The Purex Plant has been requested to process Z-Plant MR and EPT solutions containing about 200 kilograms of plutonium in order to alleviate processing problem at Z-Plant and to reduce the inventory of MR and EPT rework. Campaign recycle of uranium through the main plant is recommended as an economical and effective means of reworking large quantities of Z-Plant plutonium solutions. This memorandum outlines process alternates and costs for reworking the solutions and itemizes specific recommendations for process and critical mass control.

In response to an inquiry by Euratom, estimates of the costs for the production of 85 kg of 15% Pu-240 metal and for the production of 15 kg of 25% Pu-240 oxide at HAPO were recently requested by the Atomic Energy Commission. In connection with this inquiry, comments were requested regarding the possibility of establishing and measuring product plutonium oxide ``sinterability`` parameters. This report presents estimates of the costs for separations processing by the Chemical Processing Department for the cases of interest. Process ground rules and any necessary assumptions are explained. In addition, the problems of measuring oxide ``sinterability`` are briefly discussed. Highlights of this study were previously transmitted to the Irradiation Processing Department for incorporation in a formal reply to the original Commission request. Subsequently, some adjustments in ground rules have caused cost changes which are included in this report.

Several evaluations of Harvey ``O`` size natural I&E aluminum components have been made. The performance of components received prior to May 1961, was unsatisfactory. To improve component quality, Harvey made major process modifications. Components processed at HAPO after July 1, 1961, were received subsequent to Harvey`s modifications, and met specifications. Procurement and evaluation of an additional 150,000 Harvey OIIIN components was authorized. Evaluation of the 5 first 150,000 Harvey OIIIN improved components suggested partial qualification. This document reports and makes recommendations based on the test data for Harvey improved components as of August 31, 1963.

A program for increasing the available coolant flow at the H Reactor has been proposed and supported by documentation. This Process Improvement Transition Authorization (being written in two parts) authorizes the initiation of an immediate phase of the program designed to increase total coolant flow by about 6,000 to 10,000 gallons per minute. Part I of this PITA describes in detail the limitations and requirements peculiar to Process Engineering aspects of the proposed modifications and is presented as a separate document. This portion of the PITA, Part II, is written to establish and define conditions and restrictions in the area of Operational Physics, including loading procedures, instrumentation requirements startup checks and procedures related to reactivity effects, total control and speed of control considerations, and other physics functions. The governing criterion shall be that nuclear safety is not compromised during the proposed transition, which includes a complete shutoff of reactor flow for a limited period of time under closely monitored conditions.

BS>Declassified 6 Sep 1973. Information is presented concerning the LCRE kinetics, auxiliary systems, fuel, primary cooling system components, instrumentation, secondary cooling system, materials development, and fabrication; and SNAP-50/SPUR kinetics, fuel, primary system pump, steam generator, and materials development. (DCC)

None

Vibrational spectra provide one of the most direct methods for the study of composition and structure of simple covalently bound species. In molten salts, where the presence of complex ionic species is debated, the application of the powerful techniques of infrared and Raman spectroscopy was hampered by severe experimental difficulty. The literature from 1925 to the present time is reviewed, and unusual aspects of experimental techniques as well as tue results obtained are covered. The discussion is limited to ionic salts except where the spectra of molecular liquids make a direct contribution to the understanding of related ionic liquids. Literature references number 62. (auth)

Decay constant and modal analysis measurements were performed in a U/sup 235/-water critical assembly, and infinitemedium neutron spectra in water poisoned with a 1/V absorber were measured at various pressures and temperatures. The results were compared with theoretical predictions. Neutron penetration of water shielding was also measured. Theoretical work involved models and codes for neutron thermalization in ZrH, Be, and water. (D.C.W.)

