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105-N charge-discharge rates

Description: Figures have and can be generated that indicate a higher charge-discharge rate if required before 105-N will be comparable with existing reactors. Also, these figures show an apparent operating cost incentive to increase the charge-discharge rates proposed for 105-N. Although these figures may be true by themselves, other figures developed from the same information and stated on a basis that affords a true comparison, show that the proposed rates for 105-N are compatible with those in existing … more
Date: July 2, 1959
Creator: Nesbitt, J. F.
Partner: UNT Libraries Government Documents Department
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Application of Rare Earths to Ferrous and Non-Ferrous Alloys

Description: The applications for rare earths as mixed metals or their oxides in the steel industry have multiplied rapidly in the past decade and are now providing a variety of alloys with markedly improved properties.
Date: November 2, 1959
Creator: Collins, J. F.; Calkins, V. P. & McGurty, J. A.
Partner: UNT Libraries Government Documents Department
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Decontamination of the KER Rupture Experiment Loop Test Series B - Tests No. 1 and 2

Description: The first series tests in the KER-REP-1 loop proved that a fisssion product contaminated loop could be decontaminated to a safe level for contact maintenance. The second series of tests ere scheduled for a more thorough evaluation of these processes includes specific decontamination factors, process corrosion rates, loop activity reduction factors (loop decontamination factors), and any preferential decontamination which may be present.
Date: November 2, 1959
Creator: Weed, R. D.
Partner: UNT Libraries Government Documents Department
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Effects of 100-K water plant expansion on Panellits and orifices

Description: The information reported here was requested by M.H. Schack, Facilities Engineering Operation. It pertains to the 100-K water plant expansion Project CG-775. In this project, cooling water pumping capacity will be increased from 178,000 GPM existing to 188,000 GPM and 200,000 GPM for five and six modified pumps respectively. Effects of increased through-put on process tube flow metering elements and on the reactor Panellit gauges have been examined. This information was required to determine cos… more
Date: December 2, 1959
Creator: Stepnewski, D. D.
Partner: UNT Libraries Government Documents Department
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Electrical Insulation Characteristics of Helium Gas at High Pressure and Temperatures

Description: Published information is not available for accurate prediction of the electrical insulating characteristics of helium at high pressures and temperatures. In general the breakdown voltage increases as the gas pressure is increased and decreases as the gas temperature is increased. The relatively low breakdown voltage of helium accents the importance of additional investigation in this field. (auth)
Date: January 2, 1959
Creator: Stulting, R. D.
Partner: UNT Libraries Government Documents Department
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Exploration of Radiometric Methods

Description: The compilation of possible analyses in aqueous solution is nearly complete. A chart has been constructed showing the elements which may be determined radiometrically. The radiometric general scheme of analysis has been roughly blocked out. The next-planned phase is to select specific reagents and determine the details of such analysis.
Date: April 2, 1959
Creator: Driscoll, William J. & Scott, Benjamin F.
Partner: UNT Libraries Government Documents Department
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Fuel Cycle Cost for Aqueous Homogeneous Reactors

Description: By using a large central fuel and blanket reprocessing facility, slurry-fueled aqueous homogeneous reactors can attain an estimated minimum fuel cycle cost of 1.4-1.6 mills/kwh; with solution-fueled two-region reactors, a doubling time of 14 years may be obtained at a fuel cycle cost of 2.0 mills/kwh. On-site processing appears desirable only for large power stations made up of reactors designed for short doubling times. For instance, a solution-fueled two-region reactor can attain a 12-year do… more
Date: June 2, 1959
Creator: Culler, F. L.
Partner: UNT Libraries Government Documents Department
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GEH-4-42, 47; Hot pressed, I and E cooled fuel element irradiation

