Resource Type

Irradiation of an Aluminum Alloy-Clad Ceramic Pellet-Fueled Plate (open access)

Irradiation of an Aluminum Alloy-Clad Ceramic Pellet-Fueled Plate

From Introduction: "An experiment, designated MTR-W10, was designed to determine the effects of high burnup on the cladding and fuel of an aluminum-1% nickel alloy (M-388)-clad ceramic pellet-fuelded plate if the type manufactured at Argonne for the BORAX-IV core. Conditions of irradiation were selected to allow local boiling at the high flux end of the plate at a pressure of 600 psig."
Date: May 1960
Creator: Gavin, A. P.
System: The UNT Digital Library
Kinetics of Dissolution of Zirconium in Molten Uranium (open access)

Kinetics of Dissolution of Zirconium in Molten Uranium

None
Date: May 1960
Creator: Golden, G. H.
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment: Operation and Testing of a Nonnuclear Liquid-Metal System (open access)

Liquid Metal Fuel Reactor Experiment: Operation and Testing of a Nonnuclear Liquid-Metal System

Extensive experimental program undertaken to provide data on the operation and testing of a bismuth-to-bismuth dual-loop system.
Date: May 1960
Creator: unknown
System: The UNT Digital Library
Measurements of Light Transmittance Through Thick Shielding Windows (open access)

Measurements of Light Transmittance Through Thick Shielding Windows

None
Date: May 1, 1960
Creator: Eckels, T. W.
System: The UNT Digital Library
NATURAL AND FORCED-CIRCULATION BOILING STUDIES (open access)

NATURAL AND FORCED-CIRCULATION BOILING STUDIES

None
Date: May 1, 1960
Creator: Marchaterre, J.F.; Petrick, M.; Lottes, P.A.; Weatherhead, R.J. & Flinn, W.S.
System: The UNT Digital Library
Nuclear Characteristics of Cylindrical Breeder Reactors Containing Thorium in Pellet Form (open access)

Nuclear Characteristics of Cylindrical Breeder Reactors Containing Thorium in Pellet Form

The results of nuclear calculations for aqueous homogeneous reactors containing blanket thorium in pellet form are presented. Critical core fuel concentrations, gross breeding ratios, power densities, and multiplication as dependent on core fuel concentration and neutron balances are included. Critical U/sup 233/ core concentration for a 24in.-diam. core was 8.4 gm/l when U/Th was 0.003 in the blanket and the relative power density at the core wall was 1.04 kw/ l/Mw. A 48-in.-diam. core required 1.6 g U/sup 233//l in the core and the relative power density at the core wall was 0.095 kw/l/Mw. The reactors had gross breeding ratios of 1.12 and 1.09, respectively. (auth)
Date: May 1, 1960
Creator: Vondy, D. R.
System: The UNT Digital Library
OMR Degasifier Loop Experiment (open access)

OMR Degasifier Loop Experiment

Abstract: A loop has been constructed to study the removal of water and highly volatile materials from Organic Moderated Reactor coolant by vacuum degasification. An analysis of the process was made to determine the most important parameters for study during the experimental program.
Date: May 1, 1960
Creator: Corporales, G. W. & Benson, P. R.
System: The UNT Digital Library
OMRE Fuel Plate Surface Temperature Measurement (open access)

OMRE Fuel Plate Surface Temperature Measurement

Abstract: Accurate measurement of OMRE fuel-element surface temperatures is important for evaluation of the performance of organic compound as moderator and coolant materials in nuclear reactors; a mixture of polyphenyls has been used in reactor operation to-date.
Date: May 1, 1960
Creator: Sudar, S.
System: The UNT Digital Library
Optics of High-Energy Beams (open access)

Optics of High-Energy Beams

Many of the experiments now being conducted on high-energy accelerators requires the use of beams of charged secondary particles. It is worth while at this time to attempt to summarize information about some of the most useful methods of setting up such beams. We are not concerned here with the primary beam of the accelerator. Rather, they assume that a target is struck by the primary beam and that it is desired to form a beam from the secondary charged particles that emerge from collisions within the target. The simplest system of forming this beam of secondary particles involves the use of magnetic fields only. In most cases it is desirable to obtain a beam of particles of known magnetic rigidity, or momentum. The bulk of this article is addressed to this problem. Some comments are also made about the use of electric fields in conjunction with magnetic fields. The inclusion of electric fields allows the separation of a beam of known momentum into its various components according to the velocities of the particles, hence according to the masses of the particles. These are referred to as ''separated beams''.
Date: May 1, 1960
Creator: Chamberlain, Owen
System: The UNT Digital Library
PDQ-3--A PROGRAM FOR THE SOLUTION OF THE NEUTRON-DUFFUSION EQUATIONS IN TWO DIMENSIONS ON THE IBM-704 (open access)