In a study based on optimistic expectations of waste composition from future fission product separations processes, estimated costs for management of wastes from which 90 and 99% of all fission products were removed were from 70 to 80% of those for management of waste from which no fission products were removed. This cost difference is not believed to be sufficient to pay for the separation and final disposal of the fission products, which was not included in the waste management costs; hence, separation does not represent an economic route for waste management unless a substantial market for the fission products exists to pay most of the costs. As a basis for this study, it was assumed that after fission product removal the waste was identical to neutralized Purex waste in volume and composition of major ingredients. The sequential steps in the management of waste from processing 1500 metric tons per year of uranium converter fuel irradiated to 10,000 Mwd/ton were: interim storage of liquid waste, conversion to solids by pot calcination, interim storage of calcined solid waste, shipment of 1000 miles, and final disposal in a salt mine. Minimum-cost schemes were worked out involving optimum choices of interim liquid and …

The DCX-2 is a large, complex experimental apparatus. Its aim is the generation of a hot, dense plasma by the injection and dissociation of 600-kev hydrogen molecNoneular ions in a magnetic-mirror field. For facilitating this process, the molecular ions are given a long path in the machine, and the ion- pumping action of the plasma is used to maintain the vacuum. The major component systems of the apparatus are the ion source and accelerator, highvoltage power supply, magnet system, beam-injection duct, vacuum system, and dissociating arc. The design, construction, and performance of each component system, the constructional features not peculiar to any one component, and the instruments and techniques available for plasma study are described. (auth)

This document reports on: Kiwi-B(1B, 2A-CF, 4A, 4A-CF, 4B-CF, 4D, 5, 6A), NRDS activities, graphite fuel element development, metal fuel element development, materials and fabrication, and nuclear flight safety. (DLC)

None

This report addresses the absolute calibration, a technique used for calibrating shock pickups. This technique can be used for an applied motion regardless of its shape.

This report is about the Calibration of Crystal Accelerometers Used for Vibration at Temperature Extremes - extracted from minutes.

This report addresses the interagency mechanical operations croup subgroup on environmental testing.

None

Processing of multiple types of irradiated fuel elements in Purex has been proposed to the Atomic Energy Commission as a means of realizing significant savings in overall CPD operating costs for weapons programs and permitting release of the Redox plant for non-weapons programs. The process and equipment requirements for implementing a multipurpose operations program have been under study in both plant and laboratory programs for processing slightly enriched Zircalloy-clad uranium metal fuels and plutonium-aluminum metal alloy fuels. The purpose of this document is to present the results of a preliminary engineering study on the processing of irradiated NPR, E-Metal, D-Metal, and normal uranium fuels and PRIR and Pu-240 plutonium-aluminum alloy fuels and to provide process flowsheets as the basis for scope design of a project for increasing processing flexibility at Purex.

None

None

The development of equations used for determination .. starting weights of the individual mix batch constituents is presented. Experimental data resulting from batches compounded in this manner are shown for uranium loading, carbon density, and composite density of as graphitized natural uranium loaded fuel elements.

Eleven papers are presented on the chemistry of protactinium. Most of the emphasis is on solvent extraction and solution chemistry. Separate abstracts were prepared for ten of the papers; the remaining paper was previously abstracted in NSA. (D.L.C.)

Both the study and the use of extractions with highmolecular-weight amines (including quaternary ammoniums) in organic solution are increasing extensively. While equilibria have been measured in the extraction of an increasing range of acids and Aetal ions, a difficulty remains unresolved in that the amine concentration powerdependence of extraction often indicates a different stoichiometry of the complex existing in the organic phase than do limiting loading and other considerations. Nevertheless, amine extraction serves as a useful tool in studying complexes formed in aqueous systems. Process applications have progressed especially in nitrate and chioride systems, in addition to the sulfate systems first emphasized. Systematic surveys, together with information accruing from process development, have extended the ranges of extractions that can be correlated in usefully generalized patterns, which in turn should accelerate the development of new applications. However, many more areas remain to be surveyed before the many pertinent variables will have been covered. New amines of all classes have become available at commercial, development, or researchsample levels, while a few previously promising amines have become less available. Descriptions and current sources are reviewed. (auth)

Efforts were directed to the evaluation of materials, fabrication, and testing problems associated with the operation of high-temperature vapor-filled thermionic converters employing uranium-zirconium carbide emitters of cylindrical geometry. To date five of these converters have operated 5300 hr. Cell H, which had two cesium vials, was placed in operation, while final assembly of Cell K was completed. Cell H output was 56 watts at an emitter temperature of 2380 deg K. The cesium temperature optimum for maximum power was 637 deg K. A collector temperature optimum was not obtained due to cooling limitations. (auth)

Represents the latest revisions of transducers selected by WANL for test purposes.