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This report presents the details of the activities of Douglas United Nuclear at the Hanford site during the month of August 1970.

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>One of the objectives of the Waste Management Program is to separate the long-lived heat emitter /aup 137/Cs from the bulk of the high-level Iiquid wastes. This separation is accomplished by the ion exchange process in the 221-B Building. Interim storage of the cesium is in solution as a nitrate. The feed for the B Plant cesinm ion exchange process is pumped from the lag storage tank, 105-C, through a pipeline and several diversion boxes to the 221-B Building. On December 19, 1969, a leak was discovered near the 241-C-152 diversion box in the section of this line, V-122, from the 105-C tank. Although the leak represented a loss of feed for the processing of /sup 137/Cs, more important was the consequence of environmental contmination to the soil from the line leak. For this reason, an investigation was made to estblish the extent of the radioactivity spread. The results of a well drilling operation undertaken to define the boundary and to estimate the extent of the leak are summarized. (CR)

This report is addressed to the radioactive effluent control program of (AEC) facilities operated by Douglas United Nuclear, Inc. It was prepared in response to an inquiry from Atomic Energy Commision AEC Division of Operational Safety via AEC-RL regarding quantities of radionuclides released. The current status, measurement, and activity of the program are described. In addition, other related efforts which have been deferred due to lack of funding are highlighted.

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The effects of SCB coating, thermal shock and hermal scak on the dimensional stability of four heavy walled Incolcy 800 cladding tubes, ranging in thickness from 20 to 44 mils, was investigated. The results of the study were summarized in TI-759-240-029. This report serves as a repository for the detailed data and profilometer traces used in the preparation of that summary.

The Filter Attenuation Measurement System was designed by J.H. McCrary. It is, as its name implies, primarily intended to measure the attenuation of an x-ray beam by various substances. However, it can also be a very useful instrument for qualitative as well as quantitative analysis through the use of absorption edge spectrometry. The essential components of the system are depicted. The brehmstrahlung originating in a tungsten target x-ray tube is collimated and the desired energy picked out by varying the angle that the primary beam makes with the (200) set of planes in a LiF crystal. The reflected beam, which is monochromatic, passes through two collimators before being detected by a NaI counter. The sample whose transmissivity is being measured is placed between the second and third collimators.

Acoustic emission monitoring augments other nondestructive testing methods and is sometimes applicable when other tests cannot be applied. This is, in part, due to the high sensitivity of acoustic emission monitoring. Acoustic emission monitoring is only sensitive to active flaw-growth, however, and will not detect a flaw in equilibrium. This paper describes the application of acoustic emission monitoring to nuclear reactor fuel pin end closure welds and other weldments of the reactor piping.

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This report includes the several additonal system transients that are calculated for 5 kWe thermoelectric system.

It was demonstrated that the modified version of the Martin flowsheet can produce SrF/sub 2/ of acceptable quality using a simulated feed of the same composition as the anticipated packaging plant feed. By careful control of operating conditions, strontium losses in the process can be reduced to an acceptable level. Using a nonrepresentative radioactive feed (which contained impurities not present in the simulated feed) high strontium losses were encountered in the feed purification step, although the purification obtained was excellent. The other steps in the process presented no difficulties. Additional tests of the feed purification step will be necessary when a representative feed is available to ensure that strontium losses can be reduced to an acceptable level. The proposed flowsheet differs from the Martin flowsheet in that a feed purification step is used in the proposed process. All the remaining steps in the process are essentially identical and the data and recommendations reported in the Martin publications appear applicable to the proposed process. Based on the results of this study (and including data published by the Martin Company), a detailed flowsheet with recommended operating conditions is given.

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