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An evaluation of simple iron-water radiation shields and radiation measurements within concrete-lined and -capped pits

Description: Program 3 of Operation BREN consisted in a study of the performance of biological shields composed of various arrangements of steel, water, and borated polyethylene in spherical, cubical, and parallelepipedal geometries. Studies were also made of the radiation levels within concrete-lined and -capped pits, 4 ft in dia and 8 ft deep. The principal radiation source was the ORNL Health Physics Research Reactor, an unshielded, unreflected, 90 wt % U-10 wt % Mo, cylindrical bare-metal assembly. It was supported at heights ranging from 27 to 1500 ft by a hoist car riding outside of a 1527-ft-high steel tower. A 1200-curie Co/sup 60/ gamma-ray source, similarly supported, was substituted for the reactor for some measurements. The work reported includes measurements of fast-neutron and gamma-ray dose rates and thermal-neutron fluxes in air and within the various shields, using the reactor source, measurements of gamma-ray dose rates in air from the Co/sup 60/ gamma-ray source, and measurements of gamma-ray pulse-height spectra within the pits, also employing the Co/sup 60/ source. 8 refs., 33 figs., 29 tabs.
Date: July 31, 1964
Creator: Muckenthaler, F. J.; Jung, L.; Blosser, T. V.; Freestone, R. M. Jr. & Miller, J. M.
Partner: UNT Libraries Government Documents Department
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Performance Characteristics of a Liquid Metal MHD Generator

Description: Report issued by the Argonne National Laboratory discussing the performance of magnetohydrodynamic generators. As stated in the abstract, "an experimental study was made of the performance characteristics of a liquid metal MHD generator utilizing single-phase sodium-potassium and two-phase sodium-potassium-nitrogen fluids. The purpose of this study was to compare the generator performance with theory for single-phase flow and to determine the effects of the introduction of the gaseous phase on the generator output and efficiency" (p. 9). This report includes tables, illustrations, and photographs.
Date: July 1964
Creator: Petrick, Michael & Lee, Kung-You
Partner: UNT Libraries Government Documents Department
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Modular Nuclear Testing Concept

Description: The continuing concern with efficient utilization of manpower at the Nevada Test Site (NTS) and the seemingly high cost of individual nuclear shots, together with the recent evolution of the L-12 scope, generated some fresh thoughts concerning more efficient procedures for the `average` test. Every time anyone looks at the problem., they tend to analyze the existing conventional approach and try to find the one or two most expensive and `lossy` factors in the can of worms. Usually this turns out to be a problem within the realm of specialization of the particular analyst! People not so directly concerned with the program tend to look for, or wish for, or even `invent` miracles`. Our present techniques appear to be the sum (and possibly even the product) of many small contributions which have all been beaten down to the same level of importance. Such a situation in any systemic problem is usually symptomatic of the need for fairly violent departures in the aver-all system approach, at least in thinking. This report proposes and details a modular nuclear testing concept.
Date: July 1, 1964
Creator: Wouters, L. F.
Partner: UNT Libraries Government Documents Department
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UO2 Pellet Thermal Conductivity From Irradiations With Central Melting

Description: Abstract: Continued irradiation experience under the AEC - Euratom, UO2 High Performance Program provided five separate and distinct sets of data on UO2 thermal conductivity. Four of these results are expressed in terms of the value of the thermal conductivity. The first two of these measurements were applicable -- strictly -- to poly crystalline UO2. Recently, three additional sets of measurements have been obtained -- all pertinent to UO2 after the formation of large columnar grains. The extent of melting in the experiments on which the results are based ranges from slight, to greater than 70 percent of the fuel cross section. The conclusions from all of these thermal conductivity measurements considered together are: (1) The true value of the UO2 conductivity integral form 0 degrees C to melting (2805 - 15 degrees C) lies in the range from 90 to 96 W/cm. The most probable value is closer to 90 W/cm. To ensure no central melting and the associated clad swelling the maximum thermal performance level for solid pellet, UO2 fuel rods should not exceed 90 W/cm. (2) Any improvement in thermal conductivity due to the formation of large, columnar UO2 grains is small and not detectable within the experimental accuracy of the measurement, i.e., 3 to 4 W/cm.
Date: July 1964
Creator: Lyons, M. F.; Coplin, D. H.; Pashos, T. J. & Weidenbaum, B.
Partner: UNT Libraries Government Documents Department
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Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: April 1 - June 30, 1964

