A test was carried out to determine the adequacy of storage capacity and operating procedures of the radioactive waste disposal system during a normal reactor plant warmup. The capacity and operating procedures were found to be adequate. It was impossible to perform a complete material balance based on existing level instrumentation and using the data required by the test procedure. Approximately 21,290 gal. of waste were received in the system and 13,210 gal. were discharged to the river with a total activity of 1200 mu c. A quantity of 6,670 gal. of reactor coolant effluent was processed. Approximately 634 lb of combustible waste were incinerated. (M.C.G.)

S>Progress is reported on the research and development program being performed in connection with the design of the Pathfinder Atomic Power Plant. The topics covered include: fuel material cladding, bonding, and irradiation testing; heat transfer and fluid flow; fuel element manufacturing research and development; low-enrichment superheater fuel element design; mechanical studies of control rods, guide tubes, and control rod drives; reactor physics; and reactor and system dynamics. (C.H.)

Plant drawings for the final design for the Army Reactor (PL-2) are presented. Two hundred and twenty-eight figures are included. (M.C.G.)

The physical and mathematical reactor models which are used in Program ODD are discussed. In addition, the FORTRAN II source program listings, decimal data input sheets, and input and output for a sample case are given. Program ODD was designed to raake use of the Revised Nuclear Data System at ANPD which consists of twenty-five energy group cross-section data including high energy inelastic scattering matrices, resonance parameters for the resolved resonances, and thermalization scattering matrices for the near thermal energy region. The most unique aspect of the program is the mathematical technique employed for eliminating inner iterations and slow convergenc rates occasioned by the up- scattering'' in the thermalization region of the energy lattice. Direct inversion of the energy matrix coupling the thermal and last four epitherma groups provides simultaneous consistent solutions for thes groups within each power iteration. (auth)

Drawings andd specifications for the PL reactor core are given. The requirements for the material procurement, fabrication, testing, and inspection of one P L-2 reactor core and spares are listed. (M.C.G.)

A detailed analysis was made of the power distributions in the SM-2 experimental core at 68 deg F and the SM-2 reference core at 510 deg F. This analysis supersedes the power distribution calculations presented in APAE No. 69. The calculated distributions for the experimental core were normalized to measured data wherever possible in order to obtain corrections factors for application to the reference core. The over-all power distributions were calculated by synthesis of one-dimensional axial calculations with twodimensional radial calculations. The variation of the power distribution with fuel burnup is also presented. In order to improve the agreement between measured and calculated axial power distributions, flux-weighting the nuclear parameters in the rods-in and rods-out regions was investigated. (auth)

Specifications for the plant equipment for a P L-2 nuclear power plant are given. (M.C.G.)

This report contains the reports of progress and the plans for future work of Douglas United Nuclear, and Atlantic Richfield on the Basic Production Mission. This mission covers the Research and Development work associated with operating the Hanford production complex in its present mode. For the conventional reactors this means primarily the production of weapons-grade plutonium. For the N Reactor this primarily concerns the production of plutonium of 12 percent Pu-240 content, or such other Pu-240 level as may be assigned by the Commission. For Atlantic Richfield this entails isolating and purifying the products of the above described reactor operations. The report describes scope and objectives, progress during report period, evaluation of effort, budget period plans, milestones, references, and statistical summary schedules for the Hanford low pressure reactors, the N reactor, and spent fuel processing activities.

At the request of NRD (NPR Physics Subsection) a study was initiated to determine the physics characteristics of various plutonium-uranium composites as fuel for the NPR. From this study, the PuO{sub 2}-UO{sub 2} fuel system was selected to receive major attention. The effect of adding a burnable poison, B-10, in intimate contact with the mixed oxide fuel was also is to be considered. The present report summarizes the results of these investigations.

Research and development activities included: spike loading of N-Reactor, Flex 3 program development, co-product hazards studies, and thorium fuel studies.

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This investigation was undertaken to determine the approximate impact characteristics of delta stabilized plutonium 1% gallium alloy, both at room temperature and at 325{degree}C. The testing done was non-standard, primarily because some approximate information was desired for another purpose and immediately available materials were used. While the results reported herein should be considered preliminary, they clearly depict the ductile impact behavior of this alloy.

This document details activities of the Fuels Preparation Department during the month of May 1960. (FI)

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.

Results of a survey covering the safety, adequacy, and reliability of certain design and construction features pertaining to the NS Savannah nuclear power plant and related systems are presented. (auth)

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This is number six in a planned series of reports intended to show the status and rates of deterioration of the iron-masonite biological shields of B, Dg DR, F, and H reactors. Since DR, F, and H reactors are in the deactivated state this is the final such report for them. Following the deactivation of D Reactor at the end of June, 1967, B Reactor will be the only one (out of the five with which the shield deterioration study began) to continue operating. Data for this report pertain to the top and left (far) side of the reactors and covers the period from January, 1963, through December, 1966.

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Declassified 6 Sep 1973. Design and operating parameters for /sup 210/ Po- and /sup 238/Pu-fueled thermoelectric generators for use in the Apollo Program are presented. (TFD)

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