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HOT CELL DEMONSTRATION OF ZIRFLEX AND SULFEX PROCESSES. Report No. 3

Description: ABS>Hot cell demonstration of the Zirflex decladding process coupled with a modified Purex solvent extraction process was completed using specimens of Zircaloy-clad UO/sub 2/ irradiated to levels of 6150-14,600 Mwd/TU. Soluble losses of uranium and plutonium to the decladding solutions were about 0.05%. Centrifugation of the decladding solution is probably necessary to remove up to 1% of the UO/sub 2/ present as fines resulting from the fracture of low (93 to 95%) density pellets; high (96%) de… more
Date: May 14, 1962
Creator: Goode, J.H. & Baillie, M.G.
Partner: UNT Libraries Government Documents Department
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DISSOLUTION OF BeO-AND Al$sub 2$O$sub 3$-BASE REACTOR FUEL ELEMENTS. PART I

Description: Aqueous methods for recovering uranium from BeO- and Al/sub 2/O/sub 3/- base gas-cooled-reactor fuel elements are being evaluated. Two methods for processing Hastelloy-X--clad pelletized BeO-base fuels containing 60 to 70% UO/ sub 2/, such as the GCRE and MGCR, seem feasible. One method involves mechanical stripping or chopping of the cladding followed by leaching of the uranium from the fuel pellets with boiling 6-l3M HNO/sub 3/. In the other method the cladding and UO/sub 2/ are dissolved in … more
Date: February 14, 1962
Creator: Warren, K S; Ferris, L M & Kibbey, A H
Partner: UNT Libraries Government Documents Department
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Radiochemical Processing-Off-Site Transportation and Ultimate Storage Problems

Description: Safe and economic methods of handling radioactive materials off-site are required for the successful operation of nuclear chemical plants. These occasions arise in the shipment of spent fuel, radioactive, isotopes, and liquid wastes. An unsolved problem exists in the development of techniques and sites for the final disposal of waste products. (auth)
Date: March 14, 1962
Creator: Blomeke, J. O. & Shappert, L. B.
Partner: UNT Libraries Government Documents Department
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Stress Analysis of the PM-2A Reactor Vessel

Description: The stress analysis performed on the PM-2A reactor vessel and cover is discussed. The maximum combined stress (51,000 psi) occurred in the studs after reaching steady-state conditions. A fatigue analysis indicated that this stress could be safely applied 2500 times, and since the studs do not approach 2500 cycles from initial stud tightening to steady-state conditions, they should not suffer any fatigue damage. (auth)
Date: May 14, 1962
Creator: Rowekamp, B. J.; McLaughlin, D. W.; Chittum, R. A. & Aitken, C. C.
Partner: UNT Libraries Government Documents Department
open access

Equilibrium panel surface temperatures in the SNAP-2 instrument compartment

Description: By equating net radiation to space to I/sup 2/R heating in the SNAP-2 instrument compartments, and neglecting internal radiation between compartments, the panel surface equilibrium temperatures were computed for hot and cold temperature extremes. These extremes are defined by: (1) cold - pre-start phase in the shade, (2) hot - full power phase facing the sun. The results of the heat balances for hottest and coldest cases are presented graphically. These figures relate the equilibrium surface te… more
Date: September 14, 1962
Creator: Gresho, P. M.
Partner: UNT Libraries Government Documents Department
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Contaminant effects study : final report, January 5 to September 15, 1962

Description: From abstract: "This report describes work done on ARF Project C 216 from January 5, 1962 to September 15, 1962. The objectives of the program include evolution of an analytical research program to evaluate effects of environment contributed contamination on precise devices"
Date: November 14, 1962
Creator: Lieberman, A.
Partner: UNT Libraries Government Documents Department
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Reactor and metallurgy R&D programs irradiation processing department FY-1963 - FY-1964

Description: This document describes the objectives, targets and scope of the development programs to be sponsored and conducted by the Irradiation Processing Department in support of the Hanford production reactors during FY-1963 - 1964. it is anticipated that the basic funding level for the IPD Reactor and Metallurgy R&D programs for the next two years will total $6,930,000 annually including overhead. Approximately 70 per cent of these funds will be directed in support of the N Reactor, and the remainder… more
Date: September 14, 1962
Creator: Greager, O. H.
Partner: UNT Libraries Government Documents Department
open access

Irradiation Processing Department Monthly Report: November 1962

Description: This document details activities of the Irradiation Processing Department during the month of November, 1962. 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: December 14, 1962
Creator: Hanford Atomic Products Operation. Irradiation Processing Department.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: November 1962

