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Hazards Report for the BF3 Withdrawal Mechanism in the SM-1

Description: A design and operational description is presented of a BF/sub 3/ withdrawal mechanism planned for installation on one of the two startup channels at the SM-1. An analysis of possible malfunctions is included. (J.R.D.)
Date: October 13, 1961
Creator: Coombe, J. R.
Partner: UNT Libraries Government Documents Department
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SORPTION OF URANIUM ON ZIRCONIUM OXIDE

Description: The sorption of the ions of uranium, copper, and nickel on hydrous zirconium oxide was investigated at temperatures from 25 to 250 deg C. The experiments were performed by equilibrating 5 ml of the test solution with 0.5 g of zirconium oxide in a titanium autoclave, which was heated by means of a rocking furnace. The sorption of uranium was affected by characteristics of the zirconium oxide, temperatare of equilibration, and concentrations of uranium and of free acid in the uranyl sulfate solut… more
Date: September 13, 1961
Creator: Goldstein, G.
Partner: UNT Libraries Government Documents Department
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TITANIUM PUMP LOOP FOR AQUEOUS SOLUTIONS AT HIGH TEMPERATURES

Description: A titanium pump loop, designed to circulate aqueous solutions at temperatures and pressures up to 370 deg C and 3000 psia, was constructed. It is to be used to study the chemical stability of uranyl sulfate fuel solutions of interest to the Fluid Fuels Reactor Program. The total loop voluime was minimized so that about 2 liters uf solution was sufficient for loop operation. The equipment includes a sampling system to remove solution samples from the loop while operating at elevated temperature … more
Date: December 13, 1961
Creator: Baker, J.M. & Bolt, S.E.
Partner: UNT Libraries Government Documents Department
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Research and Development Activities Fixation of Radioactive Residues Quarterly Progress Report, July-September 1961

Description: Progress is reported on research and development work in pot calcination and radiant-heat spray calcination studies of synthetic Purex high-level wastes; and sorption studies using synthetic minerals and resins as well as natural minerals. The calcination studies are discussed in terms of batch calcination, melting of pot calcination products, spray calcination, and off-gas treatment; and sorption studies in terms of mineral reactions, fixation chemistry, and condensate wastes. (B.O.G.)
Date: October 13, 1961
Creator: Irish, E.R. ed.
Partner: UNT Libraries Government Documents Department
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MEASUREMENT OF THE VAPOR PRESSURE OF TBP

Description: Two methods, the transpiration and direct P/sup 32/ counting methods, were tested for use in measuring the vapor pressure of TBP. With the transpiration technique, measured TBP vapor pressures were sufficiently reproducible, and probably of sufficient accuracy, to warrant improvement of the apparatus and its use in measuring the vapor pressure of TBP over various TBP- diluent-HNO/sub 3/-H//sub 2/O-UO/sub 2/ (NO/sub 3/)sub 2 solutions. With this method the vapor pressure of TBP containing 0.2 wt… more
Date: December 13, 1961
Creator: Faure, A. & Davis, W. Jr.
Partner: UNT Libraries Government Documents Department
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TWENTY-FIVE GROUP REACTOR NUCLEAR DATA TAPE NEUTRON CROSS SECTIONS

Description: A compilation is presented, in the twenty-five group Reactor Nuclear Data Tape format, of neutron cross sections for elements of major interest for GE- ANPD reactor analysis. The tabulated data are a reproduction of neutron cross section information contained on the Reactor Nuclear Data Tape, which was recently prepared. A brief outline of methods used in processing of the cross sections is also included. (auth)
Date: June 13, 1961
Creator: Zwick, J. W. & Kostigen, T. J.
Partner: UNT Libraries Government Documents Department
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The processing of Pu scrap at Hanford

Description: This study responds to the requests for data on the subject contained in the D.S. Burrows letter entitled ``Processing Plutonium Scrap`` (symbol FAc:EAS) dated June 30, 1961 and received for reading by Chemical Processing Department Management on July 5, 1961. Cognizance is also taken of the July 5 teletype from G.F. Quinn requesting an appendix updating the content of our document HW-63560 (Pu Reclamation -- January 18, 1960) with regard to safety aspects covered therein. Appendix A of this pa… more
Date: July 13, 1961
Creator: Grimm, K. G.
Partner: UNT Libraries Government Documents Department
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Maximum liability evaluation: Strontium and cesium shipments on Decalso media

Description: This report summarizes the evaluations of the maximum monetary liability associated with cesium-137 shipments in the STT Casks and strontium-90 shipments in the HAPO-IA Cask. These evaluations are of most immediate importance since these shipments are planned for the month of March 1961. These liability evaluations concern the direct consequences of a release of the fission product shipment in each case, but do not cover the probability of such events occurring. The liability evaluation of the … more
Date: March 13, 1961
Creator: Watson, E. C. & Zahn, L. L.
Partner: UNT Libraries Government Documents Department
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Interim goal exposure plans for O-III-NB and O-III-EB material for B, D, DR and F reactors

