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Hanford Laboratories Operation Monthly Activities Report: June 1960

Description: This is the monthly report for the Hanford Laboratories Operation, July 1960. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities,, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: July 15, 1960
Partner: UNT Libraries Government Documents Department
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Hanford Operations Office monthly status and progress report. Part 1

Description: This is the monthly report for the Hanford Laboratories Operation, July, 1960. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: July 1, 1960
Creator: Travis, J. E.
Partner: UNT Libraries Government Documents Department
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Duplex bath variables experiments

Description: No Description Available.
Date: July 20, 1960
Creator: Burgess, C. A.
Partner: UNT Libraries Government Documents Department
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Variable goal exposure plans for production type fuel elements

Description: The purpose of this memorandum is to transmit revisions to the goal exposure plans of reference (1). The plans, herein, supersede the previous recommendations. Similar to the plans of reference (1), the exposures calculated from these plans are designed to maximize plant return on the basis that the only restraint on metal usage is that imposed by the economics of the plutonium production process and associated uranium cycle, as described and defined in references (2) and (3). When metal throug… more
Date: July 6, 1960
Creator: Bloomstrand, R. R.
Partner: UNT Libraries Government Documents Department
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Design of supplement B to PT-IP-262-A-11-FP, evaluation of projection fuel elements for use in ribbed process tubes

Description: One of the three major categories of HAPO fuel element failures is the side corrosion type rupture. The majority of side-corrosion failures has been characterized by oval or tear-drop shaped flow patterns containing evidence of accelerated corrosion. Thorough examination of many of these so-called `hot spot` failures has indicated the failure was caused by poor heat transfer associated with misalignment, dimensional distortion or poor jacket-to-core bonding. It has been postulated that misalign… more
Date: July 18, 1960
Creator: Hodgson, W. H. & Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department monthly report, June 1960

Description: This document details activities of the irradiation processing department during the month of June 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: July 15, 1960
Partner: UNT Libraries Government Documents Department
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Supplement D, Production Test IP-314-A, measurement of fuel element temperature changes as the result of film deposition

Description: The thermocouple train is modified by the substitution of one eighteen-inch enriched and four twenty-four inch natural uranium tubular elements for the two thirty-six inch enriched tubular elements used on the original thermocouple train. The operating limits for the loading have been changed because of the change in charge power. This supplement also authorizes the addition of fuel elements upstream of the thermocouple train if the thermocouple element and heater elements do not provide enough… more
Date: July 29, 1960
Creator: Kratzer, W. K. & Peacock, D. W.
Partner: UNT Libraries Government Documents Department
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Irradiation summary report - PT-IP-288-A, evaluation of seven rod cluster elements with modified end closures

Description: The objective of this report is to summarize all in-reactor operating data associated with PT-288-A. This document will serve as a ready reference to the irradiation history of the fuel elements, and will record any anomalies encountered in the performance of this test.
Date: July 13, 1960
Creator: Kratzer, W. K. & Peacock, D. W.
Partner: UNT Libraries Government Documents Department
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Inventory radioactive liquid waste to ground 200 Areas, 1945--1959

Description: Since startup in January 1945 through December 1959, 4 {times} 10{sup 9} gallons of radioactive liquid wastes have been discharged to cribs and trenches at HAPO by the Chemical Processing Department facilities in the 200 Areas. These wastes contained approximately 2.5 {times} 10{sup 6} curies of beta emitters. The Scavenged Waste Recovery Program was completed in 1957 and Redox Plant process changes were made during the latter part of 1958. These changes resulted in significant reduction in the… more
Date: July 28, 1960
Creator: Brown, G. D. & McConiga, M. W.
Partner: UNT Libraries Government Documents Department
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Status report: Protection fuel testing program, July 1960

Description: The program`s objective is to develop the technical foundation for use of projection fuel elements through an accelerated testing program. Two types of projection fuel elements are being considered (1) Self-supported fuel elements for use in ribless aluminum or zirconium process tubes; and (2) Bumper fuel elements for use in ribbed process tubes. A further objective of the program is to determine the most desirable method of fabrication and type of support for projection fuel elements. The prog… more
Date: July 15, 1960
Creator: Clinton, M. A. & Peacock, D. W.
Partner: UNT Libraries Government Documents Department
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Reactivity capacity of NPR control systems

Description: The reactivity control capacity of the N-reactor control systems has been calculated by methods which take into account the absorption of epithermal as well as thermo neutrons. Earlier calculations were made using a method which is satisfactory in control calculations for the existing Hanford reactors but which largely neglects the epithermal absorption. The new calculations were undertaken because of recent evidence that the epithermal absorption is more important to the NPR control strength a… more
Date: July 14, 1960
Creator: Simpson, D. E.
Partner: UNT Libraries Government Documents Department
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Testing of Zircaloy-2-Clad Uranium Seven-Rod Fuel Elements. Final Report

