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Heavy Water Power Reactor Program Monthly Report: July 1964

Description: Report documenting progress on the Heavy Water Power Reactor Program including the discontinuation of all 16 long-term creep tests at Battelle Memorial Institute, failed CANDU assembly for the irradiation program, and data on the CANDU assembly for the heavy water components test reactor.
Date: August 21, 1964
Partner: UNT Libraries Government Documents Department
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Heavy Water Power Reactor Program Monthly Report: June 1964

Description: Report documenting progress on the Heavy Water Power Reactor Program including the dismantling of the CANDU on-power refueling machine in preparation for shipping, updates on multiple different studies on fluid dynamics and heat transfer, and completion of design and cost estimates for Sargent and Lundy's 300 MWe prototype reactor.
Date: July 21, 1964
Partner: UNT Libraries Government Documents Department
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Heavy Water Power Reactor Program Monthly Report: December 1963

Description: Report documenting progress on the Heavy Water Power Reactor Program including multiple progress points across different fluid dynamic and heat transfer tests, preliminary engineering on the prototype reactor design, and the operating history of the heavy water components test reactor.
Date: January 21, 1964
Partner: UNT Libraries Government Documents Department
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Heavy Water Power Reactor Program Monthly Report: May 1961

Description: Report documenting progress on the Heavy Water Power Reactor Program including progress made in research and development areas such as requests to perform research and development on ultrasonic nondestructive testing technique of thin-wall Zircaloy sheathing, continued studies of various alternatives for complete compatibility of the AMD in-line refueling system with both the physical limitations, and the investigation of combinations of separate function tubes.
Date: June 21, 1961
Partner: UNT Libraries Government Documents Department
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Effect of 1200ºF Sodium on Austenitic and Ferritic Steels Progress Report: December 1963

Description: This is the fortieth progress report from December 1963 detailing progress made in areas such as the continued progress on topical reports for Tests 1 and 2, operational difficulties when conducting the main test for Test 3, and partial completion of Test 4.
Date: January 21, 1964
Creator: Andrews, R. C.; Barker, K. R. & Werner, R. C.
Partner: UNT Libraries Government Documents Department
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Effect of 1200ºF Sodium on Austenitic and Ferritic Steels Progress Report: May 1963

Description: This is the thirty-third progress report from May 1963 detailing progress made in areas such as the completion of tests on the determination of the physical propertied of stainless steel specimens in low oxide sodium, helium and air, the continued progress of metallurgical examination of the specimens, and ongoing examinations between the incomplete physical property data and the environment in which the specimens were run.
Date: June 21, 1963
Creator: Andrews, R. C.; Barker, K. R. & Werner, R. C.
Partner: UNT Libraries Government Documents Department
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Numerical Three Dimensional Temperature Analysis Of The EGCR Fuel Rod

Description: The temperature field in an outer rod of the EGCR fuel assembly is presented. The numerical analysis has taken account of the three dimensional spatial dependence of the thermal neutron flux and has considered the four regions involved, that is, fuel pellets, ceramic disc, steel end caps, and cladding. The convective heat transfer coefficient and fluid temperature were considered constant over the 2.185 in. of rod length studied.
Date: March 21, 1960
Creator: Epel, L. G.
Partner: UNT Libraries Government Documents Department
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Some Experiments On The Accuracy Of Thoria Slurry Samples

Description: Tests were performed on a thoria slurry flowing in a 3 inch diameter pipe to determine the magnitude of the possible error involved in the sampling process. Evidence indicates that a correct sample is obtained by withdrawing the sample isokinetically (i.e. by facing the sampler into the flow and adjusting the sampler velocity to match the ambient velocity) provided that the sampler is larger than some minimum diameter that is dependent on the mean eddy length and/or the mean particle size.
Date: April 21, 1960
Creator: Wichner, R. P.
Partner: UNT Libraries Government Documents Department
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Thorium Breeder Reactor Study: Optimization of a Blanket Processing Cycle To Obtain Minimum Total Inventory in a Chemical Reprocessing Cycle

