Summary. The analysis of the motion of a six-bar linkage is difficult because of the large number of variables involved and the large number of calculations that have to be made for each position of the linkage. If a digital computer is used to make the calculations required for a multi-position analysis of a mechanism, it is feasible to design by analyzing a large numbers of similar linkages and selecting the optimum configuration. In this paper expressions have been derived for the output angle as a function of the input angle and the transmission angle as a function of the input angle for any single-degree-of-freedom six-bar linkage for which the parameters are known An example showing the usefulness of a six-bar computer program as a mechanism design tool is discussed.

Report that briefly describes many of the models of crystal and molecular structures which have appeared in the literature, and presents a bibliography of the publications, grouped according to model types, which describe the models in more detail.

From Abstract: "The methods used at the National Bureau of Standards in calibrating line standards of length and measuring tapes submitted for standardization are outlined. The equipment used is described briefly. There is a discussion of some considerations that should be given as to whether or not a standard should be submitted to the Bureau."

Selective hydrocracking of total coolant was found to be an efficient and economic method for reconstitution of high boiler in the coolant to usable product. Such a process could eliminate the expense of vacuum distillation and disposal of high boilers produced in a nuclear reactor power plant. The selective conversion was possible since polyphenyls were found to be more susceptible towards hydrocracking as the phenyl chain length increased. Both cobalt molybdate on alumina and nickel oxide on alumina (50 to 80 square meters per gram) were found to be efficient catalysts at conditions of 900 deg F and 1000 psig with the latter giving more selective conversion to terphenyls. Continuous flow hydrocracking tests on OMRE Core II cool ant (containing 23% high boiler) resulted in 90 to 100% conversion of high boiler at product recoveries of 85 to 95 wt%. Average molecular weights of the products (biphenyl and heavier) were in the range 205 to 225 compared to 270 for Core II coolant. High boiler in Core III-A coolant which contained mainly first-generation polymers (hexaphenyls) was slightly more refractory toward hydrocracking than Core II high boiler, and conversion decreased slightly with increasing on-stream time. However, at optimum condition for processing …

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This report, from the Chemical Processing Department at HAPO for April 1966, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; and waste management.

Introduction: The chemical character of ground water depends to a large degree upon the character of the rock formations through which the water moves. The composition of the water is the result of several solutional and decompositional processes.

The detailed description includes flow measuring methods, flow rate calculations, operating pressure constants, crossheader number, header elevation corrections, and header pressures for the reactor record. The unit records include: tube number, header number, flow zone, trip dial readings, effective range, taps, corrosion index, rib type, rear fitting type, Panellit pressure, date, calculation methods, tube flow rate, tube class, load type, charge date, and header pressures. The reactor operating limits include: tube number and class, tube flow rate, Panellit pressure, boiling limits, base pressure, adjustment date, limit codes, load type, and flow factors.

To determine the present flow properties of the KE downcomer and the effect of small flow increases upon the downcomer pressure characteristics.

Reduction of the reactor process water pH from 6.9 to 6.6 at 100-B, D, DR, KF, and H currently is proposed in order to reduce the aluminum corrosion rate and the resultant outage time for water leaks, fuel ruptures, and process tube replacement. This document reviews the current knowledge of the effect of reducing the pH to 6.6 on aluminum corrosion. An estimate of the expected costs and benefits is included.

A series of three tests will be performed to evaluate: temperature gradients between wall and central coolant channels in an FFTF fuel assembly to assess thermal stress level in the pins. The potential hot spot caused by the presence of a wire wrap spacer. A single electrically-heated 7-pin fuel assembly model will be used to perform these tests. The configuration is summarized in Table 1 and the instrumentation in Figure 1. Pins 1, 2, and 7, along with the local coolant thermocouples, characterize the central and outer channels. Pins 4 and 6 provide data on the hot spot under the spacer, while pin 3 (along with pin 2) provides data on the gradient across an outer row pin.

Studies were initiated at Hanford in 1961 and 1962 toward the development of an alternate assembly process for the production of I&E fuel elements for the eight existing Hanford reactors. Of the processes considered, hot die sizing, a diffusion bonding process, offered the greatest incentives in terms of improved quality and potentially cheaper unit cost of fuel elements compared to the currently used AlSi braze process. This interim report presents the results of initial process variables tests designed to establish optimum process parameters for producing good diffusion bonds on the lateral external and internal surfaces of I&E fuel elements during the sizing step of the hot die size process. In a subsequent step, the end bonds are formed. Optimization studies for producing good end bonds will be reported in future interim reports.

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The mechanism of reduction for chromium(III) ion to chromium(II) at the mercury cathode was studied in 0.1M KNO/sub 3/. Data obtained at varying temperature and solution composition from polarograms gave values for DELTA H*, DELTA S*, and DELTA F* which indicated that two mechanisms were involved. At potentials more positive than the polarographic half-wave potential, the mechanism appeared to be simple electron transfer from the electrode to the chromium(III) ion in solution. When the potential was more negative than the half-wave, potential electron exchange between the reduced chromium ion near the electrode surface and a chromium(III) ion in solution became appreciable. Values for the heat of activation for the reduction of chromium(III) to chromium(II) in 0.1M KNO/sub 3/ for the electron transfer and exchange reaction mechanisms were determined to be 34.7 and 27.0 kcal mole/sup -1/, respectively. (auth)

From Abstract: "Sources of error in measuring pressures are described in considerable detail, particularly for portable instruments including scale, temperature , gravity, capillarity, vacuum errors and return gas column. Methods of minimizing those errors and of making the corrections, including extensive tables, are presented."

This report consists of list of the military-industrial complex.

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This report is applicable to the eight operating production reactors, B, C, D, DR, F, H, KE, and KW. It covers the following: operating parameter limitations; reactivity limitations; control and safety systems; reactor fuel loading; coolant requirements with irradiated fuel in reactor; reactor confinement; test facilities; code compliance; safety instrumentation and set points; and control criteria. Also discussed are administrative procedures for process control, training, audits and inspection, and reports and records.

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This production test is designed to demonstrate that the K Reactors can be operated. with a higher graphite temperature limit than stipulated in present standards without a significant increase in the rate of either burnout or contraction of the graphite moderator stack. It is intended that the increase in allowable maximum graphite temperature will be utilized to permit operation with slightly higher reactor power levels with substantially the same enrichment level of the total uranium fuel charge as is currently in practice at the K Reactors.

Half-plant production tests have been used for many years to evaluate changes in water treatment processes. Since some conjecture existed regarding the validity of this test concept, it was decided to employ a tracer element. Bromine was chosen as the tracer element due to its absence in raw water, the short half life of its radionuclides, and its compatibility as a potable water treatment chemical. The parent production test was run for four days, but the scatter in the data indicated equilibrium had not been reached and conclusions could not be made. The test supplement was run for a period of 12 days. This report provides the test data which shows that an average cross flow of 7.6% is experienced, as measured in the reactor rear riser, when a reasonably balanced pumping system is maintained. Operating experiences at D and F Reactors during the early part of 1965 further confirm these facts. Excessive film build-up occurred in both instances on plant halves. A distinct demarkation line was experienced between vertical rows 73 and 74, as measured by front face Panellit pressure increases.

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Hot die sizing is one of three solid state diffusion bonding (SSDB) processes that has been proposed as an alternate manufacturing process for fabricating HAPO metallic uranium, aluminum-clad fuel elements. This document establishes the provisional process specifications for the assembly of fuel elements by the hot die sizing process. These specifications were developed for the CDB2N model fuel element (CSN equivalent AlSi model) and do not necessarily apply to any other model.