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THE METABOLSIM AND TOXICITY OF RADIUM-223 IN RATS

Description: This report covers studies of the excretion and retention of 'tracer' and toxic doses of the 11.2-day Ra{sup 223} isotope, its acute toxicity (organ weight changes, gross and microscopic pathology, and Fe{sup 59} utilization by the bone marrow), and long-term histopathological changes and alterations in the hemogram.
Date: February 21, 1958
Creator: Durbin, Patricia; Durbin, Patricia W.; Asling, C. Willet.; Jeung, Nylan; Williams, Marilyn H.; Post, James. et al.
Partner: UNT Libraries Government Documents Department
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HAPO irradiation of capsules containing UO{sub 2} specimens

Description: A knowledge of the effect of reactor irradiation on the properties of UO{sub 2} is relevant to the design and evaluation of UO{sub 2} fuel elements for the PRTR. Of particular interest is the effect of reactor irradiation on the thermal conductivity of sintered UO{sub 2} and the type, mechanism, and extent of radiation damage in sintered UO{sub 2}. In the latter case the study of fractured surfaces of irradiated UO{sub 2} specimens is a method of determining the extent of radiation damage. It i… more
Date: February 17, 1958
Creator: Newkirk, H. W.; Millhollen, M. K. & Brite, D. W.
Partner: UNT Libraries Government Documents Department
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Fuels Preparation Department monthly report, January 1958

Description: This report describes the operation of the fuels preparation department for the month of January, 1958. Manufacturing, employee relations, process development, plant improvements, and financial operations are described.
Date: February 28, 1958
Partner: UNT Libraries Government Documents Department
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Status report -- Fuel element machining

Description: This report summarizes the design and development work completed since May, 1957; the current status of fuel element matching problems, and the plans for future modifications to improve machining techniques.
Date: February 12, 1958
Creator: Nickolaus, J. W.
Partner: UNT Libraries Government Documents Department
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Organic Moderated Reactor Experiment : Safeguards Summary

Description: Abstract: This report presents a description of the Organic Moderated Reactor Experiment (OMRE), of the hazards associated with this experiment, and all of the safeguards taken to ensure the safety of the operating personnel and the population of the surrounding area.
Date: February 1, 1958
Creator: Sletten, H. L. & Blue, L. R.
Partner: UNT Libraries Government Documents Department
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Fluidization in Tapered Beds

Description: Abstract: The concept of a tapered fluidized bed is explored briefly. Data are given showing that in bench scale apparatus a tapered bed gives better fluidization with some materials that are difficult to fluidize in a conventional cylindrical bed.
Date: February 14, 1958
Creator: Rossmassler, W. R. & Harris, R. L.
Partner: UNT Libraries Government Documents Department
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Surface Motion from an Underground Detonation

Description: Abstract: Surface and near-surface acceleration and strain were measured on a deep underground nuclear burst (Rainier Shot; 900 ft; 1.7 kt) to permit extrapolation of results to nuclear detonations of other yields under different test or employment conditions.
Date: February 28, 1958
Creator: Swift, L. M.; Sachs, D. C.; Brenner, J. L. & Wells, W. M.
Partner: UNT Libraries Government Documents Department
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Air-Gun Studies of Ferroelectric Materials (Second Printing)

Description: Specimens of two ferroelectric materials, barium titanate and lead-zirconate titanate, have been subjected to high dynamic stresses by impacting them with a projectile accelerated by an air gun. The purpose of these tests was to supplement information previously obtained using high explosives to stress the ferromagnetic materials.
Date: February 6, 1958
Creator: Ripperger, E. A. & Beck, A. F.
Partner: UNT Libraries Government Documents Department
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Increase in reactor power ratings through increased H{sub 2}O and D{sub 2}O flow rates

Description: As a part of the Productivity Increase Program, consideration should be given to further gains in 100 Area production levels which can be achieved by further increases in both light and heavy water flow rates. This memorandum presents a summary of the power level gains which should be achieved from the flow increases under consideration, a discussion of the costs and production losses which might apply, and a brief listing of some other considerations which might influence any decision to incre… more
Date: February 12, 1958
Creator: Holmes, R. C.
Partner: UNT Libraries Government Documents Department
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Evaluation of Countermeasure System Components and Operational Procedures

Description: Abstract: The objective of Project 32.3 was to evaluate some operational characteristics of a radiological shelter and to determine values for some countermeasures-system parameters.
Date: February 14, 1958
Creator: Strope, W. E.
Partner: UNT Libraries Government Documents Department
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Transistorized Trip Circuit for Critical Assemblies

Description: Abstract: A transistor trip circuit intended for critical assemblies and which provides maximum safety against human error or component failure is described.
Date: February 24, 1958
Creator: Wade, E. J. & Davidson, D. S.
Partner: UNT Libraries Government Documents Department
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ROLL CLADDING URANIUM-ZIRCONIUM AND URANIUM-ZIRCONIUM-NIOBIUM ALLOYS WITH ZIRCALOY-2 FOR PLATE-TYPE FUEL ELEMENTS