Description: A reactor which produces U233 from Th232 needs to operate with as low total inventory of fissionable and potential fissionable material, U233 and Pa233, as possible in order to achieve short doubling times. The blanket processing cycle can be optimized to give minimum total inventory by the proper arrangement of Pa233 decay and U233 extraction steps. The optimization consists in choosing the proper storage time associated with each processing step. Graphs are presented correlating the optimized… more
Date: January 21, 1960
Creator: Carter, W. L.
Partner: UNT Libraries Government Documents Department
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Research on Krypton 85 : Seventh Monthly Progress Report Covering December 1, 1959 to December 31, 1959

Description: Work during this report period includes a continuation of the study of the effect of krypton 85 on the polymerization of styrene; an attempt at evaluation of the polymers produced; and the effect of krypton radiation on the electrical properties of gases, such as the rare gases, and nitrogen, and oxygen. the results obtained are summarized in the report.
Date: January 21, 1960
Creator: Miller, H. S.; Marancik, W. G. & Zufall, J.
Partner: UNT Libraries Government Documents Department
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Preparation and Specifications of Miniature Fermi Reactor Core B Fuel Specimens for Irradiation Testing

Description: The preparation of miniature plate specimens containing dispersions of 33.2 wt % UO2 in type 347 stainless steel for irradiation testing is described. These plates stimulate the prototype roll-bonded stainless steel clad composite plates intended for the Core B fuel element of the Enrico Fermi sodium-cooled reactor. The significant characteristics of the fabricated irradiation specimens are tabulated. The samples will be used to determine the irradation behavior of 33.2 wt % UO2 at temperatur… more
Date: April 21, 1961
Creator: Cherubini, J.H. & Williams, R.C.
Partner: UNT Libraries Government Documents Department
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EPITAPH - A Reactor Fuel Cost Calculation

Description: EPITAPH is an economics calculation which was written to investigate nuclear fuel cycle costs as a function of various cost parameters. The fuel cost has been broken down so that the user may easily study the effect of various cost parameters on the total fuel cost.
Date: March 21, 1961
Creator: Bennett. L.L.
Partner: UNT Libraries Government Documents Department
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Fission Product Transport Through Graphite Matrices

Description: The transport of fission products from points of origin in unclad graphite matrix-types fuels to the reactor circulating system involves, as one of the steps, diffusion through the graphite matrix to the fuel element surface. An important problem is the determination of the effective transport rates of the various mobile elements (e.g., Xe, Kr, I, Br, Cs, Rb, and Te) and their daughter products of interest (Sr, La, Ba, Ca, Nb, Y and Te) through various graphites suitable for use as fuel elemen… more
Date: March 21, 1961
Creator: Korsmeyer, R. B.
Partner: UNT Libraries Government Documents Department
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Determination of the Six Turbulent Reynolds' Stresses by the Hot Wire Method for Arbitrary Intensity and Geometry with Special Application to Axisymmetric Flow

Description: A relationship is derived the mean square fluctuating current of a hot wire anemometer and the sic turbulent Reynolds stresses in the stream-coordinate system without employing the usual low turbulent intensity approximation. The relatively simple result is a consequence of assuming proportionality between the wire current reading and the perpendicular velocity component instead of the non-linear dependence required by King's law. The assumption is valid for instruments equipped with the proper… more
Date: February 21, 1961
Creator: Wichner, R. P. & Peebles, F. N.
Partner: UNT Libraries Government Documents Department
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HFIR Beryllium Reflector Preliminary Design Report

Description: This report considers the HFIR reflector design criteria and presents a summary of the reflector design. The reflector type chosen as complying best with the established criteria consists of a 3 in. thick removable beryllium annulus utilizing four concentric cylinders with cooling water flowing through the annuli between cylinders, and an outer 9 in. thick permanent beryllium annulus with axial circular coolant holes. Reflector support structures and experimental facilities are described and pr… more
Date: February 21, 1961
Creator: Hilvety, Neil
Partner: UNT Libraries Government Documents Department
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Pressure Vessel Exposure to Fast Neutrons

