Search Results

open access

PREPARATION AND FABRICATION OF PLUTONIUM FUEL ALLOY FOR LOS ALAMOS MOLTEN PLUTONIUM REACTOR EXPERIMENT NO. 1

Description: Tantalum-sheathed plutonium fuel pins were prepared for the first core loading of the Los Alamos Molten Plutonium Reactor Experiment-I. Plutonium--10 at.% iron alloy was prepared by co-reduction and by co-melting methods. After casting the alloy into rods, each rod was machined and finished to a 0.357-in.- diameter piece weighing 175 g. The finished alloy rod was finally placed in a tantalum sheath, then sealed by fusion welding to a tantalum cap. Procedures and equipment used for alloying, casting, machining, welding, and inspection are described. Methods used to prepare rods of other low-melting plutonium alloys also are discussed. (auth)
Date: April 15, 1960
Creator: Anderson, J.W.; McNeese, W.D. & Leary, J.A.
Partner: UNT Libraries Government Documents Department
open access

FUEL BURNUP STUDIES FOR A 225 Mwe ADVANCED SODIUM GRAPHITE REACTOR

Description: Reactivity and fuel burnup studies were performed for a 255 Mw(e) sodium- graphite reactor of the advanced calandria core type. This reactor is briefly described. Initial criticality calculations and flux distributions were obtained, using two-group theory for enrichments between 2.0 at.% U/sup 325/ and 4.0 at.% U235. A four-group burnup study was performed for enrichments between 2.5 at.% Uisup nd 3.25 at.% U/sup 235/. Core lifetime, changes in isotopic fuel composition, variations in radial power distribution, and fuel cross sec tions are presented. Reactivity during core lifetime was assumed to be controlled by the presence of a homogeneous poison which simulated the effects of control rcds. The results presentad are useful in determining initial enrichment selection in fuel programming and fuel cost studies. (auth)
Date: June 15, 1960
Creator: Aronson, A. L.
Partner: UNT Libraries Government Documents Department
open access

A LINEAR INDUCTION PUMP FOR LIQUID METALS

Description: A linear induction pump of a special design was used to circulate molten sodium through a mockup of an experimental "overflow" type of sodium-cooled reactor. The distinctive features of this pump are that no seals or moving parts are required: no piping is required to carry sodium to the pump or away from it because the pump is mounted directly on the reactor vessel, with the windings outside of the vessel and the magnetic flux return path inside the vessel. The pump develops 342 gpm at 6.2 psi when pumping sodium at 600 deg F with an efficiency of 4.7%. (auth)
Date: January 15, 1960
Creator: Baker, R.S.
Partner: UNT Libraries Government Documents Department
open access

SELECTION OF THE PIQUA OMR FUEL ELEMENT

Description: Two types of aluminum-clad uranium alloy fuel elements, a square (parallel flat plate) and a circular (concentric cylindrical shell) were investigated to determine their relative suitability for use in the Piqua Reactor. Nuclear, thermal, and mechanical data are given, and considerations leading to selection of the circular element are presented. Design dimensions are listed and reactor thermal design and operating conditions are given for the proposed element. (auth)
Date: March 15, 1960
Creator: Baumeister, E.B. & Wilde, J.D.
Partner: UNT Libraries Government Documents Department
open access

Hanford Laboratories Operation Monthly Activities Report: July 1960

Description: This document presents a summary of work and progress at the Hanford Engineer Works for July, 1969. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Services Departments have sections presenting their monthly statistics, work, progress, and summaries.
Date: August 15, 1960
Creator: Bennett, C. A.
Partner: UNT Libraries Government Documents Department
open access

Thermoelectric Materials. Final Report, January 28, 1959-July 28, 1960

Description: BS> A method for the measurement of thermal conductivities of electrically conducting materials at temperatures in excess of 1000 deg C with a high accuracy was devised. The spatial boron concentration gradient in boron- doped graphite to achieve maximum p-type thermoelectric output was established. The production of an n-type silicon carbide-graphite composit was studied. Theoretical studies produced a detailed picture of the effect of doping on the electronic properties of graphite. A method was developed for the preparation of rare earth nitrides in a good state of purity. Electrical studies of the materials produced showed that several of the compounds are semiconductors as had been predicted. (M.C.G.)
Date: August 15, 1960
Creator: Brechenridge, R. G.
Partner: UNT Libraries Government Documents Department
open access