Description: A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. Quarterly progress: Project fuel fins irradiated to 1860, 3000, and 5300 MWD/T have been successfully sampled in the Radioactive Materials Laboratory. The samples have been dissolved and aliquots delivered to Chemistry for Mass Spectrometry and burnup determination. The first Stanford Pool Irradiation indicated that there was some inconsistency in the thermal flux and the near thermal epithermal flux. The experiment was repeated, increasing the number of foil wheel positions from two to three. The data from the second measurement are being reduced. The EPITHERMOS code modification has been completed. Comparisons between the results computed by the code and experimental data show much improved agreement. The metallographic photomicrographs of a polished half-pellet from rod F, irradiated to 5000 MWD/T, show structure very similar to that shown by the pellet from rod S, irradiated to 1860 MWD/T.
Date: July 15, 1964
Creator: Robkin, M. A.
Partner: UNT Libraries Government Documents Department
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Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 7

Description: The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nuclear Power Station located at Sessa Aurunca (Campania, Italy). One task is in progress: Task I - Data Logging and Computer System. The work on the other tasks is being planned and initiated.
Date: July 1, 1964
Creator: Howard, C. L.
Partner: UNT Libraries Government Documents Department
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Transition Boiling Heat Transfer Program; Sixth Quarterly Progress Report, April - June 1964

Description: Summary: Transition boiling data was taken with an improved flow loop, to explore the influence of loop characteristics on rod temperature fluctuations the transition region was found to be much smaller than for comparable conditions with a different loop. Also the amplitude, and frequency of the temperature oscillations, were significantly less than before. These results indicate that loop characteristic and flow disturbance parameters play a prominent part in governing the transition temperature fluctuations. Additional two-rod transition boiling data are presented. The results include data taken at high wall temperature levels during a demonstration test at low steam qualities, and the effect of a change in rod spacing on heat transfer performance.
Date: July 1, 1964
Creator: Quinn, E. P.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly report, June 1964

Description: This document details activities of the Irradiation Processing Department during the month of June, 1964. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.
Date: July 15, 1964
Partner: UNT Libraries Government Documents Department
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Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1964 - June 1, 1964

Description: Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: July 1, 1964
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Collins, William R., Jr.
Partner: UNT Libraries Government Documents Department
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A Procedure to Determine the Relative Extent of Reactor Fission Product Releases Under Various Meteorological Conditions

Description: From Abstract and Introduction: "A procedure for the application of these programs and graphs to the review and evaluation of reactor safety problems is presented. The purpose of this work is to present of the subsequent meteorological considerations suitable for review and analysis using a small digital computer."
Date: July 1964
Creator: Lanes, Stephen J.
Partner: UNT Libraries Government Documents Department
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An Engineering Method for Calculating Protection Afforded by Structures Against Fallout Radiation

Description: From Introduction: "The purpose of the paper is to discuss the assumptions and the reasoning by which the calculations described in the Engineering Manual were derived from the data in [1]. The relevant curves from [1] are given in Appendix A and the technical charts from the Engineering Manual are given in appendix B."
Date: July 2, 1964
Creator: Eisenhauer, Charles
Partner: UNT Libraries Government Documents Department
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An evaluation of the experimental determination of the effects of burnout and corrosion on spline worth

Description: Efforts have been made to experimentally evaluate and to calculate the effect of reactor environment on splines. This report follows some of these efforts and relates them to operational experience. The use of splines in the Hanford Reactors has improved the efficiency and ease of operating the reactors. With the widespread use of splines, it is important to know the effect of reactor exposure to safely and efficiently use the splines in reactor operation.
Date: July 13, 1964
Creator: Blyckert, W. A.
Partner: UNT Libraries Government Documents Department
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Neptunium-237 production forecasts, IPD 1964--73

Description: Neptunium-237 production has been-calculated according to the equations documented in Reference 1 for use in 1964-AEC study. cases. The assumptions made in the forecasts are as follows: Only the 947 stream is recycled. The blend enrichment for the recycle maternal is 1.2 per cent for F-Y 64 and 65. For FY 66 -73, a blend enrichment of 1.4 per cent is assumed which is better value according to the optimization model of C. W. Showalter. The 947 stream recycle time is two years. In cases A and B where the 947 stream volume is materially increased, virgin 947 material is introduced to make up the material balance. The U-236 content of the blend material- is 66 ppm{sup 2}. The U-236 input level in the 947 stream for the input of FY 64 is 200 ppm{sup 1}. Separations recovery is 85 per cent for FY 64--65 and 90 per cent thereafter. The material throughput data are given in Table I. These values are consistent with those being assumed for the AEC study cases. The Kgs of Np-237 by fiscal year are given in Table II. It must be remembered that these forecasts are based on a particular set of idealized assumptions, and the schedules represent IPD output only.
Date: July 10, 1964
Creator: Nilson, R.
Partner: UNT Libraries Government Documents Department
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Standard X-ray Diffraction Powder Patterns: Section 3. Data for 51 Substances

