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THE PHYSICS DESIGN OF THE EBR-II
The physics design problems of the EBR-II are summarized. These include analysis of the EBR-II engineering design as well as applicable zero-power critical experiments. Pertinent reactor safety problems are reviewed. Safety considerations bearing on normal plant operation and manipulations within the reactor are emphasized. The implication of controlled in-pile meltdown experiments is considered. Irradiation damage and metallurgical phase phenomena are summarized and related to reactivity. The nuclear performance of the system is considered in terms of actual plant operation. The predicted shift of both power and reactivity from core to radial reflector is described. (auth)
Date:
July 1, 1961
Creator:
Loewenstein, W.B.
Object Type:
Report
System:
The UNT Digital Library
BIOLOGICAL AND MEDICAL RESEARCH DIVISION SUMMARY REPORT, JANUARY-DECEMBER 1960
Separate abstracts were prepared for 43 sections of this report. (C.H.)
Date:
May 1, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Steady State and Transient Thermal and Hydraulic Analysis of SM-2 Termination Report
Thermal characteristics of the SM-2 core were analyzed at steady state and loss of flow conditions. For steady state operation, the steady state code STDY-3 was used. For transients during-a loss of flow acident, ART-02, a onedimensional code, was used. This analysis indicated the SM-2 core is safe from burnout under steady state operation at design power level (28 Mw(t)) because no nucleate boiling exists, and the minimum burnout ratio is above 2.0. The core is safe from burnout under loss of flow transient because the minimum burnout ratio in the hottest element channel of 1.82 is above the minimum design criteria of 1.5. (auth)
Date:
September 1, 1961
Creator:
Segalman, I. & Bradley, P. L.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Hydrocarbon Diluents for the Purex Process
Forty-nine hydrocarbon products were evaluated in the laboratory in a search for a highly stable diluent for the organic extractant used in a radiochemical separations plant. The formation of zirconium ligands during chemical and radiolytic degradation increased with boiling point for isoparaffinic producte but was approximately constant for n-parafiins. Of those materials that met the local flash point specification, the n-parafiins were superior. (auth)
Date:
November 1, 1961
Creator:
Dennis, B. P. & West, D. L.
Object Type:
Report
System:
The UNT Digital Library
ELECTROSTATIC ION-CYCLOTRON PLASMA INSTABILITIES IN A TWO-FLUID HYDRODYNAMIC THEORY
None
Date:
September 1, 1961
Creator:
Wimmel, H.K.
Object Type:
Report
System:
The UNT Digital Library
Periodic Waste Disposal System Material Balance Test. Core 1, Seed 2. Test Evaluation T-641317. Section 1
A test was carried out to determine the adequacy of storage capacity and operating procedures of the radioactive waste disposal system during a normal reactor plant warmup. The capacity and operating procedures were found to be adequate. It was impossible to perform a complete material balance based on existing level instrumentation and using the data required by the test procedure. Approximately 21,290 gal. of waste were received in the system and 13,210 gal. were discharged to the river with a total activity of 1200 mu c. A quantity of 6,670 gal. of reactor coolant effluent was processed. Approximately 634 lb of combustible waste were incinerated. (M.C.G.)
Date:
June 30, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
A Simulation of the EGCR Steam Generator
An analog model of the EGCR steam generator was developed and operated on the ORNL analog computer as part of a program to simulate the operation and control of the EGCR reactor plant. Equilibrium operation and the transient response of the steam generator unit to system perturbations were studied. A simultaneous solution of the basic heat transfer equations representing the performance of the unit was obtained. The model was operated initially at steady- state conditions, and then perturbations were made to gas flow, gas inlet temperature, and steam throttle valve position. The response characteristics of the model during the transients were recorded. The steam generator gas outlet temperature showed a marked degree of insensitivity to changes in gas inlet temperature. The effect of gas flow changes on gas exit temperature was slightly more pronounced. The transient behavio-r of the unit was reasonable, and the model developed indicated satisfactory operation within the design range of 20 to l00% of full power. (auth)
Date:
October 1, 1961
Creator:
Yarosh, M.M. & Ball, S.J.
