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Semi-final report (report No. 3) E-N load conversion ratios

Description: Experimental data on plutonium yield and U{sup 235} burnout are now available on the E metal portion of three central zone striped E-N columns and one fringe blanket E column. These data and an overall E-N load conversion ratio based on experimental data are now reported.
Date: December 22, 1960
Creator: Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
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100-K Area electrical power system load and voltage study for project CG-775. Revision

Description: The proposed increased water capacity for 100-K plants will increase the electrical load to be supplied. The load study showed that the capacity of the existing 13.8 kV system is adequate to carry the increased loads proposed for Project CG-775, while for the 5 kV system, an expanded power system is proposed. Likewise, the voltage regulation on the kV system bus will be excessive, and voltage regulators should be added.
Date: February 22, 1960
Creator: Thorson, W. R.
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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Radiochemistry for the rupture of a Zircaloy-2 clad seven rod cluster fuel element in KER Loop 2

Description: On the 0000-0800 shift, October 15, 1959, the delayed neutron monitor on KER Loop 2 gave a high coolant activity signal indicating a possible fuel element failure in this loop. KE reactor was shutdown immediately thereafter. This report is being written to summarize the events pertinent to this KE reactor scram and to discuss the results and significance of data from analyses on coolant and coupon samples taken from KER Loop 2.
Date: January 22, 1960
Creator: Perrigo, L. D.
Partner: UNT Libraries Government Documents Department
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Production Test IP-300-A: Irradiation of twenty inch natural uranium tube and tube elements with hot headed inner tubes

Description: The objectives of this production test detailed in this report is to evaluate the behavior during irradiation of tubular fuel elements with hot-headed end closures. With natural uranium twenty-inch tube- and-tube elements will be irradiated to a goal of 2500 MWD/T in the KER loops. The inner tubes will be closed by the hot-heading technique and the outer tubes will have normal welded closures.
Date: January 22, 1960
Creator: Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Expansion task force: Old reactors speed of control for no overbore cases

Description: The Criteria for Speed of Control must be met for all cases being considered in the Expansion Studies. These Criteria are dependent upon the ratio Volume of water/volume of uranium in the process channel, the reactor power level, and the rate at which the vertical rods are released and inserted into the reactor. For those cases wherein the graphite channel is overbored by 0.200 inch., the criteria can generally be met for the power levels under consideration since the ratio of Vw/Vu is maintain… more
Date: February 22, 1960
Creator: Gilbert, W. D.; Carlson, P. A. & Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department Monthly Record Report: December 1959

Description: This document details activities of the irradiation processing department during the month of December, 1959. 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: January 22, 1960
Creator: Greninger, A. B.
Partner: UNT Libraries Government Documents Department
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Potential for process tube burnout during transient conditions

Description: This report is an interpretation of data (flow, pressure, temperatures within a process tube during events affecting single tubes) as applied to the most severe (rapid) K-reactor transients which are credible. Analyses indicate that no fuel channel burnout will result from a BPA power loss to the process pumps.
Date: April 22, 1960
Creator: Carlson, P. A. & Jones, S. S.
Partner: UNT Libraries Government Documents Department
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Proposed solid state diffusion bonding (SSDB) process: Gas pressure bonding

Description: This report presents a technical and economic study of the lead-dip canning process compared to two types of solid state diffusion bonding processes (hot-press die and gas pressure bonding) for Hanford production fuel elements (exclusive of NPR). It is concluded that either bonding process has potential advantages over the lead-dip process. The gas pressure bonding process has advantages over the hot-press die process.
Date: June 22, 1960
Creator: Weakley, E. A.
Partner: UNT Libraries Government Documents Department
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A CORROSION STUDY OF WELDED STAINLESS STEEL FUEL ELEMENTS

Description: Fuel element corrosion studies designed to and in selecting and evaluating SM-2 fuel element welding techniques are discussed. Tests on type 347 ss plate type fuel elements welded by the selected tungsten inert gas technique showed good corrosion integrity of specimens under a variety of conditions including a 500-hr test under simulated SM-2 conditions of flow and coolant chemistry. (auth)
Date: December 22, 1960
Creator: Bergen, C. R.
Partner: UNT Libraries Government Documents Department
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Current status -- Second generation process tube internal corrosion

