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Ionization Equilibrium Equation of State (open access)

Ionization Equilibrium Equation of State

Abstract: "A simple solution to Saha's equation has been obtained. The method of solution involves iteration with respect to the electron pressure or concentration and can be applied to the simultaneous calculations of any number of ions. Sample results are given for lithium and aluminum."
Date: October 5, 1959
Creator: Rouse, Carl A.
System: The UNT Digital Library
Chemical Processing Department Control Study: Final report on the control of CPD product materials (open access)

Chemical Processing Department Control Study: Final report on the control of CPD product materials

The purpose of this report is to present the conclusions and recommendations obtained during the course of the CPD Control Study and the conceptual framework upon which they are based. Primary emphasis has been given to the control of product materials. In order to logically present the background for the definition and delineation of an appropriate CPD Control System, Section III of this report discusses a control system in the following manner; (1) the description of the control system information requirements, (2) the definition of the conceptual framework of product material control, (3) the discussion of the interrelationships of production scheduling, process control and accountability and (4) the methods for the effective utilization of control system information. Section IV utilizes this conceptual framework in order to enable a logical presentation of a proposed product material control system for the CPD. A summary of conclusions and recommendations is included in Section II. The Appendices consist of discussions of specific analysis conducted during the study. Other related reports that have been issued during the course of the study are included in the references.
Date: January 5, 1959
Creator: Shepard, D. F.; Hough, C. G.; Burke, R. C. & Stewart, K. B.
System: The UNT Digital Library
Total Control vs Reactivity Parameters (open access)

Total Control vs Reactivity Parameters

Changes in pile operating parameters, such as fuel exposure, paver, and reactivity gain upon water loss affect the potential reactivity of the operating, pile and, therefore, the amount of enrichment required to operate under the desired conditions. Similarly a change in ECT (through enrichment location) changes the amount of enrichment.needed to maintain a constant reactivity. Many of the factors which influence the operating reactivity have quite different effects upon the reactivity of the dry pile with the ball 3X system inserted; therefore, changes in operating parameters may cause sizeable changes in requirements for supplementary control to maintain sub-criticality in the dry pile. It is the purpose of this document to summarize these trends in disaster control requirements for the K piles. The trends are presented as graphs of supplementary control requirements against a single varying parameter. All other parameters are held fixed as specified on each graph. The fuel element (central orifice zone) for all examples is the K-2 slug. In general, the slopes of these curves are only slightly dependent upon the specific values assigned the fixed parameters, although the magnitude of the control requirements may be quite dependent on these values. Unless otherwise noted any dependence of the …
Date: February 5, 1959
Creator: Simpson, D. E.
System: The UNT Digital Library
Radiochemistry for the rupture of a tube in tube fuel element in KER Loop 3 (open access)

Radiochemistry for the rupture of a tube in tube fuel element in KER Loop 3

On the 0000--0800 shift, September 30, 1959, the delayed neutron monitor on KER Loop 3 gave a high coolant activity signal. Events occurred rapidly that tended to substantiate the possibility of a fuel element failure in this loop. KE reactor was shut down immediately thereafter. This report is being written to summarize the sequence of events prior to and those following the KE reactor scram and to discuss the results and significance of data from analyses on coolant and coupon samples taken from KER Loop 3.
Date: November 5, 1959
Creator: Perrigo, L. D.
System: The UNT Digital Library
Power Reactor Fuel Reprocessing Status Report of ORNL Chemical Technology Division for April 1959 (open access)

Power Reactor Fuel Reprocessing Status Report of ORNL Chemical Technology Division for April 1959

None
Date: May 5, 1959
Creator: Blomeke, J. O.; Goeller, H. E. & Lewis, W. H.
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment:  Dynamic Utility Test Loop (open access)

Liquid Metal Fuel Reactor Experiment: Dynamic Utility Test Loop

This report provides an overview of the creation of the Liquid Metal Fuel Reactor Experiment program. It furthers the work by constructing a single loop to test all the components required for the 16 loop reactor. This utility loop was also constructed to provide a facility for testing various components such as valves and flow meters.
Date: May 5, 1959
Creator: Baker, O. H.
System: The UNT Digital Library
Eurochemic Information Exchange- Answers to Specific Questions (open access)

