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Uranium burnout values

Description: Attached is the interpolated uranium burnout values for .570% through 3.000% U-235. Due to increasing interest in higher U-235 values, this document was issued to replace HW-77929 which contained values to 1.519% U-235. The source data was based on the Reactor Cost Studies burnout schedule obtained from Washington -- AEC.
Date: January 30, 1964
Creator: Smith, W. G.
Partner: UNT Libraries Government Documents Department
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N-Reactor fuel development pp. 51 through 57, HW-80908

Description: The imminent use of pressurized water-cooled, metallic uranium fuel elements on a large scale in the N-Reactor not only represents an extrapolation from previous Hanford fuel technology, it represents the only production-scale application of this concept in this country or abroad. Provision of a supporting technology is and will continue to be a major activity at Hanford as only a limited amount of directly applicable R&D will be available from other sites. The major benefit to be achieved thro… more
Date: March 30, 1964
Partner: UNT Libraries Government Documents Department
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Production test IP-665-A, evaluation of hot-die-sized end bonding processes

Description: Investigations of possible operational limitations of the ALSi bonded e elements and the need for a replacement or alternate fuel fabrication process have been lender way for several years. Recently, one fuel manufacturing process, hot-die-sized diffusion bonding, has been intensely examined and irradiation testing of this new fuel type began in 1963. This production test is one additional step in evaluating the new fuel fabrication process. The objective of this test is to evaluate the effect … more
Date: March 30, 1964
Creator: Hladek, K. L.
Partner: UNT Libraries Government Documents Department
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Physics calculations for mixed PuO{sub 2}-UO{sub 2} NPR loadings

Description: At the request of NRD (NPR Physics Subsection) a study was initiated to determine the physics characteristics of various plutonium-uranium composites as fuel for the NPR. From this study, the PuO{sub 2}-UO{sub 2} fuel system was selected to receive major attention. The effect of adding a burnable poison, B-10, in intimate contact with the mixed oxide fuel was also is to be considered. The present report summarizes the results of these investigations.
Date: June 30, 1964
Creator: Bennett, C. L.
Partner: UNT Libraries Government Documents Department
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Reactor Physics monthly technical report, June 1964

Description: Research and development activities included: spike loading of N-Reactor, Flex 3 program development, co-product hazards studies, and thorium fuel studies.
Date: June 30, 1964
Creator: Nichols, P. F.
Partner: UNT Libraries Government Documents Department
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Monthly record report Research and Engineering N-Reactor Department

Description: This document is a monthly report on the operation and engineering work associated with the N-Reactor department. It summarizes the operating history of the reactor during the month of Nov 1964. Included are brief descriptions of ongoing and planned work on testing and development of reactor components, fuel elements, safety tests, cooling systems, fuel production, materials testing, and other projects to provide safe and efficient plant operation.
Date: November 30, 1964
Creator: Leverett, M. C.
Partner: UNT Libraries Government Documents Department
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Laboratory studies of the use of uranium(IV) as a plutonium reductant in a Purex process

Description: This report describes laboratory-scale studies made to evaluate the feasibility of using uranium(IV)-hydrazine instead of ferrous sulfamate-sulfamic acid as the partitioning agent in the Hanford Atomic Products Operation Purex separations plant. Iron(II), in combination with sulfamic acid as a holding reductant, has been used very successfully for many years as a plutonium reductant in solvent extraction separation processes for irradiated nuclear fuels. However, the iron remains in the radioac… more
Date: July 30, 1964
Creator: Mendel, J. E.
Partner: UNT Libraries Government Documents Department
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Preliminary Design Report - Title 1 on Mobile Gamma Irradiator

Description: Introduction: The Mobile Gamma Irradiator is a semi-production demonstration unit capable of being transported from one area to another for use in irradiating fruit and farm produce, with the capability of furnishing dosages in the pasteurization range.
Date: October 30, 1964
Creator: Lowenberg, H. & Allentuck, J.
Partner: UNT Libraries Government Documents Department
open access