Description: This is the monthly report for the Hanford Laboratories Operation, November 1962. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: December 14, 1962
Creator: Hanford Laboratories
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation monthly activities report, August 1962

Description: This is the monthly report for the Hanford Laboratories Operation August 1962. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.
Date: September 14, 1962
Partner: UNT Libraries Government Documents Department
open access

Production reactor process tube, dummy, and fuel element cladding film and radioactivity studies

Description: During the normal operation of reactors ionic, particulate and colloidal substances in the coolant are activated as they pass through the neutron flux. The parent substances for the activated materials come from several sources: transient corrosion products from the coolant system piping and fuel element cladding, coolant additives and coolant impurities. Previous studies have shown that a major portion of these substances do not simply pass through the neutron flux field but undergo complex so… more
Date: March 14, 1962
Creator: Perrigo, L. D.
Partner: UNT Libraries Government Documents Department
open access

Reactivity accounting by ``CALHOT``, a one-group one-dimensional buckling code

Description: Normal Pile exposure variations and day-to-day operating reactivity adjustments must be compensated by a combination of in-reactor poison and enrichment. The calculation of current reactivity status and the prediction of future trends is an integral part of the Physicist`s responsibility. This document describes the computer program ``CALHOT,`` which is based upon one-group diffusion theory, and is intended to be used in routine reactivity-enrichment calculations. It offers the advantages over … more
Date: December 14, 1962
Creator: Chitwood, R. A. & Toyooka, R. T.
Partner: UNT Libraries Government Documents Department
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Design Criteria for Reactor Test Support Facility at NRTS

Description: This technical report provides a design criteria for a technical support facility for the Lithium Cooled Reactor Experiment (LCRE) and SNAP-50-DR-1 Test Facilities. The support facility is adjacent to the LCRE Test Facility and is located completely within the existing Building 629 structure at the former ANP area of the National Reactor Testing Station (NRTS) near Idaho Falls, Idaho. The information and specifications presented establish the basis for the design of laboratories, shops and en… more
Date: September 14, 1962
Creator: Macfarlane, D. B.
Partner: UNT Libraries Government Documents Department
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Design of a Pilot Plant Facility for Radioactive Demonstration of the Pot Calcination Process

Description: Based on process development work at ORNL, a facility was designed for demonstration of the pot calcination process with a variety of high-level radioactive wastes. In this facility, operational and control problems associated with an integrated process can be identified and solved, procedures to improve characteristics of the calcine can be studied, and important aspects of calcine temperature distribution and fission product behavior can be observed. Installation of the facility is planned fo… more
Date: December 14, 1962
Creator: Wheeler, B. R. & Buckham, J. A.
Partner: UNT Libraries Government Documents Department
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Test Program for 30 Megawatt Prototype Sodium Intermediate Heat Exchanger and Steam Generator

Description: The designer's concept of a test program for the 30-Mw prototype intermediate heat exchanger and steam generator designed and fabricated as part of the Sodium Components Development Program is presented. The performance data will serve to verify the thermal design, or allow application of improved techniques to future designs, give an improved basis for stress analysis in design of future units, and demonstrate the capability and limitations of the units in relation to the performance specifica… more
Date: September 14, 1962
Partner: UNT Libraries Government Documents Department
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Army Reactors Program Progress Report

Description: Research and development on metallurglcal aspects of pressurized-water systems is summarized. A survey was made of the methods of determining fuel burnup. The mechanisms and kinetics of the loss of boron during heating at 1135 deg C in various dynamic environments were determined. A model was developed to quantitatively characterize the UO/sup 2/ dispersion microstructure of roll-clad fuel plates relative to an ideal'' dispersion. In order to avoid the loss of boron from UO//sub 2/- stainless s… more
Date: February 14, 1962
Partner: UNT Libraries Government Documents Department
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Analysis Of Activation Measurements Of Th$sup 232$ Resonance Captures In The Peach Bottom (40-MW(E) Prototype HTGR) Critical Assembly

Description: Measurements of thorium resonance-capture activations relative to those of Au/sup 197/, which were made in the Peach Bottom (HTGR) critical assembly, are analyzed and compared with thorium resonance activations calculated from tabulated values of the resonance parameters. The new vanadium-subtraction method that was applied is shown to measure thorium resonance captures relative to those of Au/sup 197/ to within several per cent in this geometry. The measurements show that the lowest several re… more
Date: September 14, 1962
Creator: Sampson, J. B.
Partner: UNT Libraries Government Documents Department
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