This report address a brief summary of anticrime legislation enacted during the 89th ad 90th congress.

Report regarding the first year of work designing and constructing a portable reverse osmosis pilot plant for converting brackish water.

Report that "covers the field operation of a 36-in. diameter pressure-vessel-type reverse osmosis system over a seven month period and the post-operational inspection of the unit and associated hardware" - (p. 1).

From Introduction and Summary: "This report is essentially a continuation of Aerojet Report No. F1027-01-A, submitted to the Office of Saline Water in may 1967. These two reports present the results of the efforts under Contract No. DI 14-01-0001-930 and all amendments. * "

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.

Annual report with the objectives of evaluating, producing, and maintaining an up-to-date set of basic nuclear data; producing and evaluating multigroup constants; and improving of present day methods of neutronic calculations as related to microscopic and macroscopic nuclear data, for unclassified research sponsored by the U.S. Atomic Energy Commission during FY 1968.

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This report presents the details of the activities of Douglas United Nuclear at the Hanford site during the month of April 1969.

This document comprises a compilation of preliminary data generated during the reporting months of March, April, May, 1969. Data relate to fuel element development, cladding development, fuel quality assurance, fuels evaluation, and offsite fuel programs.

This document comprises a compilation of preliminary data generated during the reporting month of May, 1969. The data relate to fuel element development, fuels quality assurance, cladding development, fuels evaluation, and offsite fuel programs.

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Quarterly report with the objectives of evaluating, producing, and maintaining of an up-to-dat set of basic nuclear data; producing and evaluating of multigroup constants; and the improvement of present day methods of neutronic calculations as relates to microscopic and macroscopic nuclear data, for unclassified research sponsored by the U.S. Atomic Energy Commission during FY 1968.

The following activities were conducted during the month of April 1969: continued effort toward completion of the detailed design of the PMC-2 converter, conducted technical liaison with Westinghouse with respect to the power cable specification, conducted potting test for evaluation of material suitable for SNAP-23A converter PMC-2 leak specification, and completed design of parts for the Weld Development Program. Test data evaluation and analysis were performed on the following long-term test devices during February 1969: experimental mockup converter No. 2 (EMC-2), experimental mockup converter No. 3 (EMC-3), prototype mockup converter No. 1B (PMC-1B), 10-couple modules 1 and 3, 10-couple modules 5 through 12 on design-of-experiments tests, 6-couple module 23A3, and converter 23 P-2.

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