The results of our assessment of the processing methods and costs for the recovery of cesium, techneium, rhodium, and palladium from aged waste supernates are presented. Guidelines for the assessment of costs are given. Cesium can be readily absorbed from alkaline waste supernates without prior treatment using Linde AW-500, a synthetic zolite. Technetium, present in the supernate as the pertechnetate anion, together with rhodium and palladium, probably present as anionic nitrite complexes, can be absorbed from untreated waste supernates using Dowex 1-X4 or similar anion resins. Although the behavior of cesium and technetium is reasonably well understood, the behavior of the anionic complex that accounts for the presence of rhodium and palladium in this strongly alkaline solution is not well understood. Further work is required before a process can be outlined for the clean separation of rhodium and palladium from the technetium-rhodium-palladium crude fraction sorbed on the anion resin. An assessment of capital and operating costs for the recovery of cesium only, technetium only, or both cesium and technetium are tabulated. No costs are shown for rhodium and palladium, since the technology for their separation is not sufficiently advanced. However, the incremental cost for their separation from technetium is expected …

A simplified procedure is described for the preparation of crystalline bacteriochlorophyll from R. rubrum. The chemical dehydrogenation of bacteriochlorophyll with quinones is shown to give high yields of 2-desvinyl-2acetyl-chlorophyll a, whereas the photo-oxidation of bacteriochlorophyll results in a mixture of products of which 2-desvinyl-2acetyl-chlorophyll a is only a minor constituent. A number of interesting results have been observed spectrophotometrically during these oxidations under different reaction conditions. These observations are discussed and possible reaction mechanisms are outlined. The proton magnetic resonance spectrum of 2-desvinyl-2acetyl-chlorophyll a in deuteroacetone and the visible absorption spectra of this pigment and its magnesium-free derivative in acetone are reported. As expected, these spectra exhibit a marked resemblance to chlorophyll a and pheophytin a.

This report, from the Chemical Processing Department at HAPO for May 1966, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee-relations, and waste management.

The power of some SRP fuel assemblies is limited by the burnout safety factor (BOSF) in some applications. This power limitation is unnecessarily restrictive, because the current conservatism in predicting film boiling burnout is unusually large compared to that in predicting unstable flow in fuel assemblies. In the past, most SRP fuel assemblies operated at the flow instability limit and were far enough removed from burnout that a convenient and very conservative burnout limit system could be used. If the same degree of safety was used for both burnout and flow instability, the power of BOSF-limited assemblies could be increased. This memorandum, which is part of the program to improve the system for protection against burnout, evaluates the probability and consequences of burnout at various BOSF levels.

A new concept for separation of the isotopes of uranium has been developed. The invention consists of a new process with essentially no moving parts. The new process is called the Ionized Vapor Process and is described in this report.

This report details activities of the N-Reactor Design Analysis Unit for the month of June 1966.

This report details 200 Area activities for the month of May 1966.

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Submitted herewith are source and special nuclear material composition of ending reports for the month of May 1966. Production processes and products and weapons process and products are accounted along with nonproduction reactors R&D.

This report has the following sections: Summary; Civilian Power Reactors; Applied and Reactor Physics; Reactor Fuels and Materials; Engineering Development; Plutonium Recycle Program; Advanced Systems; and Nuclear Safety.

The Pacific Northwest Laboratory has convened this meeting to enlist the best talents of our laboratories and industry in soliciting factual, technical information pertinent to the Pacific Northwest's Laboratory's evaluation of the potential fuel systems for the Fast Flux Test Facility. The particular factors emphasized for these fuel systems are those associated with safety, ability to meet testing objectives, and economics. The proceedings includes twenty-three presentations, along with a transcript of the discussion following each, as well as a summary discussion.

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During the reentry destruction of an isotopic generator, the mechanisms of fuel form ablation must be predictable to properly assess the nuclear hazard associated with the event. Ultimate land deposition patterns and contaminant densities are directly a function of the final ablative particle size. One mechanism of fuel form ablation is the mechanical breakup of molten material by aerodynamic forces created during hypervelocity reentry. The object of this study was to determine the feasibility of describing the breakup phenomenon by statistical mechanical analytic techniques, and to determine the applicability of employing a light gas gun and a controlled environmental range to experimentally observe the breakup phenomenon. (auth)

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This is a data analysis report of the 25 tests conducted with the Cold Flow Development Test System during October and November of 1965.

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The fission product, promethium-147, would be much more desirable as a heat-producing radioisotope if it were not in such short supply. C.A. Rohrmann`s chart ``Characteristics of Radioisotopic Heat Sources`` lists the annual availability of Pm-147 as 5-5 kw, corresponding to about 17 kg. Hence, consideration has been given to irradiation of neodymium-146 in order to augment the supply of Pm-147, A method for separating Nd-146 from other neodymium isotopes does not exist today. This memorandum presents the results of a brief look at the irradiation of mixed neodymium isotopes which are available without isotopic separation.

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