This document is a summary of the new Reactor Operations Daily Report, which is to be implemented August 3, 1964. The report explains how the form is to be filled out, and what information is to be entered into the different fields on the form.

The N-Reactor was shutdown on July 7, 1964, due to fuel rupture indications on tube 3361. The rupture has been confirmed as a failure in the downstream inner fuel element in tube 3361 caused by a pin hole in the weld and braze metal. This document presents a historical record of the rupture indications observed prior to and following the shutdown. The operating history of tube 3361 is compared with an adjacent tube, with no abnormal conditions observed at any time. Reactor temperature and power history since initial primary loop heatup are presented to show the total operating history experienced by N-Reactor.

This report describes laboratory-scale studies made to evaluate the feasibility of using uranium(IV)-hydrazine instead of ferrous sulfamate-sulfamic acid as the partitioning agent in the Hanford Atomic Products Operation Purex separations plant. Iron(II), in combination with sulfamic acid as a holding reductant, has been used very successfully for many years as a plutonium reductant in solvent extraction separation processes for irradiated nuclear fuels. However, the iron remains in the radioactive wastes produced in the separation processes. Its presence in these wastes accelerates corrosion of waste concentration equipment, complicates treatment of the waste for by-product recovery and adds to the total quantity of contaminated salts which must be stored. Much effort has gone into searches for plutonium reductans which would not have the disadvantages associated with iron(II). Uranium(IV) has been proposed since, having acted as reductant, it is extracted along with uranium from the irradiated fuels and does in solvent extraction separations processes have involved mixer-settler contactors. The HAPO Purex plant has pulsed-column contactors. This difference, plus certain problems due to the particular flowsheet conditions used, required that additional laboratory studies be made to determine the feasibility of using uranium(IV) in the HAPO Purex plant.

The hot-die-sized concept has been under investigation as an alternate manufacturing process for several years. Irradiation testing of the elements began in mid 1963. Some dimensional behavior problems were encountered with the fuel and a test is now being irradiated which may provide sufficient data to remedy the situation. Pre-irradiation examination of fuel elements has shown a significant dimensional change of the cores during the fabrication process, and this dimensional change is thought to contribute to the irradiation behavior of the elements. The irradiation effects of fabrication parameters that influence the dimensional. The objective of the test detailed in this is to evaluate the effects of end bonding pressure and machined core size on the irradiation characteristics of hot-die-sized diffusion bonded fuel elements.

A number of tests have been performed and reports issued concerning the adequacy of the last-ditch cooling systems at the Hanford small production reactors. At the present time, re-evaluations are being made, both theoretical and experimental, by process engineers and others at th particular reactor sites. In the interest of uniformity and consistency, this report presents a means of determining the last-ditch cooling adequacy for all the small production reactors. This method includes both the night tanks and the export system.

Two changes have been incorporated in the tables of this draft: (1) The lithium-aluminum tonnages required for blanket and E-N loadings have been changed, (2) The production numbers for the small production reactors have been reduced per AEC direction, and a separate table is included for these numbers. Included data are power levels, operating efficiency, exposure, tonnage, conversion ratios, and annual production for the C, K, and small reactors.

The horizontal control rods presently installed in the older Hanford Reactors have inadequate heat transfer characteristics for present and predicted future operation of the reactors. Continued graphite stack distortion, coupled with higher graphite temperatures, has resulted in ECR failure during reactor operation, such as swelling of the outer aluminum sheaths to the extent that rod movement in the graphite channel is severely restricted. Continued graphite stack distortion will tend to further aggravate the problem of rod operation. A new HCR design concept,was developed by P. H. Hutton of Reactor Design, IPD, to alleviate some of the pressing operational problems. Prior to the acceptance of such a design, the important rod operating parameters should be known to some degree of accuracy. This study was conducted to detexmine, by calculational methods, the temperature distributions that could be expected to occur in such an HCR when used at the present operating power levels and at 120% of the present power levels.

This report details activities of the Metallurgy Development Operation for the months of April, May, June 1964.

Quarterly report regarding the activities of the Yankee Core Evaluation Program, the purpose of which is to evaluate the performance of the core used in the Yankee Plant and to compare actual performance with predictions, as well as the revision of designs to address any differences between actual and predicted performance.

Abstract: This memorandum discusses a new design definition technique, requiring no standard, which pictorially shows part and gage limits on the same drawing. When functional gages, test fixtures, or optical chart gages are the selected inspection method, design, manufacturing process, and gage engineers can use these drawings directly to replace the usual standards-based drawings. In essence, this advanced technology visually describes true position dimensioning and tolerancing. It enables product designers to directly control the acceptance process.

Introduction: On November 14, 1961, an environmental test program commenced on the first SNAP 10A system structure, S10A-PSM-1.

Abstract: this report discusses and summarizes all stress analysis done on the SNAP 10A system; it also mentions many of the structural tests which were accomplished.

Abstract: This report presents the results of the structural tests which were performed on the S10A-PSM-1A system to qualify the basic structural design for the anticipated launch environment.

Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.

Outdoor monitoring of air, water and vegetation in the vicinity of the Paducah Plant is summarized for the years of 1962 and 1963.

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This report addresses the development of an improved "bubble through" saturator.

Declassified 27 Nov 1973. Information is presented concerning Tory-2C operations and testing; reactor kinetics; control system and instrumentation; and physical properties of ceramic materials. (DCC)

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This report describes the initial approach to critical experiment and power level, control rod, and moderator level calibration experiments which were conducted in the PRCF when it was moderated with D2O.