Description: In our continual effort to improve the present fuel elements which are irradiated in the numerous Hanford reactors, we have made what we believe to be a significant improvement in the hot pressing process for jacketing uranium fuel slugs. We are proposing a large scale evaluation testing program in the Hanford reactors but need the vital and basic information on the operating characteristics of this type slug under known and controlled operating conditions. We, therefore, have prepared two typi… more
Date: November 2, 1959
Creator: Neidner, R.
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T)

Description: Report documenting two in-pile loop experiments conducted at the Battelle Research Reactor-Gas Cooled Reactor (BRR-GCR). These experiments test heat transfer calculations and the behavior of the fuel element under severe thermal-cycling conditions.
Date: July 2, 1959
Creator: Nakazato, S.; Williams, P. M. & Wilson, W. D.
Partner: UNT Libraries Government Documents Department
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Instrumentation and Controls Division Annual Progress Report, July 1, 1959

Description: Report documenting ongoing research and development carried out by the Instrumentation and Controls Division of the Oak Ridge National Laboratory.
Date: November 2, 1959
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
Partner: UNT Libraries Government Documents Department
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Leaching of RAINIER Debris

Description: The possibility of series ground water contamination is an important consideration in the peaceful application of contained nuclear explosions . A series of leasing tests were performed on RAINIER debris to established the extent of ground water contamination which would result from such debris. The leaching data show that no appreciable amounts of radioactive contaminants will be released to ground water. Only about 0.5% of the activity was leached from debris crushed to <53 mu when agitated f… more
Date: April 2, 1959
Creator: Bond, Walter Dayton
Partner: UNT Libraries Government Documents Department
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Low-Energy [pi] Mesons in the Cosmic Radiation

Description: The intensity of 𝜋 mesons in the atmosphere is investigated in the energy region 𝐸kin≲50 Mev at sea level and at mountain altitudes. Positive 𝜋 mesons coming to rest in an absorber-scintillator are identified by the characteristic 𝜋−𝜇 decay. They are detected electronically and recorded photographically. The value 1.45±0.09 is adopted for the negative-to-positive ratio at small energies. The omnidirectional intensities 𝐽𝜋+ of slow positive 𝜋 mesons at sea level (91m), Echo Lake, Colorado (326… more
Date: February 2, 1959
Creator: Fotino, Mircea
Partner: UNT Libraries Government Documents Department
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Nuclear-Conventional Power Plant Cost Study. Conventional Coal Fired Power Plants : 25,000 KW to 325,000 KW for Argonne National Laboratory, Lemont, Illinois

Description: In order to establish a basis for comparing the estimated cost of nuclear power plant designs, a set of general and detailed design considerations for conventional coal-fired power plants was established. Five preliminary designs of conventional coal-fired power plants ranging in size from 25to 325 mw were selected, and cost estimates were prepared. ( A.C.)
Date: March 2, 1959
Creator: Chittenden, W. A.
Partner: UNT Libraries Government Documents Department
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Operating Procedure for the Bulk Shielding Reactor, Fourth Edition

Description: Report issued by the Oak Ridge National Laboratory discussing the 4th revision to the operating procedures used with the bulk shielding reactor. Standard procedures, emergency procedures, and authorized personnel for the bulk shielding reactor are presented. This report includes tables, and illustrations.
Date: January 2, 1959
Creator: Henry, K. M. & Maienschein, F. C.
Partner: UNT Libraries Government Documents Department
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ORIC R-F Model III Progress Report

Description: The ORIC (Oak Ridge Relativistic Isochronous Cyclotron) radiofrequency system for which Model III represents the resonator is the third system which has received enough consideration to warrant construction of a model. The purpose of the model is to check the calculations for the frequency range and excitation power of the resonator. After an introductory description of the r-f system and model, the detailed calculations of the properties of the model will be given followed by the data from me… more
Date: June 2, 1959
Creator: Worsham, R. E. & Mosko, S. W.
Partner: UNT Libraries Government Documents Department
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Poison Rod Requirements for a Solid-fuel Leacher Tank