Object Type:
Report
System:
The UNT Digital Library
AN ANALYSIS TO DETERMINE THE PERCENTAGE OF HELIUM BYPASSING THE CORE DUE TO THE REFLECTOR SEALING SYSTEM DURING NORMAL OPERATION OF THE HTGR
The percentage of helium which will bypass the core if the reflector system shown is used is predicted. It is estimated that nominally about 0.1 to 0.2% of the total flow will bypass the core, which is not considered excessive. The most difficult parameter to determine was Z, the gap between the sealing surfaces. The method used to predict Z is presented. The effect of bowing due to a temperature gradient across the seals is discussed. (auth)
Date:
November 15, 1961
Creator:
Nimtz, F.B.
Object Type:
Report
System:
The UNT Digital Library
Data Telemetry Package Powered by Strontium-90 Fueled Generator. Final Report
An automatic, nuclear powered, meteorological data transmitting radio station was designed and fabricated for unattended service at a remote Arctic location. The system automatically measures air temperature, barometric pressure, wind direction, and two wind speed averages- Once every three hours it transmits this data in binary digital form, on two frequencies, to a manned receiving station (also designed as a part of this contract) where it is recorded on a two-channel recorder. Temperature, wind direction and barometric pressure are read at the instant of transmission; wind speed is averaged during an eightminute interval and a one-minute interval immediately preceding transmission. A five-watt thermoelectric generator was designed, manufactured and electrically tested for a period of 8.5 months. In May 196l, the generator was fueled with a capsule containing 17,500 curies of Sr/sup 90/. Electrical performance tests were conducted with the integrated system of generator, converter and batteries prior to isotope loading and also after Sr/sup 90/ fueling operations. Weather station compatibility tests were performed in June 1961 and the complete power supply and station housing were packaged for overseas shipment in July 1961. Current residence of the Sr/sup 90/ generator is on Axel Heiberg Island in the Arctic region. (auth)
Date:
September 1, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
SORPTION OF URANIUM ON ZIRCONIUM OXIDE
The sorption of the ions of uranium, copper, and nickel on hydrous zirconium oxide was investigated at temperatures from 25 to 250 deg C. The experiments were performed by equilibrating 5 ml of the test solution with 0.5 g of zirconium oxide in a titanium autoclave, which was heated by means of a rocking furnace. The sorption of uranium was affected by characteristics of the zirconium oxide, temperatare of equilibration, and concentrations of uranium and of free acid in the uranyl sulfate solutions. Conclusions are drawn concerning the relationship between each of these factors and uranium sorption. (auth)
Date:
September 13, 1961
Creator:
Goldstein, G.
Object Type:
Report
System:
The UNT Digital Library
Heat Transfer With Laminar Flow in Concentric Annuli With Constant and Arbitrary Variable Axial Wall Temperature
An analysis has been performed to determine the heat transfer characteristics for laminar forced-convection flow in a concentric annulus with prescribed surface temperatures. Three distinct problems were considered: (a) wall temperature prescribed at both the inside and outside wall; (b) inside wall temperature prescribed and the outside wall insulated; and (c) inside wall insulated and outside wall temperature prescribed. The solution for temperature distribution was similar to that obtained by Graetz for laminar heat convection in a pipe with uniform wall temperature. Expressions are presented for heat flux, mixing cup temperature, and Nusselt number as a function of downstream position. Eigenvalues and eigenfunctions were computed for values of the ratio of the inside to the outside radii for the boundary conditions. Mixing cup temperatures, local and fully developed Nusselt numbers, and thermal entry lengths are presented graphically. The solution of Problem (a) was extended to the situation in which the temperatures of the inside and outside walls of the annulus are not equal. By utilizing the method of superposition and the solutions already obtained for Problem (a), the temperature distributions were determined. By way of illustration, heat fluxes were calculated for several values of the temperature ratio (T/sub wi/-T/sub 0/)/(T …
Date:
December 1, 1961
Creator:
Viskanta, R.
Object Type:
Report
System:
The UNT Digital Library
PL FINAL DESIGN REPORT. VOLUME II. PLANT DRAWINGS
Plant drawings for the final design for the Army Reactor (PL-2) are presented. Two hundred and twenty-eight figures are included. (M.C.G.)
Date:
June 30, 1961
Creator:
Combustion Engineering, Inc. Nuclear Div., Windsor, Conn.
