On August 21, 1948, several smear samples of contamination from the inner rod room at 100-F Area were submitted for beta identification. This contamination was spread as a result of maintenance work on the horizontal rods. Urine sample were deemed advisable for two men who had been exposed while working on the rods. These urine samples were also submitted for beta analyses. The analyses of the smears showed the contamination to consist of primarily S{sup 35} (65%) and Fe{sup 59} (30%)and minor amounts of Ca (5%) and C{sup 14} (3%). No significant amount of radio iron or sulfur was found in either the feces or urine samples.

In the course of some kinetic studies on photosynthesis of barley seedlings, it has been found that plants utilize C{sup 12}O{sub 2} faster than C{sup 14}O{sub 2}. The plants were placed in a closed system containing an infra-red absorption-cell for the analysis of total CO{sub 2} and an ionization chamber for the determination of C{sup 14}O{sub 2} in the gas phase, both instruments recording continuously. Carbon dioxide, containing about 2% C{sup 14}O{sub 2}, was introduced in the dark and the specific activity at this point taken as unity. After a short dark period, the lights were turned on and photosynthesis was allowed to take place. A figure shows the result of a typical experiment. During the initial dark period the specific activity fell because of dilution by inactive respired CO{sub 2}. However, as photosynthesis proceeded, the specific activity of the residual CO{sub 2} rose until, when only 1/6 of it remained, the specific activity reached a peak some 20% higher than it had been at the start of photosynthesis. At this point the steady respiratory dilution became an appreciable fraction of the total remaining CO{sub 2}, and the specific activity dropped rapidly.

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The purpose of this document is to present in graphical form a current picture of the quality of the Hanford plutonium product.

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This report lists some physical properties data of aqueous homogenous reactor materials.

Experimental investigations were undertaken at Columbia University to determine the heat transfer and fluid flow characteristics of fuel elements for the Savannah River reactors. Primarily the tests simulated quatrefoil operation, but a number of tests directly applicable to the operation of extended surface fuel elements were performed. Data books were published in which the experimental data are tabulated.

The Geneva conference of experts stated that surface waves help define the nature of a seismic perturbation. A `phase equalization` method has been proposed by several seismologists to determine the polarity of the source using crustal surface waves. In this report a horizontal source array is designed which will reduce the amplitude of the crustal surface waves by a factor of five. Experimental data from Geophysical Prospecting is cited to support the effectiveness of such arrays. It is thought that phase shifts will accompany this amplitude reduction. It is concluded that these amplitude and phase changes will make the phase equalization method unreliable. The significance of the report is that the Geneva negotiations must take into account the possibility of horizontal as well as vertical arrays.

Purpose of this study was to determine the {sup 237}Np input to the Purex process. The {sup 237}Np content of 639 g Pu/ton U irradiated fuel was found to be 1.78 {plus_minus} .09 g/ton of uranium at the 95% confidence level. Standard recovery for the chemical method was 96.7%, 98.0% for the sampling.

Five eighteen-inch enriched tube-and tube-elements will be irradiated in the KER Loops in pH 10 water to an exposure of 3500 MWD/T, (to see if a pitting corrosion problem exists under NPR conditions).

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This report is the second in a series on the definition of performance of irradiated fuel elements as measured by the Quality Certification Program. Objectives of this analysis are to establish empirical mathematical relations which fit observed data from > 2000 fuel elements measurements for WARP, TFC, and DELTA OD{sub 2}, as a function of reactor conditions (power, surface temperature, time).

Three fuel element assemblies, each containing U-Mo fuel plates, will be irradiated in a side test hole at KE-Reactor. This document presents efforts made to determine the heat generation rate of the fuel plates from data from a capsule mockup irradiation in HTR.