Description: Report documenting standard x-ray diffraction powder patterns for various compounds, intended to replace previous data or provide information for new substances. It describes the methods and, for each substance, outlines any previous data as well as information about the sample used and structural data, with a table of diffraction patterns.
Date: July 31, 1964
Creator: Swanson, Howard E.; Morris, Marlene Cook; Evans, Eloise H. & Ulmer, Linda
Partner: UNT Libraries Government Documents Department
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Effects of several EQ fuel loadings on aluminum process tube life

Description: Tube life estimates for the base case and the five study cases are given for 6.6 and 7.0 pH. The fuel sizes and operating conditions for each case are summarized. Information on the mixer position that gives maximum tube life for each case is shown. A tube life distribution was calculated for the base case using the outlet temperature distribution for 1197 central zone tubes at B reactor. Average tube life for the 1197 tubes war estimated to be 3.0 years (100 percent TOE) for operation at 6.6 pH, and the outlet temperature corresponding to average tube life vas l07{degree}C. Similar numbers could be calculated for the study cases if estimates of the outlet temperature distributions were available.
Date: July 24, 1964
Creator: Hough, C. G.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: June 1964

Description: This report, for June 1964 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.
Date: July 22, 1964
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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Tables of Chemical Kinetics : Homogeneous Reactions (Supplementary Tables)

Description: From Preface: "A brief description of the method used in compiling these tables and the limitation of coverage are given in the preface to Supplement 1 of the NBS Circular 510. The present volume contains information pertaining to substitution, exchange, and elimination reaction types and extends the material on these types found in NBS Monograph 34, Volume 1. The date on each page gives the year and month to which the literature had been surveyed."
Date: July 1, 1964
Creator: United States. Bureau of Standards.
Partner: UNT Libraries Government Documents Department
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Production test IP-695-AC thorium oxide irradiation -- K Reactors

Description: Irradiation of thorium for the production of ``clean`` U-233 at HAPO began in CY 1963. Several small-scale tests, involving from gram-size quantities up to a few elements, were successfully conducted; the results from these tests, coupled with theoretical predictions, indicated the desirability of further investigation. The objectives of this test are to (1) authorize the irradiation of about two tons of thorium oxide target elements in central zone process tubes of KE Reactor, (2) determine the reactivity effects of an enriched uranium-thorium oxide (E-Q) loading in the K Reactors, (3) demonstrate the feasibility of using the K Reactors in production of ``clean`` U-233, (4) provide sufficient irradiated thoria material to permit demonstration of the chemical processing capabilities, and (5) obtain data from an extended irradiation of one column of thoria elements.
Date: July 7, 1964
Creator: Gross, P. D. & Hladek, K. L.
Partner: UNT Libraries Government Documents Department
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Preliminary hazards evaluation for enriched uranium-thoria (E-Q) loading: Hanford IPD reactors

Description: The General Electric Company, as contractor to the AEC at Hanford, is proposing to modify the fuel loading of one or more of the IPD production reactors for the purpose of producing ``clean`` U-232 as a coproduct with plutonium. The isotope, U-233, with low (3-5 ppM) U-232 content, is expected to become a material with important nuclear applications. The IPD reactors are well suited to produce clean U-233. A proposal to produce 200 kg of U-233 for critical experiments for the AEC`s seed-and-blanket reactor program have been made in response to recent AEC inquiries. The production of such large quantities of U-233, on the schedule requested, would require nearly full utilization of the IPD reactors for a period of about half a year. This report, therefore, is intended to evaluate the nuclear safety of the IPD reactors whose entire loadings have been altered to coproduce U-233 and Pu-239. The coproduct loading will involve irradiating thorium oxide target elements. Excess reactivity to support the target material will be furnished by slightly enriched uranium, charged in tubes separate from the thoria. The expected fuel-to-target ratio is about 5.5 in the reactor cores and two in the reactor fringes. A full technical hazards evaluation of the E-Q load is presently in preparation and will be issued as a supplement to the Hazards Summary Reports. This treatment covers only the highlights of the full report and is intended as an interim and preliminary evaluation.
Date: July 23, 1964
Creator: Nilson, R.; Carlson, P. A. & Owsley, G. F.
Partner: UNT Libraries Government Documents Department
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