Water plant modifications for increased production at B, C, D, DR, F, and H Reactors

Description: The purpose of this report is to define the extent of modifications necessary to increase capacities of the 100-B, C, D, DR, F, and H water plants for reactor flows of 90,000 95,000 105,000 and 115,000 GPM, and to provide supporting data for budget studies for increased production.
Date: April 15, 1960
Creator: Brinkman, L. B. & Corley, J. P.
Partner: UNT Libraries Government Documents Department
open access

Gamma activity of irradiated zircalloy samples

Description: Three small samples of zircalloy-2, obtained from a KER tube, were irradiated in the Quickie Facility in F Reactor for one, four, and nine months, respectively. Each sample weighed approximately two grams. One day after discharge from the reactor, the specific activity of each of the samples was essentially the same (about 150 mr/hr/gram at one foot in air). Attenuation measurements taken one day after discharge using lead plates yielded a ten-fold reduction in gamma intensity for each 0.95 inches of lead. This indicates that an enclosure for kilogram samples of zircalloy which have been irradiated for long periods of time at fluxes up to 10{sup 14} neutrons per square centimeter per second should have six inch thick lead walls or the equivalent for gamma shielding. Based on the effective gamma energy and the half-life for the first day, it appears that Zr-89 may be the predominant isotope initially. After a few days, the half-life become long and gamma spectrometer measurements indicate the gamma softens revealing that Zr-95 might become the predominant isotope. However, isotopes were not determined specifically; impurities, other isotopes, or combination of isotopes could yield the same results.
Date: June 15, 1960
Creator: Bunch, W. L.
Partner: UNT Libraries Government Documents Department
open access

Cap-spire pulsing

Description: The cap-spire pulsing technique of preheating the cap-spire portion of the fuel assembly does significantly improve the brazing of the cap-spire assembly. The air pocket at the spire wafer junction is fully removed. The cap side wafer is essentially 100% wetted with brazing alloy. Destructive tests show that a 4 to 1 improvement in most quality measurements is achieved over present cap preheating techniques, without using additional cleaning step of spire etching. The pulsing is accomplished by a cammed drive system, using a stroke of three-fourths of an inch with a spring return. The system is driven by an electrical gear reduction motor at a rate of 1.4 pulses per second. A preheating cycle of 21 {plus_minus} 2 seconds is used for the current I&E cap designs. The cap-spire assembly does not require any special treatment other than the normal chemical cleaning.
Date: June 15, 1960
Creator: Burgess, C. A.
Partner: UNT Libraries Government Documents Department
open access

Magnetic Recorder for Nuclear Pulse Application : Covering the Period from February 6, 1960 to April 5, 1960

Description: Abstract: "The accuracies which can be achieved in analog recording systems are for the most part tape limited. While reasonable variations in tape speed do not directly affect the accuracy, such variations result in improper tape tensioning, which in turn results in poor head-to-tape contact. The quality of the tape transport mechanism should be such that the error introduced by improper head- to tape contact is less than tape errors. Some additional equipment is necessary in setting up a tape recorder for a given experiment. The amplitude of the input pulse spectura to the recorder should be adjusted for optimum value and, if possible, the counting rate should be adjusted to obtain good tape utilization. An oscilloscope is probably adequate to satisfy both conditions."
Date: April 15, 1960
Creator: Burgwald, G. M.
Partner: UNT Libraries Government Documents Department
open access

MAGNETIC RECORDER FOR NUCLEAR PULSE APPLICATION. Period covered: February 6 to April 5, 1960

Description: The accuracies which can be achieved in analog recording systems are for the most part tape limited. While reasonable variations in tape speed do not directly affect the accuracy, such variaticns result in improper tape tensioning, which in turn results in poor head-to-tape contact. The quality of the tape transport mechanism should be such that the error introduced by improper head- totape contact is less than tape errors. Some additional equipment is necessary in setting up a tape recorder for a given experiment. The amplitude of the input pulse spectrura to the recorder should be adjusted for optimum value and, if possible, the counting rate should be adjusted to obtain good tape utilization. An oscilloscope is probably adequate to satisfy both conditions. (auth)
Date: April 15, 1960
Creator: Burgwald, G.M. & Norton, R.M.
Partner: UNT Libraries Government Documents Department
open access

