Equations based on kinetic theory relate the contamination of refractory metals in vacuum to the appropriate variables. Several examples are given for which the allowable system pressures are calculated. The examples illustrate the effect of varying several parameters. The importance of the sticking factor for active gases on hot refractory metals and its effect on the system design are discussed. The data for estimating the sticking factor for O/sub 2/ on Nb are given, along with some estimated values. Experimental data on the composition and rates of outgassing of ultrahigh-vacuum systems and their importance in system design are discussed. Several methods of reducing contamination rates and the relative ease and effectiveness of these methods are presented. It was concluded that tests of 1000 hr or longer will probably require system pressures of between 10/sup -9/ and 10/sup -6/ torr, the particular pressure depending upon the residual gas composition, test duration, allowable contamination level, and the other variables discussed. Since the most important source of contamination in a properly designed ultrahigh-vacuum system is the outgassing process, bakeable systems should be designed to operate with walls as cool as practical, and to have a minimum of surface area and outgassing materials inside. …

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It is the purpose of this document to provide assistance to the Manufacturing Section personnel in determining their future operating plans. In general, the inter-relationship of such engineering parameters as projected flow rates, reactor orificing pattern, fuel element performance, and process limits have been considered. Based on these engineering parameters and related process economics, suggested reactor ``Operating Plans`` are graphically presented in this document. It is emphasized that these plans do not reflect operational considerations which may modify the desirability of the indicated power level increase nor has allowance been made for major projects, major maintenance outages, etc. Many factors which only manufacturing personnel are capable of evaluating may make it desirable to operate above or below these operating plants. These plans are designed to present reasonably achievable but perhaps optimistic power levels together with process limits which will be approached or will possibly limit reactor power levels unless limit revisions can be effected. It should be noted that the engineering parameters and basic assumptions which have been factored into these plans are subject to continual re-evaluation and revision. In a strict sense, these plans are out-dated even as they are published. However, their value will lie primarily in illustrating …

This Cost Improvement Proposal recommends an increase in the length of enriched fuel elements (for H Reactor only) from 6.64 in. to 8.1 in. A cost improvement would result as follows: Annual Out-of-Pocket Cost Savings, $121,000; Annual Outage Time Savings -- 65 Hours, worth 4,550 MD and Annual Production Level Gain -- 7,000 MWD. Since the Production Fuels Section and off-site suppliers are already equipped to handle elements of this length, the cost to make the change should be insignificant compared to the annual savings.

This report is divided into: metallic fuels technology, metallic fuel development, plutonium physical metallurgy, plutonium mechanical properties, and plutonium mechanical metallurgy.

Fabrication studies to produce high density solid solutions of 80% UC-- 20% RaC, with reproducible structure, composition, and density, were completed. Two types of material were produced: (U/sub 0.8/Pu/0.2/)C/sub 0.95/, single-phase monocarbide pellets with average densities of 12.8 g/cm/sup 3/ (94% of theoretical), sintered at 1950 deg C; and (U/sub 0.8/Pu/0.2/) C/sub 0.95/ + 0.1 wt% Ni sintering aid, major monocarbide and minor amount of sesquicarbide pellets, with average densities of 13.1 g/cm/sup 3/ (96.5% of theoretical) sintered at 1550 deg C. Bar-shaped thermal expansion specimens were fabricated of UC, prior to fabrication of similar (U,Pu)C specimens. UC pellets were fabricated for electropolishing and liquid-metal bonding studies. Chemical analysis procedures were established, and checked, for plutonium, nitrogen, and oxygen. Chemical analysis procedures for carbon are being estsblished. The experimental setups for the measurement of coefficient of thermal expansion, thernial stability, melting point, and fuel cladding compatibility were completed. Testing of thermal expandsion, vapor pressure, and melting point standards was initiated. UCliquid metal-tantalum compatibility tests were completed, and (U,Pu)C-liquid metal-tantalum compatibility specimens were prepared. These tests are to help in choosing a liquid-metal bond for the thermal conductivity test. The pre-installation tests for the safe performance of the high temperature measurements …

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A time-to-height conversion system was developed which is useful for measuring time intervals from 10 psec to 200 mu sec. When driven by a mercury- relay pulse generator through appropriate fixed delays, the resolution of the system, FWHM, is 6 psec, the apparent time shift with temperature is less than 2 psec/ deg C, and the integral linearity is within plus or minus 1%. The apparent time distribution through a type 58 AVP photomultiplier tube driven by a mercury-relay pulser was less than 0.3 nsec at a fixed light level equivalent to 10/sup 3/ photoelectrons per pulse. The apparent time shift was less than 0.5 nsec for variations from 10/sup 2/ to 10/sup 4/ photoelectons per pulse. (auth)

