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Management of radioactive wastes at the Hanford site is presented. Radionuclide migration is also addressed.

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Differential equations and associated parameters are derived for heat transfer to a thin liquid-saturated wick, as in the evaporator section of a ''heat pipe.'' Prescribed are a numerical method of solution and a procedure for experimental measurements of heat transfer in the flat plate model. This effort is a part of the Project CLEER program which is currently sponsored by the Mechanical Engineering Department research account.

This report was prepared by Battelle-Northwest under Contract No. AT(45-1)-1830 for the Atomic Energy Commission, Division of Reactor Development and Technology, to summarize technical progress made in the Fast Flux Test Facility Program during May 1969 .

The storage capacity for irradiated fuels at the standby and abandoned basins is documented for the basins at B, C, D, DR, F, and H reactors. Tonnage is given for singly and doubly stacked buckets.

Battelle-Northwest is developing a general-purpose data retrieval system. The system is planned to provide almost unrestricted flexibility in application and use, with no limitations on the quantity of data, except those imposed by hardware. This data retrieval system is being programmed in Fortran-V, for batch processing on a Univac-1108. The control, search-and-retrieval, query-input, output, and startup programs have been written in preliminary form, and are in the initial debugging and test stages. Current versions of these programs are presented.

This proposal is submitted in response to Request for Proposal No. 438468, dated 27 May 1969, from the Power Procurement Section of the NASA Lewis Research Center, to design, fabricate and test Primary NaK Loop (PNL) valves for use in ground testing of the SNAP-8 Power Conversion System.

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A test arrangement and procedure has been devised for a miniaturized gap test in which the donor is essentially a length of hypodermic needle tubing loaded with an exploslve. The particular size used in the work reported hereln had an explosive column charge diameter of 33 mils. The procedure was used to determine gap sensitivities of several explosives including tetryl, RDX, PETN, HMX, and PBXN-5. Several of the explosives were tested of more than one particle size and loaded at more than one density. Within the group of explosives tested, both particle size and loading density had more affect upon sensitivity, as measured in these tests, than did composition. The coarser materials were found to be both less sensitive and more variable than the fine explosives. The fine explosives were found to become less sensitive as the loading density increased. This trend was apparently reversed for the one coarse explosive (RDX, Class a) for which data was obtained. The test arrangement and procedure is a promising tool for the acquisition of data for the design of fuzes of minimum dimensions.

The mechanical cycling test was required to verify the integrity of the welded joints and the thin wall tube bends in the primary loop manifold assembly of a four pack thermo electric module and to help establish structural and mechanical requirements of any possible redesign. The test section was subjected to more severe loading conditions than will be experienced during actual operating conditions. The test was a mechanical simulation of the differential thermal expansion which occurs due to the approximately 600{degrees} F temperature differential in the subassembly. The actual load exerted on the test section represented this deflection. The effects on the joints and tube material were observed. The test was conducted on a test segment of manifold designed to duplicate two of the flexible elbows; the transition joints between the elbows and the tubular module inner clad; and the welded joints of the elbows to the primary loop header. The assembled test segment and hold-down bracket are shown. The bracket was mounted to the base of the Universal Test Machine. Dial indicators measured the relative displacement between the line of applied load (through the vertical axis of the primary loop header) and the attachment point at the holddown bracket. …

The {eta}'(958) meson has been studied in the reaction K{sup -}p {yields} {Lambda}{eta}', with K{sup -} beam momenta ranging from 1.70 to 2.65 Gev/c. The Dalitz plots of {eta}' decay into {pi}{sup +}{pi}{sup -}{eta} and {pi}{sup +}{pi}{sup -}{gamma} have been examined, and from them we have determined that the most likely quantum numbers of the {eta}' are I{sup G}J{sup P} = 0{sup +}0{sup -}, although J{sup P} = 2{sup -} cannot be completely ruled out. They have also shown that the decay into {pi}{sup +}{sup -}{gamma} is mediated by the decay {eta}' {yields} {rho}{sup o}{gamma}. An examination of the production process has yielded further evidence for the J{sup P} = 0{sup -} assignment and suggested that the process takes place via K*(891) exchange in the t channel. Branching fractions and cross sections have been determined, and finally a search for a negatively charged {eta}' in the deuterium reaction K{sup -}d {yields} p{Lambda}{eta}' has confirmed the I = 0 assignment for the {eta}'.

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This document provides, by program, consolidated abstracts of two detailed annual R&D reports which individually cover separations (Atlantic Richfield Hanford Company), and reactors (Douglas United Nuclear, Inc.). Work performed by the Battelle Northwest Laboratory is included with and forms part of the basis or work described in the reports for separations or reactors. The complete annual report consists of this document and the two detailed reports. It is based on the objectives and milestones as listed in the Summary Document for FY 1968, in this summary, and the two contractor reports. The pattern of missions shown on previous semiannual and annual reports have been consolidated into four programs, Under these headings are the subitems recognizable as titles of the former missions: Basic Production; Product Flexibility; Tritium, (Coproduct); Transplutonium; Plutonium-238; Other Isotopes; Enriched Fuels (Oralloy); Target Space Enhancement; Waste Management Environmental, Safety and Regulatory Technology; Nuclear Safety; Columbia River; Radionuclides in the Soil. Estimated expenditures for fiscal years 1969--1971 are shown.

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