This discussion and summary report illustrate the type of information that is in data processing machine language and available to those who require it. The reports are comprised of three major sections. The first is a map indicating the number of recordings of data in the category defined by the function number code. The second is a summary of the data, in term of hours, for each of the functions performed during an outage, except secondary function code number 21 which is the number of tubes associated with the basic function performed. The third is a summary of the secondary functions performed with a basic function class, the associated delay total and the number of tubes involved for those functions where a delineation by tube count may be of interest.

This report is a summary of the way information is stored on the maintenance histories of the Hanford Production Reactors. Twenty two different categories are considered as primary reasons for maintenance down times. The data is stored in terms of hours spent on different tasks, and is also grouped by the controlling cause of the outage.

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The feasibility of operation with an enriched core to ``override`` the xenon transient and thus reduce minimum downtime has been reasonably well established. The principle economic disadvantage of the present technique is associated with the use of boron splines for compensating the reactivity effect of the core during normal operation. The boron-containing spline parasitically absorb the excess neutrons produced in the core thus wasting these surplus neutrons during the operation when the enriched core is compensated by poison; also, because of the relatively slow removal rate of irradiated splines, a significant portion of the potential downtime reduction is used to remove the splines from the core. The purpose of this report is to point out incentives and alternate methods for improved poison control with the xenon override core and to present current plans for resolving these limitations to the xenon override concept.

These technical specifications are applicable to the eight operating production reactor facilities, B, C, D, DR, F, H, KE, and KW. Covered are operating and performance restrictions and administrative procedures. Areas covered by the operating and performance restrictions are reactivity, reactor control and safety elements, power level, temperature and heat flux, reactor fuel loadings, reactor coolant systems, reactor confinement, test facilities, code compliance, and reactor scram set points. Administrative procedures include process control procedures, training programs, audits and inspections, and reports and records.

The purpose of these tests is to provide necessary laboratory data in support of an R,PEO program in determining the energy loss associated with various hardware size combinations on the rear face of the B-D-F reactors. The original method used to check for critical flow was determined to be faulty. A revised method demonstrated critical flow did occur in the 5/8-inch inconel connector and combination 1 fittings. The remaining fitting combinations with the 5/8-inch inconel and 3/4-inch aluminum connector were not rechecked because of the reaming of the I.D. to permit the continuation of the original tests. During test number 6, audible cavitation was heard with the highest severity at a point midway between pressure points 3 and 4 on the connector. This condition appeared again in tests 6A, 7, and 7A, with incipient cavitation at approximately 40 gpm in each test, regardless of the rear header pressure and/or temperature.

This is one of twenty-one volumes sumarizing the Aircraft Nuclear Propulsion Program of the General Electric Company. This volume discusses the background to the General Electric program, and summarizes the various direct-air-cycle nuclear test assemblies and power plants that were developed. Because of the requirements of high performance, low weight, and small size, vast improvements in existing technology were required to meet the flight objectives. The technological progress achieved during the program is also summarized. The last appendix contains a compilation of the abstracts, tables of contents, and reference lists of the other twenty volumes.

This is the monthly report for the Hanford Laboratories Operation, May, 1962. Reactor fuels, chemistry, dosimetry, separation process, reactor technology employee relations, operations research and synthesis operation, programming, and radiation protection are discussed.

The purpose of this document is to provide a tabulation of data concerning ruptured slugs for the use of various interested parties. This report presents data for the ruptures that occurred from January 1, 1962, through April 30, 1962, inclusive. Definitions of the terms used in the tabulations are nearly self-explanatory and are documented in the reference document. The possible exceptions to this are the three terms: type of metal, type of failure, and lot number. The legends currently in effect for these three terms are provided in this report.

This discussion and attached summary report illustrate the type of information that was in data processing machine language and available to those who require it. The reports are comprised of three major sections. The first is a map indicating the number of recordings of data in the cateogry defined by the function number code. The second is a summary of the data, in terms of hours, for each of the functions performed during an outage, except secondary function code number 21 which is the number of tubes associated with the basic function performed. The third is a summary of the secondary functions performed within a basic function class, the associated delay total, and the number of tubes involved for those functions where a delineation by tube count may be of interest. The function code numbers relate directly to the definitions of the hours expended for charge-discharge, rupture removal, tube leak repair, tube replacement, and so forth. These definitive classes are taken from the distribution records supplied by the various reactor analysts and summarized by the Reports and Statistics group in the IPD Production Operation.

The SNAPSHOT Safety Program, as described in this document, is therefore formulated to align safety studies performed by separate agencies and their contractors. At the present stage in program development, the plan is principally concerned with the initial SNAPSHOT flight (SNAP 10A). SNAPSHOT represents a special flight mode for the initial reactors operated in space. The flights are designed to permit early space reactor tests prior to resolving all the safety proglems that may be associated with more advanced programs. Of primary significance is that reactor operation will not be initiated until an orbit of satisfactory lifetime has been obtrained, thus ensuring the long-term decay of the fission products producted prior to re-entry.

The scope of this report is as follows: (1) Presentation of data obtained from the well flow metering tests performed during the week of May 28, 1962; (2) Interpretation of the observed data relative to total mass flow, chemical composition, and heat energy available from the well discharge at this stage in the well flow test program; (3) Compilation of well head pressure and temperature readings and other available pertinent data regularly logged from start of flow test program on May 18, 1962; (4) Determination of electric power generating capability of the well based on observed data; (5) Determination of quantity of major chemical constituents available from the well effluent; and (6) Conclusions and recommendations regarding well performance, future test procedures, and test equipment.

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A superposition model is developed to predict the critical heat flux in forced convection flow. The model is applied to available experimental results in boiling water flows and good agreement is obtained between the model and test data over the multitude of geometries, flow rates, pressures, and fluid enthalpies tested to date. (auth)

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Fission product Ru, normally volatile to the extent of 20 to 60% in evaporation and calcination of simulated high level radioactive wastes at 500 to 1000 deg C, can be 99.9% retained in the solid product by addition of 2 moles of phosphite or hynophosphite per liter of waste. As little as 0.1 mole per liter lowered the Ru volatility during distillation approaching equilibrium by factors which varied from 38 for Darex to 225 for TBP-25 (aluminum) waste solutions. The final products with Purex, TBP-25, and Darex (stainless steel) wastes were insoluble glassy solids with densities of 2.4 to 3.8 g/ml and represented volume reductions of 2.9 to 8. These volume reductions are essentially the same as those obtained when the waste is calcined without additives. (auth)

Research and development progress is reported on plastics, analytical methods, radioelements, isotope separation and purification, reactor fuels and materials developmert, Ranger x-ray sensor program, and SNAP a. (M.C.G.)

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