This document discusses waste disposal criteria were established on the basis that the occurrence of river flow rates which were 72 cents of normal would not cause the effects of waste disposal to exceed limits. Since even the base case exceeds the criterion for the average body burden of phosphorus-32, provision to reduce the output of this radioisotope must be included in any expansion program. Provision to reduce the output of other radioisotopes will be required for most cases where the bulk outlet temperature limit is 105{degrees} or higher. For reactor flow rates exceeding 100,000 gpm it may be necessary to reduce sodium dichromate concentrations as low as 1.5 ppM during periods of low river flow. Heat output was discussed but no limit was set.

It has been proposed that Pu-238 be produced by irradiating neptunium solution in one or more loops in a reactor and then recovering the Pu-238 in a close-coupled separations plant. Such a scheme could replace the more conventional scheme of solid element fabrication, irradiation, and reprocessing for plutonium and neptunium recovery. This document presents the advantages of such a scheme from the standpoint of product purity and Pu-238 production.

The process water pumping system for the K-reactors consists of six parallel sets of two series-connected pumps. A BPA outage could sever the power to all pumps. It is of major concern to known how the reactor flow decays with time following the power severance. The following analysis gives the general solution of this problem without recourse to the assumptions which have been used heretofore. The solution of the decay problem was programmed on the IBM 709. The program will give the flow transient for two series-connected pumps arbitrary physical characteristics, initial conditions, system and supply curves. It will give the decay characteristics for loss of power to either or both pumps. A full description of the program and its output is given in the Appendix.

The objective of this test is to determine the quality and erosion resistance of cape and cans produced from cast X-8001 alloy blanks through fabrication and irradiation of limited quantities in accordance with the testing procedure herein defined. Components which were fabricated from X-8001 alloy cast blanks have been subjected to rigorous out-of-reactor tests and have indicated equivalence or possible superiority to standard X-8001 alloy components. It is, therefore, proposed that; (1) six enriched charges of (0.94% U235) test material alternated with standard control material be irradiated; two to 500 MWD/T, and four to 800 MWD/T goal exposures in an old reactor, to compare corrosion resistance and (2) up to 240 charges of test enriched fuel elements be irradiated to normal variable goal exposure for enriched I&E in the same reactor, to further evaluate the performance of the components fabricated from cast blanks.

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A description is given of the properties of the nuclides included in the active deposit'' of thoron. A method is presented for obtalning a quantitative measurement of the activity of the transient-equilibrium mixture. (auth)

Heat loss tests were conducted with six insulation configurations for application in the riser regenerator and auxiliary regenerator sections of the loop. Insulation consisting of ten laminations of 0.003 in. stainless steel shim stock spaced 1/8 inch apart produced a temperature drop across the 15/16 inch annulus of 1200 F with a heat loss of 1.04 KW per foot of 2 inch schedule 40 pipe. The curve of heat loss vs. temperature difference is presented which, with results of similar tests with a 1/4 inch annulus, will permit the evaluation of a heat balance and temperature profile for the entire loop. (auth)

At present, the Purex Plant employs a two-stage process for the recovery of nitric acid from high-level wastes. This report summarizes the results of a design study on the Phase I installation of a prototype demister (vapor filter) between the E-F6 Concentrator and the T-F5 Acid Absorber. Further, the results of an engineering study are presented on the feasibility of the subsequent Phase II bypassing of the E-F11 Concentrator and auxiliaries to permit single-stage acid recovery, once satisfactory performance of the Phase I prototype equipment has been demonstrated. 7 figs., 2 tabs.

The behavior of insoluble corrosion products in the HRT is generally understood and studies of the removal of these solids by hydroclones can logically be terminated after the effect of higher processing rates by the multiple hydroclone has been determined. Chemical descaling may be required to supplement solids removal by hydroclones. Laboratory studies to find suitable reagents will be continued in conjunction with decontamination work presently in progress.

Developments in the production of various graphite products and data on the properties, outgassing, and radiation resistance of various graphites are reviewed. (C.J.G.)

An apparatus is described for using phosphorescent particles to enable photographic determination of qualitative and quantitative instantaneous velocity profiles in flowing liquids. Phosphor and film data are tabulated, and factors to be considered in analysis ot the photographs are discussed. (J.R.D.)

Absorption spectrophotometric methods were used in a study of complex ion formation and acid-base reactions in fused chloride and nitrate systems. Several methods for the treatment of spectrophotometric data were investigated. The spectra of various chromium salts were determined in three nitrate melts and in fused lithium chloride-pothssium chloride. In low solute concentrations in LiNO/sub 3/-KNO/sub 3/, NaNC/sub 3/-KNO/sub 3/, and LiCl-KCl melts, the species found was the chromate ion, while in molten AgNO/sub 3/, the species found was the dichromate ion. An explanation of these observations is put forward, and their significance discussed. Formation constants for leadchloro and lead-bromo complexes were evaluated. The values obtained for the first two lead-chloro and leadbromo complexes are 11.3, 3.6 and 13.3 and 6.0, respectively. Mass spectral studies of the gaseous products of the reaction between dichromate ion and nitrate ion in fused NaNO/sub 3/-KNO/sub 3/ showed that the reaction is of an acidbase type, involving formation of a nitronium ion which then reacts with nitrate ion to evolve dinitrogen pentoxide decomposition products. A number of qualitative experiments in fused salts involving acid-base reactions were performed, and their relation to oxidation-reduction processes in the fused salts is discussed. An analogy is drawn to …