Impact properties of plutonium 1% gallium alloy

Description: This investigation was undertaken to determine the approximate impact characteristics of delta stabilized plutonium 1% gallium alloy, both at room temperature and at 325{degree}C. The testing done was non-standard, primarily because some approximate information was desired for another purpose and immediately available materials were used. While the results reported herein should be considered preliminary, they clearly depict the ductile impact behavior of this alloy.
Date: June 30, 1964
Creator: Gill, S. M.
Partner: UNT Libraries Government Documents Department
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Effects of corrosion upon the adequacy of the 105-KE and 105-KW emergency coolant backup system

Description: When final system acceptance tests were performed on Project CGI-844, 100-K Coolant Backup System, it became evident that less than the design flow of 32,000 gpm was being achieved. Since the tests indicated that only 28,200 gpm was being supplied to KW and 26,700 gpm was being supplied to KE, it was obvious that the cross-tie lines had higher friction losses than anticipated. A study was therefore made to determine the effects of crosstie line cleaning to remove corrosion nodules. Calculations… more
Date: January 30, 1964
Creator: Watson, D. F.
Partner: UNT Libraries Government Documents Department
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Development test IP-646-D, irradiation service request HAPO 278, outgassing rate of tritium at high temperatures and hydriding corrosion of Zircaloy-2

Description: Objective of the KE reactor test is to determine the hydriding corrosion rate of Zircaloy-2 at high temperature in a damp helium atmosphere, and to determine the outgassing rate of tritium generated in a lithium-aluminum alloy. The irradiation capsule design, operating conditions, etc. are discussed.
Date: December 30, 1964
Creator: DeMers, A. E.
Partner: UNT Libraries Government Documents Department
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Steam-Water Critical Flow From High Pressure Systems. Interim Report

Description: In an earlier report, the problems associated with the prediction of the critical discharge rates of steam-water mixtures were discussed in detail. That report also gave the results of an experimental investigation of critical flows from long flow passages performed at low pressures. That investigation was later extended to consider short tubes, nozzles, and orifice flow configurations. The present work was undertaken to experimentally investigate the critical discharge phenomenon at higher pre… more
Date: January 30, 1964
Creator: Zaloudek, F. R.
Partner: UNT Libraries Government Documents Department
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Saxton Plutonium Program Quarterly Progress Report: September 30, 1964

Description: Quarterly report regarding the activities of the Saxton Plutonium Program, the purpose of which is gathering information and analyzing performance through design, fabrication, and operation of plutonium enriched fuel in a pressurized water reactor system in the Saxton Reactor.
Date: September 30, 1964
Partner: UNT Libraries Government Documents Department
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Pluto quarterly report No. 20, April--June 1964

Description: Declassified 27 Nov 1973. Information is presented concerning Tory-2C operations and testing; reactor kinetics; control system and instrumentation; and physical properties of ceramic materials. (DCC)
Date: July 30, 1964
Partner: UNT Libraries Government Documents Department
open access

Aluminum Bar-X seal tests. Test series FFL-13

Description: This report is to evaluate a silver plated aluminum Bar-X seal's effectiveness in extending the range of ability to seal such a damaged plug.
Date: November 30, 1964
Creator: Edmiston, J.M.
Partner: UNT Libraries Government Documents Department
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Conoseal Bar-X Seal Tests

Description: On the NRX-A reactors the instrument ports are sealed by a Bar-X seal. Damage to the ports, which are part of the pressure vessel, required machining on the pressure vessel. A new design, using a Marman flanged piece to house the Bar-X seal port separate from the pressure vessel, was proposed. The test program was to determine the torque required to seal and the ability of each seal to hold during thermal shock.
Date: November 30, 1964
Creator: Edmiston, J.M.
Partner: UNT Libraries Government Documents Department
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