Description: The purpose of this report is to recommend variable goal plans for natural and enriched bumper fuel elements, specifically for 0-III-NB and 0-III-EB materials, to be irradiated at the B, D, DR, and F Reactors. The average goal exposure for all bumper fuel elements at D Reactor was specified to be 900 MWD/T, with provisions being made for revision by normal procedures. Exposures for enriched bumper material at the B, M. and F Reactors were not specified in the PITA supplement authorizing chargin… more
Date: February 13, 1961
Creator: Bloomstrand, R. R.
Partner: UNT Libraries Government Documents Department
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Production test IP-394-I: Use of PT-216 fuel columns for routine axial flux determination

Description: It is the objective of this production test to authorize the use of PT IP-216-A (Quality Certification) fuel columns and supplementary numbered columns are required for obtaining routine axial flux measurements suitable for metal performance analysis.
Date: February 13, 1961
Creator: Graves, S. M.
Partner: UNT Libraries Government Documents Department
open access

Fabrication Costs

Description: This document from the principal engineer of the manufacturing section at Hanford calls attention to irreconcilable costs for two fuel fabrication studies. Specifically, the major trouble areas appear to be in refinery, green salt and machining steps.
Date: September 13, 1961
Creator: Lang, L. W.
Partner: UNT Libraries Government Documents Department
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The Equation of State of Solids at Low Temperature

Description: Technical report describing and evaluating the the three experimental methods for obtaining equation of state data at low temperatures; (1) approximate measurement of the PVT relationship by a piston-displacement technique, (2) the measurement of a heat capacity at constant volume as a function of molar volume and temperature, and (3) direct measurement of the pressure variation of the elastic constants using ultrasonic techniques. X-ray methods also might be applicable.
Date: October 13, 1961
Creator: Bernardes, N. (Newton), 1931- & Swenson, C. A.
Partner: UNT Libraries Government Documents Department
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Nuclear rocket engine dynamics study

Description: No Description Available.
Date: October 13, 1961
Creator: Blake, P.J. & Esselman, W.H.
Partner: UNT Libraries Government Documents Department
open access

Solvent Extraction Recovery and Purification of Strontium-90

Description: A solvent extraction process was developed to produce high-purity Sr/sup 90/ from an irradiated U reprocessing waste solutlon. The extractant is D2EHPA diluted with TBP and Shell Spray Base. The process uses an acetic acid-acetate huffered aqueous phsse which is countercurrently contracted with the D2EHPA organic phase. Calcium and some Ce/sup 144/ extract with the Sr/sup 90/; extraction of other contaminants (Zr/sup 95/, Nb/sup 95/, Ru/sup 106/, and inert lead and iron) is prevented by adding … more
Date: December 13, 1961
Creator: Schulz, W. W.; Mendel, J. E. & Richardson, G. L.
Partner: UNT Libraries Government Documents Department
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ENERGY DISTRIBUTION OF IONS AND ELECTRONS IN DCX AFTER BURNOUT: ORACLE CODE EDDIE

Description: Numerical calculations of energy distributions of ions and electrons in DCX in steady state after burnout are discussed. The d-c plasma potential establishing quasineutrality is also determined. The electron distribution is found to be Maxwellian, but the ion distribution is not. For typical DCX conditions, the plasma potential is an appreciable fraction of the injected ion energy (tens of kev). The code employed, ORACLE code EDDIE, which solves coupled, steady-state Fokker-Planck equations gov… more
Date: September 13, 1961
Creator: Fowler, T.K. & Rankin, M.
Partner: UNT Libraries Government Documents Department
open access

OPERATIONAL INVESTIGATION OF NUCLEAR INSTRUMENTATION. CORE I, SEED 2. Test Results (T-643725). Section 2

Description: The test data indicate that the response of the Intermediate-Range log- level-current instrumentation was linear between 5 x 10/sup -//sup 1//sup 1/ to 5 x 10/sup -//sup 7/ amperes for start-up rates of 0.2 to 1.0 decsdes per minute based on the as sumption that the reactor trsnsient behavior can be predicted by the reactor kinetic equation. A comparison of the intermediate range start-up rate readings with the start-up rates determined from the slope of the intermediate-range log-level current… more
Date: March 13, 1961
Partner: UNT Libraries Government Documents Department
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Tests of the HNPF Plugging Meter

Description: A plugging meter designed for the Hallam Nuclear Power Facility was tested. Plugging performance was satisfactory and excellent reprcducibility was achieved. Although the time limitations precluded complete testing of the automatic control equipment, the tests performed gave satisfactory indication of correct performance. (auth)
Date: February 13, 1961
Creator: Davis, K. A.
Partner: UNT Libraries Government Documents Department
open access

Effect of Temperature on Radiation-Induced Contraction of Reactor Graphite

Description: Radiation-induced contraction as a function of temperature was studied in needle-like and conventional coke graphites from 450 to 1200 deg C. Fast neutron exposures ranged up to 3.2 x 10/sup 21/ nvt, E) 0.18 Mev, corresponding to approximately 20,000 Mwd/at. in a Hanford graphitemoderated reactor. The results significantly extend information on the effect of high temperature irradiation on needle-like coke graphites manufactured with particle size, impregnation, and graphitization temperature a… more
Date: September 13, 1961
Creator: Davidson, J. M. & Helm, J. W.
Partner: UNT Libraries Government Documents Department
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