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This paper discusses the containment philosophy, design bases, and protective devices which have been adopted as a solution to the problem of containment in a typical homogeneous reactor installation, the Homogeneous Reactor Test at Oak Ridge, Tennessee.

The first group of Pu--Al MTR fuel elements fubricated were rejected for excessive dimensions and blistering. The fuel element constitution and fubrication was reviewed, and a new Pu--Al ratio and revised rolling techniques were suggested. (D.E.B.)

The operating conditions to which the special Mark VIII quatrefoils will be exposed during the proposed piloting program have been compared with the conditions required to cause burnout, using an established method of calculating these conditions. The results of this comparison permit the following conclusions to be drawn: (1) With normal flow of coolant through the special elements the heat flux to be encountered in the R-8 cycle (1400 MW) will be 70% or that required to cause burnout (30% margin from burnout). (2) With a reduction of coolant flow to 82% of normal through one tube of a special element, burnout of that fuel column is possible in the R-8 cycle. (3) In the R-6 cycle (1280 MW), the margin from burnout in the special Mark VIII quatrefoils is 42% with full flow and 20% with the above reduced coolant flow. A similar comparison of operating conditions predicted for the L-3 cycle (full Mark VIII charge) shows that, even at the highest power level (1250 MW), the margin from burnout is greater than 55% with normal flow and 40% with reduced flow.

Daily newspaper from Alva, Oklahoma that includes local, state, and national news along with advertising.

Letter from A. H. Blackshear Jr. to Fred F. Hunter with a check for $2.88 enclosed covering Daniel W. Kempner's statement.

Letter from A. H. Blackshear, Jr. to Daniel W. Kempner discussing financial matters such as profits made from the Arbyrd Compress Co., service charges and superintendent wages, with mentions of the weather and the receival of a check from Mary Carroll Kempner.

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The conceptual design of a low cost training reactor for the instruction of physicists and engineers is covered. It is conceived as an instructional tool for a course such as that given at the Oak Ridge School of Reactor Technology. The reactor is of a modified pool type, and is designed for a maximum power level of one Mw. This arrangement will accommodate engineering experiments, shielding experiments, and critical experiments as well as being useful as a neutron and gamma source. (auth)

Daily newspaper from Orange, Texas that includes local, state, and national news along with extensive advertising.

It is the purpose of the Fuel Element Technical Manual to Provide a single document describing the fabrication processes used in the manufacture of the fuel element as well as the technical bases for these processes. The manual will be instrumental in the indoctrination of personnel new to the field and will provide a single data reference for all personnel involved in the design or manufacture of the fuel element. The material contained in this manual was assembled by members of the Engineering Department and the Manufacturing Department at the Hanford Atomic Products Operation between the dates October, 1955 and June, 1956. Arrangement of the manual. The manual is divided into six parts: Part I--introduction; Part II--technical bases; Part III--process; Part IV--plant and equipment; Part V--process control and improvement; and VI--safety.

Daily newspaper from Ennis, Texas that includes local, state, and national news along with advertising.

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Feasibility studies of a high flux, solid fuel research reactor are presented. By means of a parameter study, a reactor consisting of a cylindricai fuel annulus submerged in heavy water is described. The thermal neutron flux peaks in the heavy water adjacent to the annulus and is a maximum in the region surrounded by the fuel annulus.. while the minimum thermal flux occurs in the annulus. The fast flux has the opposite shape. Calculations indicate that practical peaking factors, ratios of maximum thermal flux in the heavy water to average thermal flux in the fuel annulus, as high as eight can be obtained. A typical reactor in which the maximum thermal and fast fluxes are greater than 10/ sup 15/n/cm/sup 2/-sec is also described. (auth)

Letter from Harry Cohen to I. H. Kempner discussing his request to include his brothers in his biographical article. Enclosed is a sketch to be approved by Kempner as well as a chance for corrections or edits.

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The attractiveness of a helium cooled, heavy water moderated, natural uranium central station power plant has been investigated. A fuel element has been devised which allows the D20 to be kept at a low pressure while the exit gas temperature is high. A preliminary cost analysis indicates that, using currently available materials, competitive nuclear power in foreign countries is possible.

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This report is a study of the feasibility of using a fused salt fuel reactor in a central station electric generating plant.

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A report based on a study about the factors which affect the amount of chemical reaction between water and Zircaloy 2 at high temperatures. Also, experimental programs for the measurement of radiation emissivity, chemical reaction rates, and diffusion rates have been completed.

Daily newspaper from El Reno, Oklahoma that includes local, state, and national news along with advertising.

Weekly newsletter written for supervisors working at the Convair Division in Fort Worth containing news about events and activities, workplace reminders, and other relevant information.

``Safe-failure`` is an important criterion for power reactor fuel elements designed to contain core materials which react rapidly with high-temperature coolant. Out-of-pile experiments indicate that, without a ``safe-failure`` fuel element, expensive and possibly catastrophic reactor shutdowns may occur if the fuel element jacket fails during irradiation in high temperature water. That jacket failures occasionally will occur, regardless of the material or fabrication process involved, seems to be generally agreed. Fuel elements involving cluster arrangements, oxide cores, and wafer assemblies with ``bulkheads`` for compartmentalization have been proposed as being relatively safe in event of jacket failure. A fourth possibility is a type of long cartridge fuel element.