Object Type:
Report
System:
The UNT Digital Library
A DESCRIPTION OF INTEGRAL PHYSICS DATA FOR FAST REACTOR DESIGN
Integral physics data for fast reactor design are discussed. The measurements needed include those of critical mass, shape factor, detector ratios, neutron spectra, material replacement experiments, reflector savings, neutron lifetime, Rossi- alpha , and similar quantities. Topics covered include Pu- and U/sup 233/-fueled systems, highly enriched U/sup 235/ systems in optimum geometry, uranium cores of various enrichments and dilutions, extreme geometry critical experiments, specific reactor systems, core mockup inhomogeneities, spectral studies and detector ratios, uranium equilibrium spectrum data, materialreplacement measurements, fast reactor dynamics, and suggested future experiments and experimental programs. (M.C.G.)
Date:
July 1, 1961
Creator:
Loewenstein, W.B. & Meneghetti, D.
Object Type:
Report
System:
The UNT Digital Library
DEVELOPMENT OF RING-JOINT FLANGES FOR USE IN THE HRE-2
Ring-joint flanges were studied in thermal-cycle tests as part of the development work associated with Homogeneous Reactor Experiment No. 2 (HRE-2). The purpose of this study was to provide criteria for design, installation, and operation of joints that would remain leaktight under reactor operating temperatures and pressures. Joints ranging from 1/2 in., l500 lb to 4 in., 2500 lb and with various initial bolt loadings were cycled between room temperature and 636 deg F. It was demonstrated that when joints were made up to HRE-2 standards and specifications, leak rates of less than 0.25 x 10/sup -3/ g of water per day per inch of gasket pitch diameter could be routinely- attained. Undamaged gaskets could be reinstalled or new gaskets used with equal probability of achieving acceptable leak rates. The system installed in HRE-2 was provided with a high-pressure buffer system to ensure that the small amount of leakage to the cell would be nonradioactive. (auth)
Date:
December 21, 1961
Creator:
Robinson, J. N.; Lundin, M. I. & Spiewak, I.
Object Type:
Report
System:
The UNT Digital Library
A Summary of Industrial Accidents in USAEC Facilities
The summary includes descriptions of serious accidents for l959 and 1960, AEC industrial injury frequency rates, criticality accidents, radiation exposures, accidents involving radioactive materials in AEC activities during 1959 and 1960, and accidents involving fatalities in AEC activities during l959 and 1960. (B.O.G.)
Date:
December 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Development of Remote Metallographic Techniques for Irradiated Materials
A remote metallographic facility is in operation at Argonne National Laboratory. Techniques relative to better contamination control and equipment operation were developed. The techniques used for microscopic examination of irradiated materials were standardized with variations only in the final polishing steps, and detailed procedures are given for several alloys. The procedures used for macroscopy vary from sample to sample, and new procedures are developed as required to suit each particular problem. (auth)
Date:
September 1, 1961
Creator:
Carlander, R.
Object Type:
Report
System:
The UNT Digital Library
Economic Analysis of Replacement Cores for SM and PM Type Reactors
An economic analysis is presented for the fabrication of replacement cores for SM and PM type reactors, including analysis of various core types and core fabrication technologies. The analysis indicates that major savings are possible by utilizing Type 3 cores (40-mil plates, 25 wt% UO/sub 2/, welded assembly) in all SM and PM type reactors, and that significant savings are possible by multiple core procurement and reprocessing, and relaxation of cobalt and tantalum requirements in Type 347 stainless steel. (auth)
Date:
October 1, 1961
Creator:
Wilder, A. S.
Object Type:
Report
System:
The UNT Digital Library
CURRENT STATUS OF THE AC IONIZATION CHAMBER
ABS>The design concept of an a-c ionization chamber and its supporting electronics is described. Several designs are possible and the sensors can be tailored to specific requirements when necessary. Mode of operation, signal voltage development, and switching frequency are discussed. High-sensitivity operation is described. Requirements for high-temperature, power-level operation are outlined. (M.C.G.)
Date:
July 1, 1961
Creator:
Rusch, G.K.
