil Zircaloy-2 jackets, will be irradiated at high temperature to an exposure of 4500 MWD/T. Coolant temperatures in the internal and external flow channels will be measured during irradiation.
Date: January 8, 1959
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Interim goal exposure plans for O-III-NB and O-III-EB material for B, D, DR and F reactors

Description: The purpose of this report is to recommend variable goal plans for natural and enriched bumper fuel elements, specifically for 0-III-NB and 0-III-EB materials, to be irradiated at the B, D, DR, and F Reactors. The average goal exposure for all bumper fuel elements at D Reactor was specified to be 900 MWD/T, with provisions being made for revision by normal procedures. Exposures for enriched bumper material at the B, M. and F Reactors were not specified in the PITA supplement authorizing chargin… more
Date: February 13, 1961
Creator: Bloomstrand, R. R.
Partner: UNT Libraries Government Documents Department
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Provisional process specifications for fabrication of KIT and KIIT target elements for K Reactor E-N load (PT-IP-561-C)

Description: It is necessary to modify existing I&E fuel element components to produce the requested target elements by early April 1963. Normally, a minimum of eighteen weeks is required to produce components of a new design. Therefore, the finished target elements will not be of the optimum designed dimensions. The proposed minor deviations have been approved by Reactor Engineering for the demonstration load. It is anticipated that only these test quantities will be fabricated to these dimensions. These p… more
Date: March 20, 1963
Creator: Padgett, E. V. Jr.
Partner: UNT Libraries Government Documents Department
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PT IP-183-A-98-FP: Evaluation of projection fuel elements for use in K Process tubes

Description: The objective of this test is to permit irradiation of projection fuel elements to evaluate jacket corrosion in areas of projection, to examine the effect of well-aligned fuel elements on hot-spot incidence, and to evaluate problems associated with projection slug usage in ribbed process tubes.
Date: November 5, 1958
Creator: Hall, R. E.
Partner: UNT Libraries Government Documents Department
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Production test IP-314-A measurement of fuel element temperature change as the result of film deposition

Description: The objective of this production test is to measure deposition on fuel element temperatures during irradiation in high pH water. A Zircaloy-2 jacketed natural uranium solid cylindrical fuel element with thermocouples located at various positions in the element and adjacent coolant channel will be irradiated in the KER Loops to measure the effect of crud film buildup on fuel temperature. Two 1.82 by 1.45 inch enriched 36 inch long tubular elements will be used to provide enough heat to permit op… more
Date: April 15, 1960
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Irradiated uranium fire hazard

Description: Earlier this year we briefly discussed the potential hazard of incurring an inadvertent uranium fuel element fire during discharge. This letter will provide data which will be of assistance to you in assessing the potential hazard, and in establishing charge-discharge procedures to minimize the probability of an irradiated fuel element lodged in the discharge area reaching aluminum jacket melting temperature without detection.
Date: February 16, 1961
Creator: Reid, R. W.
Partner: UNT Libraries Government Documents Department
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ADVANCED DESIGNS OF MAGNETIC JACK-TYPE CONTROL ROD DRIVE

Description: The magnetic jack is a device for positioning the control rods In a nuclear reactor, especially in a reactor containing water under pressure. Magnetic actuation precludes the need for shaft seals and eliminates the problems associated with mechanisms operating in water. It consists of a pressure shell, four sets of external stationary magnet coils (hold, grip, lift, pull down), and one Internal moving part (ammature) that impants linear motion to a cluster of rods. (W.L.H.)
Date: November 1, 1959
Creator: Young, J.N.
Partner: UNT Libraries Government Documents Department
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