The graphite stacks of the K reactors have been distorted to the extent that steel balls from the ball 3X system have entered some of the horizontal control rod channels and have interferred with the proper operation of the control system. One possible method of eliminating this potential hazard and attendant recurring production loss would be to place stationary sleeves around the horizontal control rods. Liners or sleeves in the vertical-ball and rod channels would prevent future leakage of balls into the moderator but would not eliminate the potential for balls already in the moderator to enter the horizontal control rod channels. For either horizontal or vertical liners it would be desirable to use an uncooled material which could withstand the reactor environment and which would not adversely affect the operation and production capacity of the reactor. The nuclear properties of five different materials have been reviewed to determine the maximum temperature which might be attained by each material when used as an uncooled sleeve, the effect each would have on the reactivity of the reactor, and the effect of each on the control capacity of the horizontal rod system. The five materials considered were: Inconel, a 300 series stainless …

The purpose of the report is to discuss the hydrogen flow experiment that was conduced in the Fluid Flow Laboratory.

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The Purex Processing Measurements Quality Control Program was designed to provide for orderly accumulation of measurements data suitable for statistical evaluation and to identify those elements of a measurement which, if improved, would result in significant reduction in overall measurement variation. This report gives an analysis of the audit data obtained at four transfer stations: L9 plutonium product loadout, K6 uranium product to storage, F15 salt waste to F16 and D5 dissolved feed to process. Estimates of variation caused by analytical, sampling and volume or weight instrumentation were computed and combined to give variation associated with a single batch transfer. Procedures for collection of future data that are more suitable for statistical evaluation are suggested. Methods used to compute random and fixed variation estimates are discussed.

This report puts under one cover numerous data which have been used and are used in health physics considerations of plutonium and americium.

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Demands for cobalt-60 have been relatively small as long as the principal applications were for radiography and gaging. The accumulated production in the entire United States is less than ten megacuries, although the Hanford plant is capable of producing about 150 megacuries every year using uranium enriched to 0.95 percent, and greater amounts with higher enrichments. The new developments brighten the prospects for large-scale utilization of cobalt-60. First is the possible us of cobalt-60 as a heat-producing radioisotope. Although shielding weights make cobalt-60 unattractive for space applications, the general size of thermal applications can be appreciated by noting that 32 megacuries of cobalt-60 would be required to provide the 500 kw of isotope heat which NASA reports they will need by 1980; terrestrial applications may be an order of magnitude larger. This application of cobalt-60 has been promoted primarily by Savannah River and utilization of high activity cobalt-60 (200-500 curies/gram) as a heat source is being investigated by them under MFC 5.

Efforts were concentrated on plant operating modes. The Heber plant, which was previously designed for consistant brine temperature, was reviewed and changes necessary to accomodate declining brine temperature were determined. Resultant required modifications to the computer code GEOTHM were made. The engineering, in terms of sketches and equipment lists, needed to support the capital cost estimate was determined. Attempts to use the computer program GEOTHM to develop the heat and mass balances for plants with declining geothermal fluid temperature disclosed that this code alone cannot be used for this purpose because it does not include turbine stage pressure-drop equations. It was determined that the most expedient method for obtaining the data needed for this study would be to develop a separate small computer program containing these turbine equations. With the assistance of a turbine consultant, the detailed methodology for the program was developed, and coding was started. (MHR)

KOVEC is a one-dimensional, Lagrangian, elastic--plastic material motion code that is available for both 7600 and STAR computers. The elastic--plastic formulation is in the principal stress coordinate system; the von Mises yield condition is used. Models for work hardening and temperature- and pressure-dependent yield strength and shear modulus are available. The hydrodynamic equations of state are analytic functions of relative volume and total internal energy. The coding allows an unlimited number of voids to open and close. The present document describes both the physics models and the user features of the KOVEC code. 3 figures, 5 tables.

Because there is no limit to the energy or power that can be delivered by a neutral-beam injector, its use will be restricted by either its cost, size, or reliability. Studies show that these factors can be improved by the injector design, and several examples, taken from mirror reactor studies, are given.

A discussion is given of a figure of merit indicative of the stability of high intensity beam transport systems. A table is provided giving this quantity under various conditions, and the limits for solenoidal focusing systems are obtained. (PMA)