Description: In a gas-cooled reactor operating at very high power density the thickness of the reflector may be determine by the requirement that the steel pressure vessel be protected from an excessive dose of fast neutrons, rather than by the usual requirements of neutron economy and power distribution. It is important the the reflector not be made thicker than necessary, since an increase in pressure vessel diameter can result in a marked increase in cost, as well as a decrease in the permitted gas pres… more
Date: January 21, 1960
Creator: Carlsmith, R. S.
Partner: UNT Libraries Government Documents Department
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Equipoise-2: A Two-Dimensional, Two-Group, Neutron-Diffusion Code for the IBM-7090 Computer

Description: Equipoise-2, a two-dimensional, two-group neutron-diffusion code in R-Z geometry, has been programmed for the IBM-7090 computer. This code was designed to permit the running of large numbers of cases without requiring excessive machine time. Typical running times are of the order of one to three minutes per case for a 1000-point problems. The maximum number of mesh points that can be used is 1444.
Date: November 21, 1960
Creator: Fowler, T. B. & Tobias, Melvin
Partner: UNT Libraries Government Documents Department
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Preliminary Analog Computer Study of the Small EGCR In-Pile Loops

Description: The ORNL analog computer was used to simulate four widely different experiment conditions in the small EGCR in-pile loops. Various control and safety systems were evaluated in each case. Curves are included which show the response to postulated accidents and component failures. The results indicate that one standard control and safety system will probably be adequate for a wide variety of test conditions.
Date: September 21, 1960
Creator: Ball, S. J. & Beasley, E. G.
Partner: UNT Libraries Government Documents Department
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Precipitation of Crystalline Uranium and Thorium Peroxide: Applications to Fuel-Element Oxides and Purifications

Description: Departures from the usual precipitation method produced crystalline uranium peroxide in several forms. Three types of segregated needles were used in the preparation of three pellets for pellet-type elements. Densities of the pellets ranged from 93 to 97% of theoretical, depending on conditions of precipitation.
Date: September 21, 1960
Creator: Whetsel, H. B. & Dean, O. C.
Partner: UNT Libraries Government Documents Department
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Xenon Chase and Samarium Burnup in the HFIR

Description: Further calculations have been made in connection with xenon and samarium transients in the HFIR, including associated variations in the power distribution. Of particular interest was the possibility of burning samarium out of a core that has been shutdown for a prolonged period of time after eleven or more days of operation at full power. The results indicate that such a core between the ages of 11 and 13 days old can complete the normal 15-day cycle after samarium burning times of zero to 50 … more
Date: July 21, 1961
Creator: Cheverton. R. D.
Partner: UNT Libraries Government Documents Department
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Erosion Experiments of Powder Compacted Uranium Dioxide Under Dynamic Steam Flow (Preliminary Report)

Description: Experiments were carried out to determine the erosion, oxidation and dimensional characteristics of purposely defected fuel elements containing unsintered UO2 powder prepared by the swaging technique. The experiments were conducted in an out-of-reactor loop under superheat conditions of pressure, temperature, flow velocity and steam chemical composition.
Date: March 21, 1961
Creator: Spalaris, C. N.; Comprelli, F. A. & Siegler, M.
Partner: UNT Libraries Government Documents Department
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High Energy Separated Beam for the 80" Chamber

Description: The angular separation of two particles of different mass obtained by means of a crossed electric and magnet field spectrometer is proportional to the length of the separator and to the electric field but inversely proportional to the cube of the momentum. The availability of the new A.G.S. separators will permit a three fold increase in the length of separator over the existing 3.7 Bec/c beam, while the maximum electric field is expected to be approximately the same. It is, therefore, clear th… more
Date: March 21, 1962
Creator: Skillicorn, Ian & Webster, Medford S.
Partner: UNT Libraries Government Documents Department
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