Description: Estimates were made of the amount of neutron poisoning, in the form of boron rods, required to maintain subcriticality in a tank used for dissolution of solid fuel elements. The tank under consideration was a cylinder 19.5 inches in diameter and 6 ft in height. Maximum concentrations of fuel and fertile material resulting from dissolution of various type fuel elements are tabulated. Below the maximum concentrations listed, it was found that the limiting poisoning requirements are associated wit… more
Date: March 2, 1959
Creator: Prince, B. E.
Partner: UNT Libraries Government Documents Department
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Power Reactor Fuel Reprocessing: Mechanical Phase

Description: The major events of the Mechanical Phase of the Power Reactor Fuel Reprocessing program during August 1959 are summarized here.
Date: September 2, 1959
Creator: Klima, B. B.
Partner: UNT Libraries Government Documents Department
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Process Vessel Precision and Accuracy Estimates

Description: The following is an attempt to explain the method by which the precision associated with an observed volume reading in a process vessel (E-12, C-1) should be calculated based upon a regression analysis of cumulative data. There are two types of volume measurement consists of estimating the total volume in a vessel at some inventory time. A transfer measurement consists of estimating the volume between two levels within a tank.
Date: March 2, 1959
Creator: Hough, C. G.
Partner: UNT Libraries Government Documents Department
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PRTR Single Tube Prototype Mockup (STPM) Operational Characteristics

Description: The Single Tube Prototype Mockup (STPM) was constructed to be used as a tool to evaluate the mechanical problems involved in operating and maintaining many components of the Plutonium Recycle Test Reactor (PRTR). This report has been written to acquaint interested HAPO components with the capability of the STPM and for use as an aid in scheduling tests and/or to properly evaluate testing results obtained from the mockup.
Date: July 2, 1959
Creator: Scott, P. A.
Partner: UNT Libraries Government Documents Department
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PT-IP-269-A-FP, evaluation of the stability of cores from extruded tubes

Description: If material received under this program is deemed acceptable for reactor charging, this test will authorize irradiation of fourteen monitor columns which shall be discharged at 200, 400 and 800 MWD/T to observe the performance of this material. This test shall run concurrently with irradiation of quantities up to 60 tons/month to be authorized separately.
Date: November 2, 1959
Creator: Hall, R. E.
Partner: UNT Libraries Government Documents Department
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Quarterly Report of Non-Production Reactor Fuels Reprocessing Budget Activity 3790

Description: This report summarizes the research and development work carried out during March, April and May, 1959, for Budget Activity 2790 - Separations Development for Non-Production Reactors, The effort on Activity 2790 will enable Hanford to begin reprocessing in January, 1962, the fuel elements from power reactors which employ depleted or slightly enriched uranium fuels.
Date: July 2, 1959
Creator: Cooper, V. R.
Partner: UNT Libraries Government Documents Department
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Results of production test IP-206-CE in pile tests of boron stainless steel splines

Description: A solid spline made of 430 boron stainless steel was tested in tube 2451 at D Reactor. The test was conducted to compare the boron carbide filled hollow aluminum spline presently used with a solid steel spline which is being considered as a substitute. Usage of hollow splines has shown that a solid rugged spline would be highly desirable. Comparisons of spline radiation and reactivity effect were obtained both in-pile and in out-of-pile test facilities. Results of the production test are report… more
Date: January 2, 1959
Creator: McCarthy, P. B.
Partner: UNT Libraries Government Documents Department
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Rubber Ring Dosimeter Calibrations with the Plutonium Radiation Spectrum

Description: This work was initiated as an evaluation of the application pf rubber finger ring dosimeters to the control of extremity radiation exposure. The use of film dosimeters is a well known general practice throughout the radiation protection profession, however, film radiation exposure measurements associated with plutonium metal handling present a unique problem. The practical measurement of extremity dose depends upon the accuracy and reproducibility of results under the most severe conditions usi… more
Date: September 2, 1959
Creator: Swanberg, F., Jr & Andersen, B. V.
Partner: UNT Libraries Government Documents Department
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