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MSRE Preliminary Physics Report

Description: This report is a compilation of the results of reactor physics calculations to date for the currently proposed Molten Salt Reactor Experiment (MSRE) core design. Estimates have been made of the reactor characteristics using the core model and calculation methods discussed in Reactor Model and Calculation Methods; these results are presented in Table 1 and discussed in Results. Consideration is given to the problems of fission product buildup, fuel salt and Xe-135 retention by the core graphite… more
Date: April 19, 1961
Creator: Nestor, C.W., Jr.
Partner: UNT Libraries Government Documents Department
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On the Activities in the Plant Off-Gas

Description: Measurements were made of the activities in the Laboratory off-gas and efficiencies of the gas cleaning facility were calculated. Sampling was done isokinetically and, by the use of filter paper and charcoal traps, particulates and adsorbable gases were collected.
Date: April 19, 1961
Creator: Fujii, S.; Manneschmidt, J.F.; Mackey, T.S. & Woodall, E.W.
Partner: UNT Libraries Government Documents Department
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Sources and Availability of Helium

Description: A review of helium sources, availability, consumption, and future production capacity indicates that the helium consumed in the operation of 100 helium-cooled reactors for 300-Mwe power plants over a 20-year period will run no more than a few per cent of the helium consumed in the U. S. in the next 25 years and less than 1% of the helium that is to be stored during that period under the helium conservation act of 1960 (Public Law 86-777).
Date: January 19, 1961
Creator: Fraas, A. P.
Partner: UNT Libraries Government Documents Department
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Some Heat Transfer Characteristics of ORR Fuel Elements

Description: Analyses are generally made at the ORR with a view toward determining the surface temperatures of fuel plates.
Date: January 19, 1961
Creator: Wett, J. F., Jr.
Partner: UNT Libraries Government Documents Department
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A Solution of the Distributional Error Problem in Cytophotometry

Description: Use of that portion of the characteristic curve of photographic film in which transmission is linear with log exposure eliminates the distributional error and thus makes possible the assessment of total mass of an inhomogeneously distributed cell consistent without scanning or measuring the cell's projected area. Measurement consists of obtaining the difference in output of a photocell receiving the total light transmitted by a photomicrograph of the cell, and a photomicrograph of the microscop… more
Date: December 19, 1961
Creator: Adams, Lawrence R. & Sondhaus, Charles A.
Partner: UNT Libraries Government Documents Department
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On Charge Conjugation

Description: It is shown that under very simple and general assumptions the existence of an antiunitary reflection transformation and the charge gauge group implies the existence of an antiparticle corresponding to a given charged particle. Similar consequences follow on replacing the charge gauge group by the baryon gauge group. No assumptions as to specific wave equations, or indeed the existence of local fields, are made.
Date: July 19, 1961
Creator: Case, Kenneth M.
Partner: UNT Libraries Government Documents Department
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Spinning of Columbium & Columbium 1%- Zirconium Tubing

Description: The following objectives were planned for this project. (1) Development of spinning data necessary for spinning Columbium and Columbium-1% Zirconium tubing from ingot, forged or welded tube blanks. (2) Determine mechanical & metallurgical properties of spun Columbium and Columbium-1% Zirconium tubing. (3) Determine dimensional and tolerance limits possible to attain on spun Columbium and Columbium-1% Zirconium tubing based on our present equipment, tooling limitations, and the spinning tests p… more
Date: January 19, 1961
Creator: Barker, Wharton R.
Partner: UNT Libraries Government Documents Department
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Hazards Report for the SM-1 Core II Without Special Components

Description: Abstract: This technical report describes the changes incurred in the SM-1 by the insertion of the SM-1 Core II without special components. The SM-1 Core II components were made to specifications very nearly identical to those of SM-1 Core I. The differences consist of europium absorber sections, internal europium flux suppressors in the control rod fuel elements, and low impurity cladding. Each of the SM-1 Core II components with the exception of the five absorber sections new in SM-1 Core … more
Date: April 19, 1961
Creator: Gallagher, J. G.
Partner: UNT Libraries Government Documents Department
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NPR pile gas purification