Eurochemic Information Exchange- Answers to Specific Questions

A number of the questions which have been posed to us in the subject references are commented upon below. These have been reviewed by personanel of the Research and Engineering Operation and the Facilities Engineering Operation, Chemical Processing Department, and of the Chemical Research and Development Operation, Hanford Laboratories Operation. Particular acknowledment is given G. J Alkire, J. P. Duckworth, J. B. Fecht, R. G. Geier, E. R. Irish, H. M. Jones, G. C. Oberg, A. M. Platt, W. H. Reas, W. C. Schmidt, R. J. Sloat, W. H. Swift, M. T. Walling and L. L. Zahn of these organizations for assistance given assembling this information.
Date: May 5, 1959
Creator: Hill, O. F.
System: The UNT Digital Library
Stability of Pressurized Tubes During Primary Creep (open access)

Stability of Pressurized Tubes During Primary Creep

This note describes an analysis of the primary creep rates in thin-walled pressure tubing. The analysis accounts for the increase in tube radius and decrease of tube wall thickness. Both of these effects increase the stress; hence, they can affect the creep rate and cause unstable creep conditions.
Date: June 5, 1959
Creator: Merckx, K. R.
System: The UNT Digital Library
A Closed Circuit Television System for In-Well Use -- Interim Report (open access)

A Closed Circuit Television System for In-Well Use -- Interim Report

Wells drilled to date on the Hanford project represent and initial investment of over one million dollars. These nearly six hundred wells have been used and will continue to be used for observation and monitoring purposes of direct interest to ground disposal of radioactive wastes. Through measurement of depth to the water table the changing gradients as a result of large volume waste disposal are determined and direction of ground water flow established. The extent of contamination in ground water is measured in samples dawn from these wells. Aquifer permeability is measured and ground water velocity predicted from pumping tests carried out out in these structure
Date: August 5, 1959
Creator: Ratcliffe, C. A.
System: The UNT Digital Library
Eurochemic Assistance Program: Status Report as of April 1, 1959 (open access)

Eurochemic Assistance Program: Status Report as of April 1, 1959

Considerable delay has occurred in getting ratification of the Eurochemic charter by 80% of the participating nations. The French, who were not expected to ratify the charter until an elected government was again established , actually ratified under de Gaulle late in 1958.
Date: May 5, 1959
Creator: Nicholson, E. L.
System: The UNT Digital Library
Nuclear and Economic Characteristics of several Two-Region Homogeneous Reactors (open access)

Nuclear and Economic Characteristics of several Two-Region Homogeneous Reactors

The nuclear characteristics and fuel costs of a number of aqueous homogeneous reactors have been estimated. Most of the reactors studied were cylindrical, two-region power-breeders variously having between 0 and 300 g/l of thorium in the core and between 500 and 1000 g/l of thorium in the blanket. The results of the calculations, including breeding ration, fuel inventories, doubling times, and net fuel costs, are summarized in this report.
Date: June 5, 1959
Creator: Rosenthal, M. W.
System: The UNT Digital Library
A Review of the Mathematical Formulation of the Problem of Inelastic Neutron Scattering by Polycrystalline Material (open access)

A Review of the Mathematical Formulation of the Problem of Inelastic Neutron Scattering by Polycrystalline Material

A self-contained developmental or the formation of the problem of inelastic neutron scattering by crystals is presented. although nearly all of the methods and results used in the present discussion have appeared in a variety of previously published papers, additional mathematical details are given here which have been found by thee authors to aid in understanding the final results.
Date: June 5, 1959
Creator: Preskitt, C. A.
System: The UNT Digital Library
Chemical Development Section C Monthly Progress Report July 1959 (open access)

Chemical Development Section C Monthly Progress Report July 1959

Nitrate contained in raffinates from Canadian Blind River mills interferes seriously with thorium extraction by secondary amines. With primary amines, however, the effect is negligible and these compounds are the preferred process extractants.
Date: August 5, 1959
Creator: Brown, K. B.; Allen, K. A.; Blake, C. A.; Coleman, C. F.; Crouse, D. J.; Ryon, A. D. et al.
System: The UNT Digital Library
Calculation of Transport Cross Sections (open access)

Calculation of Transport Cross Sections

Many elements exhibit anisotropic scattering at energies of interest in reactor calculations. A method is presented for the calculation of transport cross sections including the observed anisotropy.
Date: August 5, 1959
Creator: Nestor, C. W.
System: The UNT Digital Library
Temperature and Rate of Heat Removal of UO2 Test Elements (open access)

Temperature and Rate of Heat Removal of UO2 Test Elements

The method of calculation of various quantities relating the temperature and the rate of heat removal of UO2 test elements is presented. Graphs of the appropriate quantities as a function of the rate of heat removal are included.
Date: August 5, 1959
Creator: Perry, A. M.
System: The UNT Digital Library