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Declassified 29 Aug 1973. Critical experiments were performed with fuel elements for the Project Rover KIWI-B-2A reactor to determine nuclearly safe conditions for their production, storage, and transportation. Each element is a 0.746-in.-dia and 50.5-in.-long uranium carbidegraphite cylinder containing seven uniformly spaced longitudinal holes. The uranium concentration is 400 mg/cm/sup 3/, of which 93.15% is /sup 235/U, yielding a C: /sup 235/U atomic ratio of about 90. Throughout the experiments each element was encased in a sealed aluminum tube. In order to establish both the minimum critical number of watermoderated and -reflected elements and the relationship between moderation and critical number, several critical arrays covering a wide range of moderation were assembled. lt was found that the minimum critical number of 66 elements, containirg about 5 kg of /sup 235/U occurred at an H: /sup 235/U atomic ratio of 380. The critical number of unmoderated elements in a reflected array was greater than 2500. Experiments were also performed with uranium oxidegraphite elements from an early stage of production. The minimum critical number of full- length elements in a moderated and reflected array was 40, containing about 4.6 kg of /sup 235/U. The H: /sup 235/U atomic ratio was 270. Several …

A program (ZORCH) is described which is an extended and revised version of the point-model kinetics program MURGATROYD. A model is used in which the axial space dependence of the fuel and graphite temperatures is calculated, and the effect on reactivity of deviations from the steady state values is assumed to be given by the product of an appropriate temperature coefficient of reactivity times the deviations from the steady state value of the nuclear average temperature (NAT). The NAT is computed using a sine-squared'' weighting function in the axial direction and using an input weighting factor in the radial direction. The shape of the power density is taken to be - time- independent in contrast to the shapes of the temperature distributions, which are time-dependent in the calculation. This program is intended to be used in surveys of reactor behavior under a wide range of conditions. It is therefore based on a simplified model in order to reduce computing time, but should provide a better approximation to reactor behavior than does a purely space-independent calculation. A derivation of the equations used in the program, instructions for its use, and sample input and output for a test case are included. A …

This report is a bibliography of books, periodicals, Congressional hearings, and other government reports that focus on the issue of the government sharing its income tax revenue with state and local governments.

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A summary is presented of the broad field of graphite irradiation capsules. The various capsule designs are considered; they include temperature- controlled and temperature-monitored capsules. The components and materials of the capsules are described. Finally, methods are given for carrying out heat trandsfer calculations in capsule design and neutron spectra calculations for correlation of radiation data from different reactors. (D.L.C.)

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"The performance of the Model I electrostatic precipitator sampler in recent field and laboratory tests is described and discussed. Two of the four precipitator-bearing balloon flights during this interval reached the floating altitude of approximates 105,000 feet, and the precipitator operated efficiently on both. One sample was collected at the nominal design flowrate of approximates 100 cfm, and the second at approximates -200 cfm. Comparison of the deposition profiles of the stratospheric samples with those obtained under controlled conditions in the altitude chamber indicates that the field samples were collected with >90% efficiency. The laboratory tests also showed that the performance capability of the precipitator improves with increasing precipitator current, and with increasing altitude. One of the above balloon flights carried two Model A-I altimeters with recorder outputs. The two records were identical within plus or minus 250 feet. In addition, variations in altitude indications were consistent with the less sensitive aneroid barocoder measurements from the same flight. A revised Model A-I altimeter with a telemeterable output signal has been designed and constructed. The frequency of the signal is a function of the altitude. A preliminary design concept for a flowmeter with negligible flow resistance is described. It would utilize …

This document presents details about the activities of Douglas United Nuclear at the Hanford site during the month of August 1969.

This report presents details of the activities of Douglas United Nuclear at the Hanford site during the month of August 1967.

In the Hotcake experiments, PBX-9404 was subjected to various temperature spikes from 202 degrees Centigrade to 268 degrees Centigrade to determine conditions which would result in ignition of the explosive. since that time, measurements have been made of decomposition rates of PBX-9404, LX03, LX04, and pure HMX, at temperatures from about 240 degrees Centigrade to 270 degrees Centigrade. These data have been combined to provide a more accurate definition of the thermal stability of high explosives based on HMX. A set of values of decomposition rates and heats of decomposition has been obtained which is consistent with all previous Hotcake experiments, and will allow predictions of the results of similar experiments with PBX-9404, LX03, and LX04. Computations were made with the Hangfire program on the IBM 7090.