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One of the major factors restricting reactor power levels is the incidence of ruptured slugs. The primary purpose in studying ruptures is to determine how reactor operating variables affect rupture rates. With this knowledge reactor operating conditions may be adjusted or controlled in the manner that will optimize reactor production. In addition, knowledge of rupture rate relationships are useful in fuel element development and in overall economic studies of existing and proposed reactors and reactor processes. This report is a compendium of various types of rupture information largely developed during the past eighteen months. Plant rupture experience for CY-1957 is reviewed; rupture rate correlations with reactor variables for solid natural uranium material are presented; a comparison between solid and cored natural uranium material rupture rates is made; the basis for current discharging practice of rupture-prone metal lots is discussed. 11 figs., 2 tabs.

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Presented at the 1958 Winter Meeting of the American Nuclear Society, December 9, 1958. Experimental and theoretical work on the selflimiting response of reactors to step and ramp insertions of reactivity is discussed along with the general characteristics of self-limiting power bursts. The static characteristics of the cores investigated are presented and the techniques of measurement are discussed. Data from step and ramp tests are presented and compared with the predictions of a theoretical formulation of reactor self- shutdown in terms of energy release. The discussion includes an evaluation of some postulated shutdown mechanisms in the light of experimental results. Some results of detailed calculations of shutdown effects due to specific mechanisms which are believed to contribute significantly to reactor self-shutdown are presented. (auth)

The Pu in one batch (160 gms) is precipitated in a purification hood and waste supernatant is then transferred to the storage tank in one of the recovery hoods. Under normal process conditions a small amount of Pu remains in the supernatant. However, it is possible, though extremely unlikely, that the entire 160 grams would be transferred to the waste storage tank. The supernatants are transferred to an evaporator where they are concentrated. This evaporator has dimensions approximately the same as those of the storage tank, however, as concentration proceeds, the remaining solution can pass to a geometry more favorable for a chain reaction. There should be definite assurance before evaporation is begun that the amount of Pu in the evaporator does not exceed 160 grams. It is concluded that there is no objection, from a nuclear safety standpoint, to the discontinuance of analysis of the supernatants.

Angular distributions in SIGMA /sup +/ decay are analyzed for informatlon on SIGMA spin and parity conservation in SIGMA production. No evidence for a SIGMA spin > 1/2 or parity nonconservation in SIGMA prodiction is found. (auth)

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Seven control rods will be used in the APPR-1 instead of five as originally planned. Critical experiments evaluating the rod worth for the APPR-1 have been performed at ORNL, and calculations have been carried out by ALCO interpreting these experimental results. The calculations indicate that the capability of any four of the original five rods to shut down the cold reactor at mid-life is marginal. The calculations are summarized in this memorandum. (auth)

A simplified model for solids deposition in the pot calcination of waste was analyzed, and numerical calculations were made. In long calcination pots of 10 to 12 in. diameter, calcination times should not exceed 24 hours and might be as low as three hours if the pot is kept full. If the pots are fed at a constant rate, the cake might form with a steady state V'' when viewed in vertical section which would progress from bottom to top. Cake deposition rates appear to be independent of pot radius. Several advantages to using larger diameter pots are discussed. (auth)

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The feasibility of designing and developlng a canned centrifuge capable of operating for extended periods in a highly radioactive area was investigated. A preliminary design for the entire unit is outlined. It is concluded that such apparatus can be designed and built. Cost estimates are given, and recommended features for incorporation in the centrifuge are listed. (J.R.S.)

This report lists some physical properties data of aqueous homogenous reactor materials.

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The November, 1957 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)

This report descrirs Chemical Properties of Elements 99 and 100

A description of some of the chemical properties and of the methods used in the separations of elements 99 and 100 is given. The new elements exhibit the properties expected for the tenth and eleventh actinide elements. Attempts to produce an oxidation state greater than 111 of element 99 have been successful. In normal aqueous media only the 111 state of element 100 appears to exist. The relative spacings of the elution peaks of the new elements in some separations with ion exchange resin columns are the same as the relative spacings of the homologous lanthanide elements. The results of experiments involving cation exchange resins with very concentrated hydrochloric acid eluant show that the new elements, like the earlier actinides, are more strongly complexed than the lanthanides. The new elements also exist partially as anions in concentrated hydrochloric acid, as do earlier actinide elements, and they may be partially separated from each other by means of ion exchange resins. With some eluants interesting reversals of elution positions are observed in the region Bk-Cf-99-100, indicating complex ion formation involving unusual factors.

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A brief description of the process is given, and details of work over a three-year period are summarized. The continuous production of Re metal by low- temperature fused salt electrolysis into a continuously circulating Hg cathcde has been demonstrated. The product is amenable to direct hot pressing or to powder preparation by distilling off the Hg. The production of pure BeCl/sub 2/ in good yield by direct chlorination of BeO has been demonstrated. The production of pure BeCl/sub 2/ in good yield by direct chlorination of beryl has been studied. The status of this work is not sufficiently advanced to permit valid conclusions as to ultimate success. The electrolytic cell and associated equipment and the chlorination equipment are described in detail. Operating procedures and representative results are given. The course for continued work is indicated. (auth)

Submitted as a thesis by William Berdell Barlage, Jr. Heat transfer studies were refined and extended to the point where the results could be generalized into a mathematical correlation valid over a reasonably wide range of variables. An extended study was made of the rate of heat transfer between benzene and water in direct contact in a pulse column, and of the operating variables which controlled the behavior. In this mode of heat transfer the benzene was dispersed as a family of droplets into the water, which formed the continuous phase. The pulse column was 1.92-in. in inside diam., and contained 8 stainless steel perforated plates spaced 2.00 inches apart. The plates were perforated with 1/8-in. holes in a triangular 60 deg pattern, providing 24.6 per cent free area. The equipment was carefully insulated and modified in many details in order to permit precise heat transfer measurements. The operating conditions were varied so as to provide wide ranges of variables and heat transfer responses. (W.L.H.)

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A complete algebraic analysts was obtained for the variation of the steady state ion density n+ with injected current I in an OGRA-tane fusion device (i.e., a device based on trapping of ions by breakup of energetic molecular ions on collision with either the background gas or trapped ions). The most general variation of n+ with I is shown to be an s-curve with at most three rots of n+ for a given input I. A physical interpretation of these three roots is given. In addition algebraic expressions are obtained for the two currents at which the bends in the s-curve occur. It will be necessary to attain the larger current in order to build up a high density plasma when the density ia being increased from below. On the other hand, once the high density has been achieved it may be maintained by steady injection of a current larger than the lower value. Parameters corresponding roughly io the specifications of OGRA are used io obtaam some numerical results. The previously published formulas for burnout in DCX are extended to include effects of neutral backstreaming from the input beam and "ion- pumping." (aath)

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