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The Preparation and Properties of Molybdenum(IV) Bromide

Description: From abstract: "The preparation of pure molybdenum(IV) bromide was accomplished conveniently by the reaction between molybdenum(III) bromide and liquid bromine at ca. 55°. Molybdenum(IV) bromide was found to be soluble in liquid bromine, and this property was utilized to separate and purify the molybdenum(IV) bromide. The solution of MoBr4 in bromine was a poor electrical conductor. No evidence was found for the formation of MoBr4 from MoBr3 and bromine vapor at 2-4 atm. and temperatures from 180 to 400°. However, MoBr4 was completely decomposed at 110-130°, in vacuo, with formation of MoBr3 and bromine."
Date: June 12, 1962
Creator: Carnell, P. J. H. & McCarley, R. E.
Partner: UNT Libraries Government Documents Department
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Design and Test of a Diaphragm Pump for Liquid Metals

Description: Technical report. From Abstract : "Details are provided on the construction and operation of a two-stage diaphragm pump successfully used for the first time in liquid metal service. From the results of 5,376 hr. test of the pump it was concluded that it is well suited to the pumping of liquid metals at low flow rates where pulsating flow can be tolerated and also where remote operation is required. Operating temperatures and pressures are limited only by the availability of suitable materials of construction."
Date: April 12, 1963
Creator: Westerheide, D. E. & Clifford, J. C.
Partner: UNT Libraries Government Documents Department
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SM-1 Research and Development. Task XV, Zero Power Experiments for SM-1 Core II and SM-1A Core I

Description: Abstract: A zero power experiment on the SM-1 Core II included an element by element reactivity check of fuel elements and control rod absorber sections, and an estimate of burnable nuclear poison loading in stationary fuel elements. An approach to criticality was made by the inverse multiplication method, and critical rod bank position obtained as a function fuel loading up to full core loading. Minimum and maximum core reactivity measurements were obtained by selective loading of stationary fuel elements, and total excess K of the core was established. Power distribution measurements were taken in the regions of the core-reflector interface and the fuel-absorber interface in the control rod assemblies. The effectiveness of europium flux suppressors in the top of control rod fuel elements was determined, and power peaking was measured in stationary elements adjacent to control rod assembly water gaps. Survey measurements established the work of spiking clean, cold SM-1 cores with SM-2 elements and the work of water holes in the SM-1 Core. The reduced scope zero power experiment performed on SM-1A core I included an element by element uniformity check of stationary fuel elements, a core assembly test, comparison of Eu2O3 and B4C absorber sections, and development of initial core loading procedures for the SM-1A plant.
Date: October 12, 1960
Creator: Robinson, R. A.; Weiss, S. H.; McCool, W. J. & Schrader, E. W.
Partner: UNT Libraries Government Documents Department
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PL-3 Phase I Task 3 Research and Development Report

Description: Abstract: This technical report summarizes the results of research and development tasks performed during Phase I of this contract and presents recommendations for future development work. Work is reported in the areas of plant assembly and relocation, housings and footings, waste heat dissipation, instrumentation, refueling systems, waste disposal, shielding, core nuclear thermal and hydraulic studies, gaseous waste processing (BWR), and critical experiments on a 5 x 5 array of Type 3 fuel elements.
Date: March 12, 1962
Creator: Humphries, G. E.
Partner: UNT Libraries Government Documents Department
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Theoretical density of lithium aluminate updated

Description: The ''handbook'' density for LiAlO/sub 2/ is 2.55 g/cc. Recent data show that it should be revised to 2.62 g/cc. In the future densities reported as percent of theoretical should be based on 2.62 g/cc as being 100 percent. Values quoted on this basis will be more realistic. In order to avoid confusion it will be necessary to state which number percent of theoretical density are based upon--that is, ''2.62 g/cc = 100 percent,'' or ''2.55 g/cc = 100 percent.'' For the convenience of those working directly with the material, a conversion chart is included along with a table which gives density (g/cc) versus percent density based on 2.62 g/cc.
Date: January 12, 1966
Creator: Gurwell, W. E.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department Monthly Report: July 1960

Description: This document details activities of the irradiation processing department during the month of July, 1960. 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: August 12, 1960
Partner: UNT Libraries Government Documents Department
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GENERAL DESCRIPTIONS OF A SATELLITE PROCESSOR FOR ILLIAC II

Description: The Department of Computer Science of the University of Illinois has constructed and put into service ILLIAC II, a large-scale digital computer. ILLIAC II is used both in computer systems research and in general University service.
Date: May 12, 1965
Creator: Carter, C E & Willard, R E
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department Monthly Report: September 1960

Description: This document details activities of the irradiation processing department during the month of September, 1960. 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: October 12, 1960
Partner: UNT Libraries Government Documents Department
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Consistent Properties of Composite Formation Under a Binary Relation

Description: In this paper we study the properties of a relation, H, between two sets, X and Y, H ⊆ X x Y. We wish to determine when the existence of H between some elements of X and Y implies the existence of H between other composite elements of X and Y. The aim is to characterize a relation by its extension or restriction to composite elements.
Date: August 12, 1969
Creator: Schwebel, John C & McCormick, Bruce H
Partner: UNT Libraries Government Documents Department
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Hanford isotope production capabilities for single pass reactors