Description: No Description Available.
Date: October 19, 1961
Creator: Stepnewski, D. D.
Partner: UNT Libraries Government Documents Department
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Safety review of Nuclear Fuel Manufacturing Operations: Fuels Preparation Department

Description: Subsequent to a recent comprehensive review of the safety of Hanford`s reactor operations, a request was received from the Hanford Operations Office for a similar review of manufacturing processes within the 200 and 300 areas. Of particular concern were the non-reactor-oriented nuclear and radiological hazards involved in these operations, as well as the administrative procedures by which they were controlled. This report, which reviews these elements of safety of operations within the Fuels Pr… more
Date: May 19, 1961
Creator: Worlton, D. C.
Partner: UNT Libraries Government Documents Department
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Production test-IP-409-A-FP pilot test of self-supported fuel elements in K size smooth-bore zirconium process tubes

Description: This test authorizes installation of up to ten non-overbore size zirconium smooth-bore process tubes into KW Reactor and continued charging of these tubes with KVNS fuel elements until authorized by other means (Process Standards or PITA) or until this test is terminated. While the test authorizes up to 10 tubes, only two process tubes are immediately available and are all that will be planned for in the initial installation and charging. Goal exposure will be set at 800 MWD/T.
Date: June 19, 1961
Creator: Clinton, M. A. & Curtiss, D. H.
Partner: UNT Libraries Government Documents Department
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Reduction of the amount of dichromate added to reactor cooling water: Interim report, Production Test-IP-321-A

Description: Reduced process water treatment costs and incidental benefits of smaller hexavalent chromium discharge to the Columbia River provided incentives to conduct a half-reactor production test. The sodium dichromate (Na{sub 2} Cr{sub 2} O{sub 7}2H{sub 2}O) concentration in process water supplied to the far side of 105-C was lowered from a nominal value of 1.8 to 1.0 parts per million (ppM). This test was started September 26, 1960 and is still in progress. However, a sufficient amount of data is avai… more
Date: June 19, 1961
Creator: Nesselson, E. J.
Partner: UNT Libraries Government Documents Department
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NPR hazards review: Volume 1, Phase 1: Production only

Description: This document is designed to present as complete a review of the hazards associated with the operation of the N Reactor as is feasible at this time. Where completeness is not possible the problems are indicated and probable paths of solution are suggested. Background material is provided to put the hazards in context. Supplements to this report will be issued when the additional data and information required for completeness are obtained. This review is organized into two parts. The first part … more
Date: October 19, 1961
Creator: Miller, N. R. & Trumble, R. E.
Partner: UNT Libraries Government Documents Department
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Processing data for NIE and NIN KER Loop charges (PT 377)

Description: The following data represents processing conditions used in fabricating prototypic (except for supports) natural and enriched NPR inner fuel elements for Production Test 377. The prototypic NPR inner fuel elements were inserted into zircaloy-sleeves prior to charging. In this way it was possible to simulate, in the KER loops, the conditions under which NPR fuel elements would be subjected under irradiation. The purpose in documenting the data is to provide a permanent record of processing condi… more
Date: April 19, 1961
Creator: Kusler, L. E. & Hays, D. D.
Partner: UNT Libraries Government Documents Department
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40-tube overbore facility location, C Reactor

Description: Possible locations of the projected 40-tube overbore facility at the C Reactor are discussed from the standpoint of obtaining conversion ratio data applicable to a full-reactor overbore program.
Date: April 19, 1961
Creator: Nilson, R.: Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
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Analysis of the stored energy distribution in D-reactor

Description: The purpose of this document is to characterize, as completely as possible, the stored energy distribution in D Reactor as of March 1958, the date of the last stored energy survey and to estimate the temperature rises which can be expected to occur during a stored energy release. D Reactor was chosen for this study only because it represents one of the oldest operating Hanford reactors and not because of any circumstances peculiar to this reactor. 14 refs., 13 figs.
Date: May 19, 1961
Creator: Morgan, W. C.
Partner: UNT Libraries Government Documents Department
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Research and Development Studies on Waste Storage Process