PDQ-3--A PROGRAM FOR THE SOLUTION OF THE NEUTRON-DUFFUSION EQUATIONS IN TWO DIMENSIONS ON THE IBM-704

None
Date: May 1, 1960
Creator: Cadwell, W.R.
System: The UNT Digital Library
The Penetration of Radiation With Constant Driving Temperature (open access)

The Penetration of Radiation With Constant Driving Temperature

Exact and approximate solutions for the penetration of radiation with constant driving temperature are presented. (auth)
Date: May 1, 1960
Creator: Petschek, A.G.; Williamson, R.E. & Wooten, J.K. Jr.
System: The UNT Digital Library
Piqua Prototype Handling System (open access)

Piqua Prototype Handling System

Abstract: Equipment has been developed to handle the fuel elements and control rods for the Piqua (OMR) reactor.With the handling machine, which consists of a shielded cask mounted on a gantry, a fuel element can be replaced in the core in about 27 minutes.
Date: May 1960
Creator: Nadler, H.
System: The UNT Digital Library
Plutonium: Enriched OMR Cores (open access)

Plutonium: Enriched OMR Cores

Abstract: The influence of plutonium on the nuclear characteristics of organic moderated cores is studied.
Date: May 1, 1960
Creator: Connolly, T. J.
System: The UNT Digital Library
Preliminary Operational Safety Report for the Task 5.6 Thermoelectric Generator (open access)

Preliminary Operational Safety Report for the Task 5.6 Thermoelectric Generator

The operational hazards associated with the use of a plutonium-fueled thermoelectric generator in a terrestrial satellite are evaluated. It appears that the plutonium fuel can be consumed and dispersed at high altitude during reentry, following a successful mission. As an alternative, however, since the fuel (Pu/sup 238/) is an alpha emitter with a long half life, it appears that random intant recntry following a suceessful mission is feasible. As a precaution against aborted missions, the launch azimuth should be over water as much as possible to avoid impact or dispersion in areas of signifieant population density. It is recommended that the fuel and generators be transported by air carrier to preclude local restrictions of ground transport and to provide better statistical safety. The transport phase poses a very minor safety problem. (auth)
Date: May 1, 1960
Creator: Knighton, D.
System: The UNT Digital Library
PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING APRIL, I960 (open access)

PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING APRIL, I960

None
Date: May 1, 1960
Creator: Dayton, Russell W. & Tipton, Jr, Clyde R.
System: The UNT Digital Library
Project Hobo : Shear and Compressional Velocity Measurements (open access)

Project Hobo : Shear and Compressional Velocity Measurements

Abstract. Three groups of 100 foot holes were drilled vertically downward from the floor of U 12e main tunnel and U 123.03 drift at the Nevada Test Site. Distances between holes in each group varied from 13 to 375 feet. One hole in each group was used a a 'shot hole'; the others for seismometers to records the energy generated in the 'shot hole'. Two types of recordings were made. One for dilatational or longitudinal "P" waves and one for transverse or shear "S" waves. Simultaneous recordings were made on photographic paper and on magnetic belts with a minimum of three "specimen" records at each hole, for each type of recording. The magnetic belts were transcribed to 1/2 inch IRIG tape for computer use. Rock density measurements were also made in the holes. From these data Poisson's Ratio, Bulk Modulus, Rigidity Modulus, and Young's Modulus were computed. Elastic constant values obtained 'in sltu' are much higher than those determined by soils laboratory tests on small rock samples. The data obtained are considered to be of exceptionally high accuracy.
Date: May 1960
Creator: Swain, R. J.; Heald, C. L. & Snodgrass, D. T.
System: The UNT Digital Library
QUANTITATIVE CORRELATION OF IRRADIATION GROWTH WITH PREFERRED ORIENTATION IN URANIUM (open access)

QUANTITATIVE CORRELATION OF IRRADIATION GROWTH WITH PREFERRED ORIENTATION IN URANIUM

A review is presented of the methods developed at the Savansah River Laboratory and elsewhere for quantitative correlation of irradiation growth with preferred orientation inuranium, with preferred orientation characterized by x- nay and dilatometric techniques. In an application of the methods, it is shown that a strongly oriented uranium plate, clud in aluminum, was much more stable in dimen- . sions than would be expected from the observed dimensional behavior of either unrestrained single crystals of uranium or aluruinum-clad polycrystalline rod. The greater stability of the plate is attributed to a relatively strong claiding and other restraing effects. (auth)
Date: May 1, 1960
Creator: McDonell, W.R.
System: The UNT Digital Library
Radium and Mesothorium Poisoning and Dosimetry and Instrumentation Techniques in Applied Radioactivity (open access)

Radium and Mesothorium Poisoning and Dosimetry and Instrumentation Techniques in Applied Radioactivity