Description: Clad plate-type fuel elements containing U--5 wt.% Zr--1.5 wt.% Nb alloy cores integrally clad on all surfaces with Zircaloy-2 were developed for the Experimental Boiling Water Reactor (EBWR). These plates were prepared by roll bonding assembled components inside steel jackets at 850 deg C with 50% reduction in thickness to effect sound diffusion bonds at all component sufraces. To obtain reproducible sound bonds, uranium alloy core and cladding components were clean and free from surface conta… more
Date: February 1, 1958
Creator: Bean, C.H.; Macherey, R.E. & Lindgren, J.R.
Partner: UNT Libraries Government Documents Department
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Gas Saturated Run on the 400A-1 Pump

Description: A 1585 hr run was completed on the 400A-1 pump with a 0.4 m UC/sub 2/SO/ sub 4/ fuel solution as the pumped fluid, during which it was attempted to operate with gas bubbles in the solution. The gas content ranged from 0.56 ml/gm of solution to 1.189 mi/gm of solution and the gas other than CO/sub 2/, which was assumed to he nitrogen, varied from 0.39 ml/gm of solution to 0.966 ml/gm of solution. Because of uncertainties in the CO/sub 2/ solubility it cannot be stated conclusively that the liqui… more
Date: February 10, 1958
Creator: Payne, H. R.
Partner: UNT Libraries Government Documents Department
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A MOLTEN SALT NATURAL CONVECTION REACTOR SYSTEM

Description: Fuel-salt volumes external to the core of a molten-salt reactor are calculated for a system in which the fuel salt circulates through the core and primary exchanger by free convection. In the calculation of these volumes, the exchanger heights above the core top range from 5 to 20 ft. Coolants considered for the primary exchanger are a second molten salt and helium. External fuel holdup is found to be the same with either coolant. Two sets of terminal temperatures are selected for the helium. T… more
Date: February 1, 1958
Creator: Romie, F.E. & Kinyon, B.W.
Partner: UNT Libraries Government Documents Department
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METALLOGRAPHIC EXAMINATION OF COMPONENTS AND COUPONS FROM HRP IN-PILE LOOP L-2-17-PART I

Description: Metullographic examinations of representative reactor components and coupons from HRP in-pile loop L-2-l7 are reported. The loop operated for a total of 1l36.8 hours at 300 deg C in beam hole HB-2 of the LITR. The results are discussed and tabulated. Photographs are also included. (J.R.D.)
Date: February 18, 1958
Creator: Richt, A.E.
Partner: UNT Libraries Government Documents Department
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METALLOGRAPHIC EXAMINATION OF L6Z-114 IN-PILE AUTOCLAVE PINS

Description: During the examination of the pins from in-pile autoclave L6Z-114 it was noted that each of the doublenotched pins exhibited areas of increased corrosion while the exact duplicate single-notched pins did not. The two pairs of Zircaloy- 2 pins were identical in structure and thus the noted differencs in corrosive attack cannot be attributed to this factor. In the Zr-1.5% Sn--15% Nb pins the corrosive attack did not seem dependent on the slight variation in structure of the pins. (W. L.H.)
Date: February 1, 1958
Creator: Richt, A.E.
Partner: UNT Libraries Government Documents Department
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Progress Report No. 52 for December 1, 1957 Through February 28, 1958

Description: Some approximate values of the concentrations of the chlorine ion and the mean activity coefficients of HCl in Dowex 50, as functions of the mean activity of HCl are given. The KCl uptake by anion-exchange resins, Dowex 1 and 2, is plotted. Ion-exchange phase properties of HCl were determined from freezing point measurements. The thermodynamic acid dissociation constants of HClO/sub 4/, HCl, HNO/sub 3/, HBr, and HGaCl/sub 4/ in water-saturated bis(2- chloroethyl) ether, were obtained from coudu… more
Date: February 28, 1958
Partner: UNT Libraries Government Documents Department
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THERMAL FLUX PROGRAM FOR A SLAB SYSTEM

Description: A program is described for computing a quantity, Q, proportional to the neutron scalar flux, in an infinite heterogeneous slab system. The system is generated by a two-region unit cell. Q is the average track length per unit length, in a given interval, arising from the neutron traffic established by a spatially distributed monenergetic source. The program is coded for the IBM 704 computer. (auth)
Date: February 1, 1958
Creator: Beeler, J.R. & Popp, J.D.
Partner: UNT Libraries Government Documents Department
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HRE-3 PRESSURIZER DESIGN

Description: A conceptual design is presented for the HRE-3 core and blanket pressurization systems. In general, the systems are similar to the preliminary designs previously described. Flowsheets, conceptual sketches, and specification = for the major components are included. Estimation oi the D/sub 2/ concentration in the blanket is treated in detail. The design appears to be safe with regards to the d/sub 2/ explosion hazard. (auth)
Date: February 1, 1958
Creator: Bolger, J.C. & Maak, R.O.
Partner: UNT Libraries Government Documents Department
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DAREX PROCESS: BATCH DISSOLUTION AND CHLORIDE REMOVAL STEPS FOR YANKEE ATOMIC FUEL

Description: In laboratory scale experiments dilution of a Darex dissolver product from the integral dissolution of Yankee Atomic fuel specimens with at least an equal volume of 15.8M HNO/sub 3/, followed by distillation, produced a solvent extraction feed containing less than 50 ppm of chloride. Properly designed chloride stripping and nitric acid rectification columns are capable of conserving acids for recycle to the dissolver and chloride removal still. In initial experiments about 87% of the nitric aci… more
Date: February 21, 1958
Creator: Goode, J.H. & Flanary, J.R.
Partner: UNT Libraries Government Documents Department
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