Object Type:
Report
System:
The UNT Digital Library
Interim Report on the Development of an Air Pulser for Pulse Column Application
The Idaho Chemical Processing Plant for several years has been studying various pulsing systems, used in extraction columns for processing irradiated nucIear fuel elements, in an effort to eliminate the mechanical difficuittes in present pulsing systems. An air puising system has been demonstrated, and a discussion is given of experimental work, pulser design, and plant operational experience with this system. It is concluded, from work completed thus far that air puising of extraction columns is a considerable improvement over other systems. (auth)
Date:
September 22, 1961
Creator:
Weech, M. E.; P'Pool, R. S. & MacQueen, D. K.
Object Type:
Report
System:
The UNT Digital Library
AN INVESTIGATION OF THE HIGH-TEMPERATURE PROPERTIES OF THE AISI TYPE 502 STEEL
None
Date:
November 28, 1961
Creator:
Martin, W. R. & McCoy Jr., H. E.
Object Type:
Report
System:
The UNT Digital Library
Sodium Iodide and Sodium Iodide Crystals: Their Use in Scintillation Counting and Spectrometry. A Bibliography
References (297) were obtained from Applied Science and Technology Index, Chemical Abstracts, Dissertations in Physics, Nuclear Science Abstracts, and Science Abstracts, Section A. The period covered was from 1948 through l960. The arrangement is alphabetical by title; personal author and subject indexes are included. (P.C.H.)
Date:
October 1, 1961
Creator:
Kepple, R.R.
Object Type:
Report
System:
The UNT Digital Library
A Summary of Shielding Constants for Concrete
The present knowledge of the shielding constants of concrete is summarized. The densities, elemental compositions, and mixes, where available, are given for a wide range of concretes. From these data, various constants useful for shielding calculations were computed. These constants include the removal cross sections, total cross sections, average thermal neutron absorption cross sections, thermal neutron diffusion coefficients, reciprocal thermal neutron diffusion lengths, total gamma-ray linear attenuation coefficients, gamma-ray energy absorption linear attenuation coefficients, the effective atomic numbers for the determination of buildup factors, and the capture gamma-ray spectra. Experimental results are included where available. (auth)
Date:
November 1, 1961
Creator:
Walker, R.L. & Grotenhuis, M.
Object Type:
Report
System:
The UNT Digital Library
REMOTE DISSOLUTION AND ANALYTICAL PROGRAM FOR IRRADIATED THORIUM
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 and sampling apparatus as well as sampling techniques for the dissolved material are discussed. Analytical data obtained are tabulated. Abstracts of analytical methods for uranium concentration and isotope ratio, aluminum, thorium, cesium, and cerium are given. (auth)
Date:
July 14, 1961
Creator:
Huff, G. A.; Doggett, I. L.; Fletcher, R. D. & Jacobson, M. E.
Object Type:
Report
System:
The UNT Digital Library
Tertiary Blast Effects: The Effects of Impact on Mice, Rats, Guinea Pigs and Rabbits. Technical Progress Report
A total of 455 mlce, rats, gulnea plgs, and rabbits was subjected to lmpact at velocitles ranglng between 25 ft/sec and 51 ft/sec. The deslred velocities were generated by allowlng the anlmals to free-fall from various helghts to a flat concrete pad. The ventral surface of each anlmal was the area of impact. Problt analyses of the 24-hr mortallty data ylelded LD/sub 50/ lmpact veloclties with 95% confldence limits as follows: mouse, 39.4 (37.4 to 42.0) ft/ sec; rat, ft/sec; and rabbit, 31.7 (30.2 to 33.3) ft/sec. The LD/sub 50/ figures for the mouse and rat were slgnificantly higher, statlstically, than those for the gulnea plg and rabblt. The small spread ln the LD/sub 50/ values suggested little variation ln the tolerance of blologlcal systems to impact. Further, the steepness of the mortallty curves lndicated a narrow survlval range to lmpact. Extrapolatlon of the experimental data to the 70 kg anlmal yielded a predicted LD/ sub 50/ impact velocity of 26 ft/sec (18 mph). Literature relevant to the human case was revlewed and the tentative appllcabllity of the predlcted flgures to adult man ls discussed. (auth)
Date:
February 28, 1961
Creator:
Richmond, D. R.; Bowen, I. G. & White, C. S.
Object Type:
Report
System:
The UNT Digital Library