Description: Seven water leaks during the past year because of internal corrosion of second generation process tubes have emphasized the need for additional corrosion information. Numerous out-of-pile and probolog examinations have been made to determine the nature of the corrosion, and mixer fuel elements currently are charged in central zone tubes in order to reduce the corrosion rates. This document presents the data obtained to date as a general description of the tube condition at the time when the mix… more
Date: June 22, 1960
Creator: Young, J. R.
Partner: UNT Libraries Government Documents Department
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Irradiation Processing Department, monthly record report, February, 1960

Description: This document details activities of the irradiation processing department at the Hanford Reservation during the month of February, 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 Operation; Manufacturing Operation; Facilities Engineering Operation; Relations Practices Operation; Financial Operation; and NPR operation.
Date: March 22, 1960
Partner: UNT Libraries Government Documents Department
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Piping changes for increased production at B, D, DR, F, C, and H reactors

Description: This study proposes improvements in the process water piping adjacent to the front and rear faces of these reactors. This report covers the external piping of the reactors from the incoming valve pit to the inlets of the outgoing retention basins.
Date: January 22, 1960
Creator: Bauer, G. H.; Harrison, C. W.; Hill, V. R.; McLenegan, D. W. & Mondt, J. F.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report for January 1960

Description: Production of Pu nitrate, UO{sub 3}, and unfabricated Pu metal met schedules. Decontamination performance of Purex process continued below standard. The cerium-144 cask is being redesigned. A ``powered ferret``, for driving a scintillation counter through a conduit to monitor ground activity beneath waste storage tanks, is being designed.
Date: February 22, 1960
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report for July 1960

Description: Production of Pu nitrate from separations plant during this month was below forecast. UO{sub 3} production, shipments met schedules; so did unfabricated Pu shipments. Purex plant was stopped to replace the final waste concentrator (F-11) (leak). Two Pu-U partition failures were attributed to foreign organic material in the nitric acid; the Pu product was kept within specifications by adding NaF and ANN to ion exchange feed stream. A Np recovery run was started in Redox, and dissolution was star… more
Date: August 22, 1960
Partner: UNT Libraries Government Documents Department
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An Investigation of the Structural Integrity of Selected Components of the Oak Ridge Research Reactor

Description: An investigation was made to determine the structural behavior of selected components of the Oak Ridge Research Reactor for increased power level conditions. It was found that a reactor cooling water outlet temperature of 150 deg F will cause severe plastic strain cycling in the aluminum housings for the large test facilities. Increasing the reactor cooling water flow rate of 21,000 gpm will cause plastic deformations in certain reaons of the core box. These latter deformations can be tolerated… more
Date: July 22, 1960
Creator: Corum, J M; Greenstreet, B L; Maxwell, R L & Rosenthal, M W
Partner: UNT Libraries Government Documents Department
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PERIODIC RADIATION SURVEY OF REACTOR PLANT CONTAINER AND COMPONENTS AFTER SHUTDOWN. CORE I, SEED I. SECTION 3. Test Results (T-612076)

Description: The effect of isolation and forced draining on the radiation level of the 1AC coolant purification hairpin loop was investigated. The activity in the horizontal and vertical legs (U-bend) of the loop piping was determined by a radiochemical analysis of the crud deposits. (C.J.G.)
Date: May 22, 1960
Partner: UNT Libraries Government Documents Department
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Radial Temperature Profile of Sodium Pool Boiling Heater Assembly

Description: The radial temperature around a sodium reactor heater assembly submerged in water is calculated using a model of the heater cross section found by conformal mapping. Thermocouple readings were also analyzed. When the heat flux is 5 x 10/sup 5/ Btu/hr-ft/sup 2/, a radial temperature drop of about 680 deg C across the center of the thermocouple well is calculated and found to be within 6% of the experimental value. Since most of this drop is across the 0.001-in. helium gap between the heater and … more
Date: February 22, 1960
Creator: Cappel, H. H.
Partner: UNT Libraries Government Documents Department
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STUDIES OF THE USE OF COAGULANT AIDS IN THE LIME-SODA TREATMENT OF LARGE- VOLUME, LOW-LEVEL RADIOACTIVE LIQUID WASTE

Description: Studies on the use of coagulant aids in the lime-soda treatment of large- volume, low-level radioactive liquid waste revealed that a combination of Hagan Aids No. 50 and No. 18 gave fairly good results under most conditions. The effects of feed solution concentrations, mode and point of addition, and water temperature were studied. (C.J.G.)
Date: August 22, 1960
Creator: Subbaratnam, T; Cowser, K E & Struxness, E G
Partner: UNT Libraries Government Documents Department
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