Description: In 1955 the Fuels Development Operation began irradiation testing of fuel elements in high temperature water. It was assumed that if a new reactor were built at Hanford, it would be cooled by high-temperature, pressurized water. Corrosion tests showed that aluminum-clad production fuel elements could not be used in high-temperature water. Therefore, while work to improve the resistance of aluminum to high-temperature water proceeded, the Fuel Design Operation began irradiation of stainless stee… more
Date: July 5, 1960
Creator: Geering, G. T.
Partner: UNT Libraries Government Documents Department
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Significance of operating experience with poison splines at KE Reactor

Description: The demonstrated operating efficiency performance which has resulted from poison spline usage forces an economic decision concerning the self-supported and bumper fuel element programs. As originally conceived the projection fuel elements would preclude the insertion of a spline under the fuel charge; thus it is very important that means be devised either to make poison spline usage compatible with future pile loadings or to demonstrate that some other supplementary control system, which is com… more
Date: July 15, 1960
Creator: Franklin, F. C.
Partner: UNT Libraries Government Documents Department
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Radiometallurgical examination of 1.47 enriched I&E fuel elements for PT-IP-247-A

Description: Under the conditions of PT-IP-247-A, four columns of self-supported and four columns of rib-supported I&E 1.47% enriched fuel elements were irradiated to determine their relative performance under severe operating conditions. Four of the self-supported and two of the rib-supported control elements were received for nation. The two rib-supported control pieces, which were classified as ``near failures`` had received average exposures of 353 and 359 MWD/T at average specific power levels of 91 an… more
Date: July 19, 1960
Creator: Teats, R.
Partner: UNT Libraries Government Documents Department
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Hydraulic demand curves for K-reactor geometry at low tube powers

Description: The outlet water temperature limits for the Hanford production reactors are based, among other things, on the ability to prevent excessive fuel temperatures during or following inadvertent flow losses or power surges. The analyses involved in the determination of the limits are dependent upon laboratory heat transfer experiments which closely simulate actual reactor conditions in a single process tube. The heat transfer experiments are quite complex in that they involve the recording of rapid c… more
Date: July 20, 1960
Creator: Waters, E. D. & Fitzsimmons, D. E.
Partner: UNT Libraries Government Documents Department
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Longitudinal flux flattening

Description: To date a great deal of emphasis has been placed on flattening the side-to-side and top-to-bottom flux distribution with only minor effort to improve the front-to-rear distribution. Minor variations in the front-to-rear distribution have been achieved by horizontal control rod and Supplemental control positioning. It has-been reasonably well established that the rupture potential for one tube charge increases markedly with higher specific power and temperature; thus there is a great deal of inc… more
Date: July 19, 1960
Creator: Stiede, W. L.
Partner: UNT Libraries Government Documents Department
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Potential limitations of Al-Si bonded fuel elements

Description: Tests in which aluminum-jacketed, Al-Si bonded uranium fuel elements were baked at various temperatures have shown there is a time-temperature relationship for Al-Si layer decomposition. For heat transfer and secondary coolant barrier considerations, the extent of bonding layer deterioration during fuel element irradiation is important. Under present reactor operating conditions, Al-Si bonded fuel elements show evidence of internal bond deterioration, and to a lesser degree, external bond deter… more
Date: July 14, 1960
Creator: Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
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Final report on program for using X-8001 aluminum alloy cladding material for Hanford fuel elements: PT-IP-43-A-84-MT, IP-80-A-91-FP and IP-2-I-99-FP

Description: Use of X-8001 Al alloy as cladding for Hanford reactors was initiated because of superior (laboratory) resistance to intergranular corrosion over that of C-64 alloy. However, since severe pitting attack was observed intermittently, an evaluation was carried out on X-8001 alloy fuel element cladding.
Date: July 22, 1960
Creator: Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
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Development test IP-342-AG increase of bulk outlet water temperature 105-DR

Description: The objective of this test is to determine the DR-Reactor effluent systems characteristics under 95 degrees Celsius bulk temperature operation. This proposed bulk temperature increase from 93.5 to 95 degrees represents a 33% decrease in the bulk temperature suppression below the boiling point. A major aim of this test will be to evaluate the degree of increased maintenance at this higher temperature operation. The basis and justification, test preparation and instrumentation, procedure, costs, … more
Date: July 14, 1960
Creator: Adams, O. E. Jr.; Hedges, J. W. & Jones, S. S.
Partner: UNT Libraries Government Documents Department
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KER-3 Operating Report: Test No. K-3-10 -PT-IP 288-A, Test No. K-3-11 -PT-IP-317-A -PT-IP-315-A

Description: The loop was charged October 30, 1959 with seven 12-inch Natural Uranium Zircaloy-2 clad 7-rod clusters. The test was primarily for the new hot-headed method of end closure used on these elements. The loop was pressure tested at 4000 psi after it was charged. Initially the loop was held at low-temperature to study the buildup of oxygen (presumably from radiolytic decomposition of water). After startup the neutron activity held at slightly above normal but the strainer gamma activity was excepti… more
Date: July 13, 1960
Creator: Sharp, F. E.
Partner: UNT Libraries Government Documents Department
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