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Compact thermoelectric converter. Quarterly progress report, July 1, 1968- -September 30, 1968. Phase II-C

Description: Declassified 30 Aug 1973. An initial analysis of experimental heatup data was compiled to determine the success of module experiments designed to triple the voltage power ratio of standard TEM-9 modules. Accomplishment of this design improvement is extremely significant in the development of tabular module systems having lower power applications. With the increased voltage to power ratio, power conditioning devices will not be required to step up the module output voltage to a more usable level. Heatup data from TEM9AE S/N-1, employing 0.030-inch lead telluride washers and 0.0015-inch mica insulators, correlate very closely with performance calculations. A study was initiated to determine an optimum design for a module to be internally fueled using cobalt60. In addition, alterations to the calculation model TEMOD were made to handle the effects of gamma heating within the lead telluride washers. An experimental test program was defined which would verify the validity of the mathematical model. Additional analytical work was accomplished to correlate predicted axial heat transport rates of heat pipes with experimental data. A study of sodium heat pipe performance data revealed that a sonic vapor velocity can occur in the region between evaporator and condensor sections of the heat pipe to produce a limit to the axial heat transfer rate. Evaluation of niobium contacts show them to be considerably more compatible with p-type lead telluride than iron contacts. However, the niobium does not yield absolute electrical stability and, as a result, no further work beyond the present analysis is contemplated. Six modules containing solid tungsten conductors were placed on test at elevated temperatures. Although degradation rates measured were the lowest yet recorded for modules employing TEGS-2P material, for temperatures above 1100 deg F the most stable operation is achieved through the substitution of TEGS-3P.material for TEGS-2P material. (auth)
Date: October 12, 1968
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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Fast Flux Test Facility Fuel Handling System Group 40, fuel handling and radioactive maintenance objectives, requirements, and criteria

Description: This report discusses the objectives of the FFTF Fuel Handling and Radioactive Maintenance System Group which are: To remove and replace test components from the reactor core under a controlled environment to permit maximum acquisition and preservation of experimental data; to service and maintain the reactor core to enable maximum utilization of the irradiation capability of the facility; and to provide the radioactive maintenance capability consistent with the requirement for high plant factor and safety considerations.
Date: October 12, 1966
Creator: Lenkersdorfer, H. D.
Partner: UNT Libraries Government Documents Department
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Improved Zirconium Alloys Quarterly Report: July - September 1962

Description: Quarterly report describing the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between July 1 to September 30, 1962 and was conducted by the United States and the European Atomic Energy Community (EURATOM).
Date: October 12, 1962
Creator: Weinstein, Daniel & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department Monthly Report: September 1962

Description: This document details activities of the Irradiation Processing Department during the month of September 1962.
Date: October 12, 1962
Creator: Hanford Atomic Products Operation. Irradiation Processing Department.
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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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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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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