"The study of the toxicity of Ra and MsTh(Ra/sup 228/) in humans was continued. Several Thorotrast cases were also examined. Physical and clinical studies were made on 151 persons. In all cases possible gamma ray measurements were made of Ra and MsTh decay products retained in the body, alpha -ray measurements of Rn and Rn/sup 220/ in breath, a complete medical history was taken, a complete x-ray examination was made of the skeleton, and urinalysis, hematological, and blood chemistry studies were made."
Date: May 1960
Creator: Evans, Robley D.
System: The UNT Digital Library
Rasium and Mesothorium Poisioning and Dosimetry and Instrumentation Techniques in Applied Radioactivity. Annual Progress Report (open access)

Rasium and Mesothorium Poisioning and Dosimetry and Instrumentation Techniques in Applied Radioactivity. Annual Progress Report

The study of the toxicity of Ra and MsTh(Ra/sup 228/) in humans was continued. Several Thorotrast cases were also examined. Physical and clinical studies were made on 151 persons. In all cases possible gamma ray measurements were made of Ra and MsTh decay products retained in the body, alpha -ray measurements of Rn and Rn/sup 220/ in breath, a complete medical history was taken, a complete x-ray examination was made of the skeleton, and urinalysis, hematological, and blood chemistry studies were made. Medical data are appended. An extensive intercomparison of Ra burden measurements on living subjects was carried out between M.I.T. and ANL. Results are tabulated. Complete measurements were made of tooth and bone MsTh/Ra ratios on 24 individuals. Comparison of results with data on Ra/Ca ratios of teeth and total skeleton and with data from whole-body measurements on the same individuals led to the conclusion that estimates of total skeleton Ra burden can be made with reasonable accurateness on the basis of data obtained from Ra gamma -counting a single tooth. Data are being recorded on punched cards for correlation with the incidence of various affects such as tumors, bone fractures, age at exposure, age at occurrence of effects, …
Date: May 1, 1960
Creator: unknown
System: The UNT Digital Library
Relativistic and Diamagnetic Corrections of Atomic g Values (open access)

Relativistic and Diamagnetic Corrections of Atomic g Values

None
Date: May 1, 1960
Creator: Lindgren, I. P .K.
System: The UNT Digital Library
REMOVAL OF A RADIOACTIVE PRIMARY SODIUM PUMP OR A RADIOACTIVE PRIMARY COLD TRAP (open access)

REMOVAL OF A RADIOACTIVE PRIMARY SODIUM PUMP OR A RADIOACTIVE PRIMARY COLD TRAP

Methods and procedures are described for removing a radioactive primary sodium pump or a primary cold trap with handling casks from the Hallam Reactor. (D.L.C.)
Date: May 1, 1960
Creator: Mallon, P.J.
System: The UNT Digital Library
Scale "Up or Down" Analysis for Prototype Test (open access)

Scale "Up or Down" Analysis for Prototype Test

Introduction: In conjunction with the final design and development of a 70 MW sodium intermediate heat exchanger and a sodium steam generator, an analysis is required which can be used as a basis for a determination to scale up or scale down the designs. Included in this analysis are those considerations leading to the recommendation of the best prototype test unit and to some of the limits imposed on scaling up or down when considering future applications of designs other than those actually tested. In addition, these considerations include aspects required to accurately predict the performance, operation, mechanical reliability, and feasibility of fabrication of the 70 MW design.
Date: May 1, 1960
Creator: Alco Products (Firm).
System: The UNT Digital Library
SERVOMECHANISMS WITH FORCE FEEDBACK (open access)

SERVOMECHANISMS WITH FORCE FEEDBACK

A class of linear proportional servomechanisms is examined in which an electrical signal proportional to output force is used to improve performance. The effect of this "force feedback" on a positional servomechanism is analyzed as well as the effect on a special type of servomechanism which reflects load forces back to the input. This latter type of servomechanism is called "force reflecting." Laboratory models of these servormechanisms were designed and constructed, and experimental data are presented in support of the analysis. (auth)
Date: May 1, 1960
Creator: Arzbaecher, R.C.
System: The UNT Digital Library
SL-1 ANNUAL OPERATING REPORT FOR FEBRUARY 1959-FEBRUARY 1960 (open access)

SL-1 ANNUAL OPERATING REPORT FOR FEBRUARY 1959-FEBRUARY 1960

The pericd from February, 1959, when CE assumed operative responsibility of the SL-1 Reactor Plant, to February, 1960 is covered. The operations of the year are summarized; the reactor, instrumentation, mechanical, electrical, and facility systems are evaluated; health and safety, and the operational costing program are discussed. (auth)
Date: May 1, 1960
Creator: Canfield, R. T.; Crudele, J. S.; Vallario, E. J.; Young, R. G. & Rausch, W. P.
System: The UNT Digital Library