In-reactor rupture testing of Zircaloy-2 clad seven-rod cluster fuel elements

Description: Three tests have been run in the ETR in high temperature, high pressure, recirculating water. In one test, previously unirradiated fuel elements were used and in the other two the fuel was irradiated to 2400 MWD/T at HAPO prior to insertion in the ETR. Failure was initiated by shearing off a projection on the surface of one rod of a fuel element, thus opening a 25-mil hole through the cladding. The projection was sheared off by a hydraulically operated chisel controlled from outside the reactor. The first test was operated seven hours after the defect was opened with no failure. Failure is defined as having occurred when sufficient uranium oxide has formed to split open the cladding and release large amounts of fission products into the loop water. The second test was operated for fourteen hours after the defect was opened with again no failure. The third test was operated for only 33 minutes after the defect cap was sheared off before fission product activity in the loop water caused the test to be terminated.
Date: April 15, 1960
Creator: Call, R. L. & Kaulitz, D. C.
Partner: UNT Libraries Government Documents Department
open access

An appraisal of the Hanford high-level waste program

Description: As set forth in the CPD Waste Management Program (HW-63958), new and improved methods of waste processing are planned to be initiated at Hanford. A major part of this program is concerned with the high-level wastes from the Purex Plant, with major objectives being the control of long-term hazards, the insurance of production continuity, and the attainment of positive waste accountability at reasonable over-all costs. Specific plans for the disposal of Purex wastes are based on the use of high temperature calcination for immobilization and volume reduction of the solvent extraction raffinates (1WW). Four major steps are involved, each of which is of basic importance to the program objectives. These are: (1) interim 1WW storage and removal for calcination, (2) calcination, (3) primary containment of the calcined waste, and (4) long-term storage. Immobilization of coating wastes and organic wash wastes is also planned, either by tank solidification methods or possibly by inclusion in the calcination feed stream. This document was dated September 15, 1960.
Date: September 15, 1960
Creator: Campbell, B. F.
Partner: UNT Libraries Government Documents Department
open access

NUCLEAR CHARACTERISTICS OF BeO-MODERATED CORES VS. GRAPHITE-MODERATED CORES

Description: Multigroup calculations were performed to compare BeO-moderated cores with graphite-moderated cores, using various void fractions and core diameters. The core leakages and conversion ratios which were calculated are presented in a series of curves. (auth)
Date: January 15, 1960
Creator: Carlsmith, R.S.
Partner: UNT Libraries Government Documents Department
open access

An IBM-704 Code for a Harmonics Method Applied to Two-Region Spherical Reactors

Description: An IBM-704 computer code for the harmonics method of criticality calculation for two-region spherical reactors is described. In the harmonics method, the criticality condition corresponds to the vanishing of a certain infiniteorder determinant; in practice, this condition is replaced by equating a finite-order approximating determinant to zero. By hand, the calculations can be performed conveniently only for second-order approximating determinants. The approximating determinant with the described code is customarily of the seventh order. Losses of significant figures prevented the use of larger determinants. The machine running time per case is generally about 30 sec. (auth)
Date: March 15, 1960
Creator: Chalkley, R.; Nestor, C. W. Jr. & Tobias, M. L.
Partner: UNT Libraries Government Documents Department
open access

Maximum Volume-to-Stress Ratio for a Two-Radii-Contour Diaphragm Pump

Description: Analytical methods were employed to determine the maximum volume-to- stress ratio for a two-radii-contour diaphragm pump. A proposed failure criterion considers the effect of biaxial stresses on fatigue failure through. the use of the Mises-Hencky criterion for fatigue failure. By use of the proposed criterion, it was determined that an optimunn ratio of the two radii does exist, its value being dependent on the ratio of diphragm thickness to diaphragm deflection. Values for the optimum ratio of the two radii (where the ratio of radii is defined as the radius of the central pcrtion of the diaphragm contour divided by the radius of the outer pontion of the diaphragm) range from 1.94 to 7.33 as the ratio of diaphragm thickness to diaphragm deflection varies from 0.5 to 0.05, respectively. (auth)
Date: February 15, 1960
Creator: Cheverton, R. D.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen