The three main areas of effort have been: (1) definition of the general acoustic response pattern related to the gross aspects of forming and extending a crack in various materials, (2) development of a monitor system prototype concept exclusive of transducers and (3) development of a suitable, high temperature transducer. Tests using double cantilever beam (DCB) specimens of various materials to establish conditions of crack formation and growth have indicated that material ductility is a major controlling factor in the acoustic response pattern. It appears to effect both acoustic emission intensity and the point in the crack formation-growth sequence at which the main emission occurs. A concept has been developed for the prototype of a full scale monitor system. Hardware development is being limited to the analyzer portion of the system at this time because it is the part most significant to demonstrating feasibility of the intended application. Signal level and signal rate are both being investigated as possible parameters for evaluating acoustic emission data. Of the various transducers for potential high temperature application, the capacitive or electrostatic transducer now looks most promising. A significant improvement in sensitivity has been achieved and a trial model used during recent tests produced …

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EWR No. VTE-188--Tubes processed by flashing getters immediately prior to seal-off from vacuum systems are compared for total residual gas pressure to tubes processed by flashing getters after tubes were sealed off vacuum systems. Comparisons of residual pressures determined from current flows in the cold cathode ion gauge.

Declassified 4 Sep 1973. Information on the development of the 710 Reactor is presented concerning the performance testing of refractory-metal fuel elements, critical experiment mockup of 710 Reactor, reactor component design and development, and test facilities and pilot loop design. (DCC)

This report summarizes the technical progress on the subject contract for the period September 15 to November 14 1962.

A model is proposed which depicts the sources of elutriatable fines in the fluidized bed calcination process as being in two major groups, spray drying mechanisms and attrition mechanisms. Based on this model, equations are derived which express the rate of change of the concentration of a chemical tracer material in the elutriated fines, following introduction of the tracer into the feed and following its removal from the feed. This system has been simulated on an analog computer, and by matching the computer simulation to results from an actual calciner run, the rates of generation of fines by each of the two groups of mechanisms has been determined; the same technique results in an estimate of the amount of these fines remaining in the fluidized bed. Agreement between postulated results and results of actual experimental tests lends credence to the usefulness of this analytical technique. (auth)

Three E-N loaded tubes were dissolved, sampled and analyzed, starting November 9, 1960. The results of these analyses and an explanation of the methods used are the subject of this report. Each tube loading received an identification code in each facility in which it was processed. All of these codes are listed for future reference. Each batch of slugs was dissolved in a preflushed dissolver. When complete solution was indicated by a leveling off of the specific gravity, two 1 ml samples were taken and analyzed for uranium, specific gravity, and excess nitric acid. The dissolver charge was digested an additional four hours. At the end of the digestion period, two 1 ml samples and one 20 ml pig sample were taken. The three samples were analyzed for U, SpG, and HNO{sub 3}. Agreement between these samples and the previous samples was taken as confirmation of complete dissolution and representative sampling. If agreement was not obtained, sampling was continued. After verification of the pig sample, six 1 ml aliquots were taken for analysis by the Analytical Control group. The remainder was aliquoted to provide material for mass analysis and for analysis by the Process Chemistry group.

A free body diagram of the bellows will show the possibility of three forces -- one in each direction, three moments -- one in each plane, and the internal pressure. Any or all of these forces and moments may fluctuate due to variations in a driving force, e.g., separation of streamlines which creates slugging of flow through an elbow. Whereas the static equilibrium condition can be analyzed and stresses and strains computed, the dynamic condition cannot be approached without information on the magnitude, frequency and location of the exciting force. Having the latter, some evaluation of the stresses to be expected can be made. By combining strains (or stresses) due to the various forces and moments, the point of maximum stress can be located and the point of maximum stress fluctuation for the fatigue cycle-amplitude-range curve can be determined. Further consideration must be given to stress concentrations. With the complete analysis in mind, we must determine how some of these forces and moments effect the tests and delineate what can he expected from the tests. This report considers each force or moment by itself and studies its relationship to the tests.

This report details model studies performed as required by the design, development, and research contract between the General Electric Company and Washington State University. These studies provide analytical considerations for K-Downcomer and Bellows.

An investigatiori of the annealing of the radioinduced carrier concentration change in Sb-doped Ge in the range 370 to 455 l K was made. The irradiations were conducted at liquid nitrogen temperature using Co/ sup 60/ gamma irradiation. A model that explains the observed behavior is presented. On the basis of the model, the observed annealing consists of vacancy diffusion simultaneously to impurity sites and annihilation centers. Analysis of the activation energy for the annealing process yields values of 0.8 to 1.4 ev in agreement with the range of energies that were attributed to vacancy motion but that cannot be resolved into unique components. The complex activation energy is explained by the model in terms of the impurity concentration. It was observed that the change in carrier concentration saturates before complete annealing is achieved. The saturation, which is stable for further annealing at higher temperatures, is also explained in terms of the model. The vacancies are considered to diffuse to annihilation centers, such as dislocation lines, and to the site adjacent to an Sb atom. Those that go to an Sb are trapped. The Sb- vacancy complex can break up to supply a vacancy back to the system or can …

This report talks about Applications of static converters in power conditioning

A Third Party inspection of the reactor work platforms was conducted by representatives of the Travelers Insurance Company in 1958. An inspection report submitted by these representatives described hazardous conditions noted and presented a series of recommendations to improve the operational safety of the systems. Project CGI-960, ``C`` & ``D`` Work Platform Safety Improvements -- All Reactors, vas initiated to modify the platforms in compliance with the Third Party recommendations. The American Standard Safety Code for Elevators Dumbwaiters and Escalators (A-17.1) is used as a guide by the Third Party in formulating their recommendations. This code is used because there is no other applicable code for this type of equipment. While the work platforms do not and in some cases can not comply with this code because of operational use, every effort is made to comply with the intent of the code.

This report describes some present practices in regard to power calibration techniques and goes on to propose an automatic calibrator based on thermal power.

The horizontal control rods presently installed in the older Hanford Reactors have inadequate heat transfer characteristics for present and predicted future operation of the reactors. Continued graphite stack distortion, coupled with higher graphite temperatures, has resulted in ECR failure during reactor operation, such as swelling of the outer aluminum sheaths to the extent that rod movement in the graphite channel is severely restricted. Continued graphite stack distortion will tend to further aggravate the problem of rod operation. A new HCR design concept,was developed by P. H. Hutton of Reactor Design, IPD, to alleviate some of the pressing operational problems. Prior to the acceptance of such a design, the important rod operating parameters should be known to some degree of accuracy. This study was conducted to detexmine, by calculational methods, the temperature distributions that could be expected to occur in such an HCR when used at the present operating power levels and at 120% of the present power levels.

The purpose of this program is to conduct studies in the freshwater environment to acquire data needed to evaluate and predict the potential radiation hazards to human populations in the defined regions of proposed nuclear excavations in the Republics of Panama and Colombia. The results of the field surveys conducted in Phase II are presented in this report. Specifically, the data describes the elemental composition of the major components of the ecosystem, and reports the calculated stable element concentration factors for the major food organisms. This data provides baseline values from which predictions can be made of the potential maximum radionuclide intake by populations using this resource.

A description is given of bubble chambers in use and those in the design stages. Safety factors in the design and operation of a bubble chamber are discussed. Data are presented on fatige and rupture tests on glass. Data are contained on the effects of liquid helium on the tensile properties of various stainless steels. (C.J.G.)

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Approximately 15 minutes after shutdown on August 21, 1962, evidence of a rupture was observed in the form of high radiation levels in the containment vessel and rupture monitor indications. Discharge of a special MgO-PuO{sub 2} test element revealed a cladding break of about 1.5 inches in length and about 1/4 inch wide in the widest place, located 36 inches from the top of the fuel element as it would have been oriented in the reactor. A visual examination in Radiometallurgy revealed that approximately 9.25 inches of fuel material or about 0.55% of the entire fuel element had escaped. The quantity of fission products released from the rupture is presented, and the quantities and radiation levels from the individual fission product isotopes are calculated and presented.

A method of calibrating control drums in a subcritical assembly with a source is given here as an to WANL- TMI- 458 which discusses the measurement of shutdown reactivity in a subcritical core

Reproducibly high density UC-PuC pellets containing minor amounts of (U,Pu)/sub 2/C/sub 3/ were made with nickel sintering aid. Average densities of 95% and maximum densities of 96.6% of theoretical were obtained. High density, singlephase UC-PuC pellets were made by sintering at high temperatures. Densities of 94% of theoretical appear to be attainable. Improved identification of microstructural constituents was made by means of metallography, x-ray diffraction, and microprobe analysis. Development of specialized chemical analysis techniques continued. The post-irradiation examination of the UC specimens was completed. Mass spectrometer analysis showed that 0.4% of the fission gases was released. Metallographic examination of the UC did not reveal any channges in structure. Metallographic examination of the metal specimen parts that were in contact with UC was completed. No evidence for interaction with niobium and slight evidence for interaction with stainless steel was found. The latter was not deleterious. Perturbation factors were calculated for the UC- PuC experiments. Negotiations continued, in order to select the most suitable test reactor. (auth)

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Aqueous zirconium fuel processing studies, directed at adapting the hydrofluoric acid process to continuous dissolution-complexing in order to increase the capacity of the ICPP process, resulted in two successful approaches to the complexing-feed adjustment step. Continuous in-line adjustment (conversion of uranium(IV) to uranium(VI) necessary for extraction) was accomplished in one minute or less at approximately 90 deg C; surges of dissolver product from the operating dissolver up to 1.9 times the flow sheet rate did not inhibit the oxidation of the uranium at this temperature. Batchwise mixing in air of dissolver product solution with complexer solution oxidized the uranium within two minutes at 23 deg C or higher. Further studies of continuous zirconium dissolution indicated that precipitation of uranium at the acid inlet can be a problem, probably because of local concentration gradients of free HF, which result in conditions of low uranium solubility. Control of dissolver acid composition by electrical conductance measurement appeared possible due to the linear relationship of conductance with acid concentration. Aluminum alloy dissolution rates in nitric acid were found to vary significantly, depending on the type and amount of alloying agent. Silicon, nickel, and copper in the alloy significantly decreased the dissolution rate. Batch dissolution …