Description: This report is a summary of several studies made by the author during 1967, and early 1968, while providing technical assistance to the Advanced Concepts and Planning Section. An attempt has been made to reduce the data to a usable form which will enable the reader to estimate the production of a particular isotope and the production of weapons grade plutonium that accompanies the co-product loading for different Uranium-235 concentrations of the driver fuels. It should be emphasized that the production data shown in this document do not constitute an engineering study of the loading. As the safety analysis has not been performed and only minimal hydrokinetics have been studied, it is imperative that the use of the data contained in this report be used only for planning and estimating work. if any particular loading were to become a reality, a detailed engineering study would be required for that loading. Although the B Reactor has been deactivated it is included in the report along with the C and K Reactors. Hence, it is possible to make estimates of the capabilities of the entire Hanford single pass reactor complex. Although Oralloy fuel for the Hanford reactors for isotope production has not been fully developed, there are several cases included for each isotope. If the state of the art is advanced in the future these preliminary calculations could possibly serve as a base point.
Date: December 12, 1968
Creator: Miller, R. L.
Partner: UNT Libraries Government Documents Department
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Fission product ratios of the Purex filter

Description: This report details measurements of fission product ratios which were made an various samples of the Purex canyon exhaust filter to determine the manner and time interval in which the filter became plugged vith foreign material. Results for samples from different levels within the filter bed were compared to investigate accumulation as a function of depth. Strontium-89/strontium-90, Zr-95/Ca-137, Ru-103/Ru-106, and Ce-141/Ce. Pr-144, ratios were determined. These were compared to a constant rate model for accumulation of fission products on the filter. Observed Sr-89/Sr-90 and Zr-95/Cs-137 ratios fall within a range of values typical of normal plant operation, Specifically long-term accumulation of Hanford material irradiated at 10 MW/T to between 600 and 900 MWD/T total exposure and cooled between 120 and 200 days. Low Ru-103/Ru-106 and Ce-141/Ce, Pr-144 ratios definitely rule out rapid accumulation of short-cooled material as the build-up mechanism but are not sensitive indicators in the case of long-cooled material. Ratios did not vary significantly with sample location, indicating that accumulation age does not differ with depth within the filter.
Date: June 12, 1964
Creator: Weiler, M. R.
Partner: UNT Libraries Government Documents Department
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B-Plant fission product flowsheets. Part 1

Description: B-Plant is currently being evaluated for use as an integrated fission product plant operating in conjunction with the Purex Plant and a waste calcination system. If the forecasted demands for fission products should increase to rates exceeding present capabilities and if private enterprise continues to remain outside the recovery field, present budget plans are to develop the use of B-Plant in three phases. In Phase 1, the B-Plant canyon would be activated and provisions made for preparing and storing fission product concentrates. In Phase 2, additional equipment would be installed to provide a single-line demonstration system for purifying and packaging fission products. In Phase 3, the plant would be converted to a double-line production system for recovering, segregating and storing, purifying and packaging fission products. The purpose of this document is to present the technical bases for B-Plant project scoping studies, including: Design flowsheets for the preparation and storage of fission product concentrates in the scope design of Phase 1 activities; and conceptual flowsheets for the purification of stored concentrates in the engineering studies of Phase 2 activities.
Date: January 12, 1961
Creator: Beard, S. J. & Judson, B. F.
Partner: UNT Libraries Government Documents Department
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Supplement C to PITA-IP-10-I, Irradiation of alloyed dingot uranium fuel elements

Description: The objective of this supplement is to authorize charging of additional dingot uranium and to extend the charging to all old reactors, (B, D, DR, F and H). The original test authorized charging 360 tons of dingot uranium at a rate of approximately 60 tons per month. Charging began in May 1960 and at present the majority of this material has been charged. The present delivery schedule calls for accepting 90 tons of dingot uranium per month from MCW, starting in November 1960. To meet this schedule it is necessary to either authorize additional charging under a suitable test program, such as this PITA, or to accept dingot uranium as normal material.
Date: October 12, 1960
Creator: Shimer, R. D.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly report, August 1960

Description: This document details activities of the irradiation processing department during the month of August, 1960. 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: September 12, 1960
Partner: UNT Libraries Government Documents Department
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Nomogram for TAI equation

Description: A nomogram is attached as Figure 1 which may be used to determine TAI limits. The nomogram was developed to meet the need for a rapid and accurate method for calculating these limits. The technical basis for determining individual tube outlet temperature limits is given in HW-65729.
Date: December 12, 1960
Creator: Carlson, P. A.
Partner: UNT Libraries Government Documents Department
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Radioisotopic analysis of aluminum control rods

Description: This barely legible document contains Zn-65 and Co-60 concentrations and total dose contributions from F area HCR`s. Differentiated include tubes form full rods, tubes form half rods, and outer sheath`s.
Date: June 12, 1964
Partner: UNT Libraries Government Documents Department
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HAPO tritium production facilities study - 1958 - study reports numbers 1 and 2

Description: Start of the development of new processes to extract mint can be a gradual program. The most promising of early results lies in the area of Isotopic Purification. Steps have been initiated to start development work on separation and purification of mint gas by chromatography. This method has the added advantage over columns as three gases, hydrogen, deuterium and mint may be separated in one operation. Should it appear that this method may fail, a second approach would be development of a packed column. Even with a change of the basic extraction process, isotopic purification is required and the improvement of such facilities would serve to provide the product at a reduced initial capital cost as well as reduced extraction cost. Work can proceed at the same time with development of a dissolution process. As noted in Appendix I, a unit extraction savings in the order of 20 percent can be expected since, in the most simple form, expensive furnace pots would be replaced by inexpensive crucibles.
Date: November 12, 1968
Creator: Kesel, G. P.; Koontz, W. H.; Smiset, O. V. & Denollander, W. R.
Partner: UNT Libraries Government Documents Department
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Dissolver operation and metal transfer

Description: This report provides data on daily dissolver operation and metal transfers. Sodium hydroxide and sodium nitrate requirements are also given.
Date: October 12, 1967
Creator: Beaulieu, O. F.
Partner: UNT Libraries Government Documents Department
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