Description: The basic objectives of this program were the determination of the thermal stability of various fission product oxides and nitrates, and an investigation of the gas phase decomposition of ruthenium tetroxide. To accomplish these objectives, a literature survey was flrst made of available physical and chemical data for the oxides and nitrates of Cs, Sr, Ru, Zr, Nb, and Ce. The data were supplemented by a calculation of thermodynamic functions for RuO/sub 4/ vapor from the experimentally determin… more
Date: May 19, 1961
Creator: Ortner, M. H.; Anderson, C. J. & Campbell, P. F.
Partner: UNT Libraries Government Documents Department
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INFLUENCE OF RADIATION FROM AN UNSHIELDED REACTOR ON A NATURAL MICROFLORA

Description: The soil microflora and its respiratory activity were measured in soil cores collected at different distances from an unshielded reactor. No direct correlation was found between dose received and microbial counts or respiration. Indication of a correlation between dose and microbial respiration was obtained after eliminating the overriding influence of moisture. Radiation probably affected the soil microflora through damage to the phanerogam vegetation rather than directly. This preliminary stu… more
Date: October 19, 1961
Creator: Witkamp, M.
Partner: UNT Libraries Government Documents Department
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An Investigation of Some of the Causes for the Spalling of Impregnated Graphite

Description: The impregnation process of the graphite used for investigations of spalling is described. Polished graphite specimens were examined at room temperature using bright field metallographic techniques. The gas evolution characteristics of impregnated graphite were also determined. Results indicated that the amount of impregnant introduced during the fourth impregnation cycle could be a critical factor in causing spalls in the manufacturing process. The permeability of the impregnated graphite was … more
Date: June 19, 1961
Creator: Kosiba, W. L.; Tully, G. R., Jr. & Turovlin, B.
Partner: UNT Libraries Government Documents Department
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Determination of Life-Time of the B$sub 4$C-in-Tubes Control Rod

Description: The lifetime of a B/sub 4/C-in-tubes'' control rod may be limited by either nuclear worth depreciation or internal gas pressure buildup as helium is formed and released from the B/sub 4/C particles. Nuclear life is enhanced by thin tube walls for any given O.D. of tubing and by high B/sub 4/C density, but the time to failure from gas pressure buildup is increased by the opposite. The optimum B/sub 4/C density and tube wall thickness were calculated for maximum control rod life, using several re… more
Date: July 19, 1961
Creator: Megerth, F. H.
Partner: UNT Libraries Government Documents Department
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CORE REMOVAL COOLING SYSTEM-SECTION II. CORE I, SEED I. Test Results T- 641113. Section 2

Description: A test was performed on June 19, 1959 to determine the capacity of the Core Removal Cooling System for removing reactor decay heat under split-flow'' conditions. The system operated satisfactorily during this test; the pumps developed a flow of approximates 73 gpm at a total head of 254 ft water, as compared with their rated capacity of 75 gpm at a total head of 250 ft water. (D.L.C.)
Date: May 19, 1961
Partner: UNT Libraries Government Documents Department
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CHARACTERIZATION OF UO$sup 2$ POWDERS. Progress Report No. 8, May and June 1961

Description: Correlation of a number of physical and chemical properties of 12 different UO/sub 2/ powders was continued. The UO/sub 2/ powders were studied by means of infrared absorption measurements, oxidation temperatures as determined by hot stage microscopy techniques, and B. E. T. surface area measurements. Additional pellets were prepared to study ceramic performance. (M.C.G.)
Date: July 19, 1961
Creator: Carpenter, J.F.
Partner: UNT Libraries Government Documents Department
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CERENKOV RADIATION INTENSITY CALCULATIONS FOR Sr$sup 90$ AND Co$sup 60$ IN WATER

Description: A method for calculating Cherenkov radiation intensity from an initial electron energy distribution is presented. The Cherenkov radiation intensity from 1 curie of Sr/sup 90/ in secular equilibrium with Y/sup 90/ in water was calculated from the beta energy spectrum to illustrate the use of the method for a pure beta emitter. The Cherenkov radiation intensity from 1 curie of Co/sup 60/ in water was calculated from the Compton electron energy spectrum to illustrate the use of the method for a ga… more
Date: September 19, 1961
Creator: Wymer, R.G. & Biggers, R.E.
Partner: UNT Libraries Government Documents Department
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