The behavior of insoluble corrosion products in the HRT is generally understood and studies of the removal of these solids by hydroclones can logically be terminated after the effect of higher processing rates by the multiple hydroclone has been determined. Chemical descaling may be required to supplement solids removal by hydroclones. Laboratory studies to find suitable reagents will be continued in conjunction with decontamination work presently in progress. Rare earth solubility levels and thus poison fraction from this group will be measured after the addition of signiflcant quantities of four important elements has minimized analytical detection problems. The role of the tellurium precursor in the interpretation of iodine behavior will be eximined extensively in the present run in an effort to resolve previous discrepancies. Studies of iodine behavior can be continued after shutdown of the hydroclone system if required. An electrolytic process for removal of nickel from fuel solution has been developed through the laboratory and engineering scale except for the design and testing of a cell suitable for radioactive environments. (auth)

Recent experiments show that a positive ion beam with a density exceeding 10/sup 8/ ions/cm/sup 3/ will neutralize its space charge by trapping electrons within the beam. This trapping of electrons converts the ion beam to a neutral plasma suitable for injection and polarization experiments in a cross magnetic field. The ion energy used is about 500 volts. The beam moves readily across the magnetic field due to polarization of positive and negative charges. To create a hot plasma, it will be necessary to use higher energy ions, increase beam density, and retain neutralization by trapped electrons. (W.L.H.)

A careful determination of /sub 2200/ from results of the Macklin- deSaussure manganese-bath experiment involves corrections for (1) the weak but nonzero transmission of subcadmium neutrons through the uranium or plutonium foils and (2) the small variation of with energy in the subcadmium region. The derivation of a single general expression for applying both these corrections is presented, and two lBM 704 codes (MTC and GTC) which were written especially to facilitate the numerical evaluation of this combined correction factor are described. (auth)

In formulating this general diffusion theory expression which represents the neutron balance in a nuclear chain reactor the following assumptions were made : (1) the medium through which the neutrons are diffusing has a low neutron capture cross section, (2) the region in which the flux distribute is being described is two or three mean free paths from strong sources and sinks or from a boundary. Certainly, is going to the lattice cell of a receptor, both of the above conditions are violated; fuel elements have a large absorption cross section and most lattice cells are only two or three mean free paths to is over-all sites

Technical report describing the investigation undertaken to determine the necessary requirements for obtaining sound bonded joints on tantalum. Corrosion and Mass Transfer Loops LTTN 237A and 427 called for fabrication of 430 stainless steel clad tantalum tubing. Since there was little or no experience at welding this material at CANEL, specimens were welded using vacuum chambers and plastic chambers as normally used for loop fabrication. Resistance welding was performed without the use of a special atmosphere producing sound bonds.

Facilities shall be provided in the 221-U Building for removing fuel elements from the casks as placed in the railroad tunnel from the transfer facility and moving the elements to modified existing 10' X 16' X 14' storage tanks in ten existing cells where they will be stored, until scheduled for processing.

A number of Pu-Al and UO2-PuO2 Zircaloy clad capsules have been fabricated for irradiation in the MTR. In addition, a four rod cluster containing Al 8 w/o Pu and Al 12 w/o Si 8 w/o Pu cores has been successfully irradiated and discharged from Loop 3 of the KER. A second four rod cluster is awaiting irradiation and design and fabrication of a seven rod cluster test element is underway.

Basic Studies. Sinterability studies on the isomorphous system UO2-PuO2 have continued. One-half inch diameter X 3/8'' long compacts containing physical mixtures of the two components have been heated in hydrogen. Sintered density as a function of time and temperature has been determined for times of one and eight hours up to 1600 C. In general, there seems to be minima on isothermal plots of density versus composition in the intermediate range 20-40 w/o PuO2. At concentrations greater than 40 w/o PuO2, density increases rapidly with increasing PuO2. In every case pure PuO2, (produced by decomposing plutonium oxalate at at 300 C) sintered to a greater density that ball ball milled PWR grade UO2. The data, for a one hour soak time, and tabulated in percent of the theoretical crystallographic density, can be seen below:

The following is taken from ORNL-2257, Instantaneous Velocity Profile Measurement by Photography, by R. E. Lynch, L. D. Palmer, and G. M. Winn. This report is in in preparation status; and errors, inconsistances, and omissions in he language, as well as in the technical aspects, may exist. The technique of using phosphorescent particles to enable photographic determination of qualitative and quantitative instantaneous velocity profiles is covered by AEC Patent Application No. SN-710, 371 issued to F. E. Lynch, L. D. Palmer, H. F. Poppendiek, and G. M. Winn and entitled " A Method of and Means for Visualizing Fluid Flow Patterns.