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Energy release per fission in the Hanford reactors

Description: The average energy release per fission event in a reactor is dependent on the composition and arrangement of the lattice materials. In a study of heat generation in the NPR, Nilson developed expressions for calculating the average energy released in each material per fission event. These relationships have been used in the present calculations to obtain the energy release per fission in existing Hanford reactors.
Date: February 12, 1960
Creator: Morgan, W. C. & Bunch, W. L.
Partner: UNT Libraries Government Documents Department
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K Reactor: HCR sleeves

Description: Irradiation Processing Department opinions regarding HCR sleeves. It is believed that Zr-2 would be a satisfactory sleeve material providing it is limited to maximum service temperatures the order of 400 degrees C. Both Inconel and a 300 series stainless steel are believed possibilities for uncooled sleeve materials, with Inconel our preference. Beryllium, in virtue of its outstanding nuclear properties and probably satisfactory chemical and mechanical properties, warrants consideration on a pi… more
Date: December 12, 1960
Creator: Zima, G. E.
Partner: UNT Libraries Government Documents Department
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Preliminary design basis modifications for improved coolant backup 100-B, D, F, H, DR, and C areas

Description: The purpose of this document is to establish the design scope for the proposed modifications to the reactor ``last ditch`` cooling systems in the 100-B, D, F, H, DR, and C Areas. The objective in making these modifications is to provide adequate ``last-ditch`` reactor coolant flows for safety of operation at power levels currently programmed for the period CY 1964 when additional ``last-ditch`` cooling facilities are planned in connection with major plant modifications. Additional interim modif… more
Date: August 12, 1960
Creator: Schack, M. H. & Tupper, W. J.
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 schedu… more
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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Discussion on Optimization of Large Oil-Pumped Ultra-High Vacuum Systems

Description: Abstract: "Discussion is directed toward eventual optimization of the largest diffusion-pump systems. Less than 100 diffusion pump fluid molecules per cm 2/sec are possible to detect using an accumulation method. Optimization discussed demands highest possible system speed compatible with the above contamination rate. Bakeable oil diffusion pump systems, with equal orifice valve-tap units, without conventional baffling, permit theoretical through-put speeds up to 0.3 of the system orifice. The … more
Date: September 12, 1960
Creator: Milleron, Norman & Levenson, L. L.
Partner: UNT Libraries Government Documents Department
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Quarterly Health Physics Report. Through June 30, 1960. (Deleted Version)

Description: A resume of Health Physics activities for April, May, and June, 1960 is presented. Discussions and tabulations which summarize results of field surveys, bioassay, personnel monitoring, and environmental surveys are included.
Date: September 12, 1960
Creator: Meyer, H.E.
Partner: UNT Libraries Government Documents Department
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HEAT-TRANSFER EXPERIMENTS ON A PROPOSED FUEL ASSEMBLY FOR THE EXPERIMENTAL GAS COOLED REACTOR. SECTION II FO FUEL-ASSEMBLY HEAT-TRANSFER AND CHANNEL PRESSURE-DROP EXPERIMENT FOR THE EGCR RESEARCH AND DEVELOPMENT PROGRAM

Description: Heat-transfer data are presented for the Experimental Gas Cooled Reactor Title I seven-rod fuel-assembly design. The effect on heat transfer of (1) the radial location of the outer six rods of the seven-fuel-rod cluster and of (2) the addition of helical-finned spacers at the midpoint of each of the seven fuel rods is discussed. The heattransfer data were obtained to verify preliminary general assumptions pertaining to the heat-transfer characteristics of the seven- rod fuel-assembly design and… more
Date: April 12, 1960
Creator: Beaudoin, C.L. & Higgins, R.M.
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
open access

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
open access

Processing of High-Fired Uranium Dioxide Fuels by a Reduction-Mercury Extraction-Oxidation Process

Description: A preliminary flowsheet for the purification of uranium dioxide fuels by a magnesium reduction-- mercury extraction-- steam oxidation process is proposed. Feasibility was indicated by laboratory-scale scouting experiments. Data evaluation indicated 100% reduction of uranium dioxide by magnesium although this figure was not demonstrated, chiefly because of poor choice of materials and design of equipment. Steam oxidation of uranlum tetramercuride produced an oxide with an O/U ratio of 2.43. This… more
Date: August 12, 1960
Creator: Messing, A. F. & Dean, O. C.
Partner: UNT Libraries Government Documents Department
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PURIFICATION OF PROMETHIUM BY LIQUID-LIQUID EXTRACTION

Description: A process was developed for separating promethium from raixed fisBion product rare earths by continuous multistage conntercurrent extraction with 100% tri-nbutylphosphste from nitric acid of 12 N or higher concentration. Distribution coefficients at 12 N acidity for aecdamium. promethium. and samarium are 0.43. 0.82, and 1.55, respectively. Single-stage separation factors of 1.9 between successive elements can be maintained throughout the system to give separations dependent only on the number … more
Date: February 12, 1960
Creator: Weaver, B. & Kappelmann, F.A.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section C Progress Report for April-May 1960

Description: An economical process was successfully demonstrated in bench-scale continuous equipment for stripping U from amines with ammonium carbonate solution. A continuous countercurrent mixer-settler extraction system was set up for further testing of the process for recovery of Te, Np, and U by tertiary amine extraction from UF/sub 6/ transfer cylinder was solutions. The effect of Purex aqueous feed adjustment procedures on Pu extraction by 1 M di-secbutyl phenylphosphonate (DSBPP) was studied. Work w… more
Date: July 12, 1960
Creator: Brown, K B
Partner: UNT Libraries Government Documents Department
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The Bonding of Molybdenum-and Niobium-Clad Fuel Elements

Description: A solid-state bonding technique involving the use of gas pressure at elevated temperatures was utilized for the self-bonding of molybdenum and niobium. Bonding conditions and surface preparation as a function of the integrity of the bond achieved were evaluated for each material. Optimum self-bonding of niobium was achieved by bonding parameters of 2100 to 2300 deg F at 10,000 psi for 3 hr with surfaces which had been prepared by etching in a nitrichydrofluoric acid solution prior to bonding. T… more
Date: July 12, 1960
Creator: Paprocki, S. J.; Hodge, E. S. & Gripshover, P. J.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section B Monthly Progress Report, June-July 1960

Description: The effect of two neutron poisons, baron and cadmium, on the rate of dissolution of high-density 95% ThO/sub 2/-5% UO/sub 2/ pellets in the Zirflex Process was determined. Dissolution of U-10% Mo alloy in boiling HNO/sub 3/ resulted in a precipitation of uranyl molybdates. Air caused greater uranium and thorium losses during decladding of ThO/sub 2/-UO/sub 2/ fuel than irradiation. Processing of U-Mo fuel by a Zircex type process is discussed. Two leaches of graphitized fuel with 90% HNO/sub 3/… more
Date: December 12, 1960
Creator: Blanco, R E
Partner: UNT Libraries Government Documents Department
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Spert Project. Quarterly Technical Report for April, May, June 1959

Description: SPERT I: The characteristics of the boiling process and its relatin to moderator expulsion in Spert I were investigated in a series of capsule type experiments. A fuel-bearing oapsule, instrumented to provide pressure, volume, and temperature data during transient power excursions, was placed in a high flux region of the Spert I P core. Five step-induced transients initiated from boiling indicate that the kinetic behavior of the stainless steel clad P-18/19 core is dependent on initial temperat… more
Date: April 12, 1960
Creator: Haire, J. C.
Partner: UNT Libraries Government Documents Department
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