Shipment of radioactive wastes in shielded transfer casks is a continuing practice between the 300 Area and the 200 Areas. However, the Waste Solidification Engineering Prototypes (WSEP) located in 324 Building, 300 Area, require the transfer of significant quantities of radioactive wastes. Two new 30-ton casks are being placed in service to accommodate the increased number of shipments. The purpose of this report is to document the design criteria, tests and calculations performed on the casks and modifications to the original cask design to insure its safe use. The design criteria was developed in January 1963 by an ad hoc committee comprised of representatives of the Chemical Processing Department, Hanford Laboratories, and Construction Engineering and Utilities of General Electric Company. The various tests, calculations and modifications of the cask were conducted by the Chemistry Department of Pacific Northwest Laboratory.

As a result of an AEC directive, a review has been made of the disposal of chemicals to the Columbia River by 100-N to determine if any water pollution hazards exist. The search revealed that no chemicals are released continuously in hazardous concentrations; that three cases exist where hazardous concentrations might be released intermittently under worst-case conditions; that two cases exist where intermittent releases result in questionable conditions; and that two cases exist where accidental release from storage might result in hazardous conditions. Recommendations for corrective action are given in all cases.

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

This report gives an analysis of the audit data obtained during the last half of 1965 at eight transfer stations: L9 plutonium product, K6 uranium product, F15 salt waste, D5 dissolved feed, F18 utility waste, G8 organic wash waste, R8 organic wash waste, and U3 laboratory waste. Two ways of improving the Purex quality control program are described.

Shipment of radioactive wastes in shielded transfer casks is a continuing practice between the 300 Area and the 200 Areas. However, the Waste Solidification Engineering Prototypes (WSEP) located in 324 Building, 300 Area, require the transfer of significant quantities of radioactive wastes. Two new 30-ton casks are being placed in service to accommodate the increased number of shipments. The purpose of this report is to document the design criteria, tests and calculations performed on the casks and modifications to the original cask design to insure its safe use. The design criteria was developed in January 1963 by an ad hoc committee comprised of representatives of the Chemical Processing Department, Hanford Laboratories, and Construction Engineering and Utilities of General Electric Company. The various tests, calculations and modifications of the cask were conducted by the Chemistry Department of Pacific Northwest Laboratory.

This report describes EG&G activities in support of the NTO Test Cell A Program for February 1966. Details with respect to the various tasks included in our scope of work are discussed in succeeding sections and appendices. At Test Cell A, the NRX/EST test series continued with the performance of Experimental Plans IIA, IIB, and IIC. EG&G personnel maintained the test cell instrumentation and controls systems in a run condition and added new channels for the next experimental plan. This will be the last publication of the monthly EG&G/NTO progress report. The contractual agreements of the EG&G Electronics Support Services contract require a monthly technical and fiscal report. Reporting shall be in the following categories: (1) TCC; (2) TCA; (3) ETS-1; (4) R&E MAD Buildings; (5) Common Operational Support; (6) Miscellaneous; and (7) Central Support Shops. In addition EG&G will submit a weekly highlight report to SNPO-N with distribution to the users.

This report details activities of the N-Reactor Department for the month of February 1966.

This document presents a survey of the EG&G NRDS photographic operation in four major sections and includes the work scope, procedures, some technical backgrounding and operational information. Two sections, Instrumentation and Photo Systems, include the areas of direct responsibilities while a section on Film Handling and Coordination and a section covering special information, pertinent to the project, are included to adequately complete this survey. The photographic group is housed in two trailers within the control point area at NRDS and from these trailers provides photographic support at a number of locations. Four camera bunkers, three camera towers, a kinescope system, a microfilm system and remote camera controls comprise the facilities that the group maintains and operates outside these trailers. The work load includes major items such as: motion picture coverage of the nuclear rocket engine tests, data record microfilming, kinescope recording, and documentary coverage of the company related operational responsibilities. In addition, a number of minor photographic services are extended, when required. The nature of the work, because of its importance within the research and development efforts at NRDS, requires optimum quality and efficiency throughout. The many procedures outlined here have been designed to satisfy these requirements.

The study of focusing aid techniques was conducted to evaluate the performance and convenience of the split image, projection, and ground glass techniques used for focusing oscilloscope cameras. Specifically, the study was intended (1) to determine the usefulness of projection-type focusing aid devices now used on EG&G Type 3171 cameras, (2) to lead to recommendations for the most satisfactory device for use with the new LC-4 type camera, and (3) to evaluate the usefulness of such devices for production-line focusing of EG&G Type 850 cameras. The study included a brief theoretical evaluation of each focusing method and a statistical determination of actual performance. The primary tests were made using a simulated oscilloscope trace to insure reproducibility. Comparisons of the results were made on a Tektronix oscilloscope to confirm validity of the trace simulation. Most of the tests were made with an LC-4 camera because the Nikon lens used in the LC-4 camera will be used in future 3171 cameras. A few experiments were conducted to confirm the correctness of applying the LC-4 camera results to unmodified 3171 cameras. A special split image focusing aid developed at Lawrence Radiation Laboratory (LRL) for the LC-4 camera was used in the split image …

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Declassified 30 Aug 1973. Progress on the couple design, testing and reliability, optimization of material fabrication, and advanced technology is reported. (TFD)

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This report details an interlaboratory cooperative study undertaken on neutron flux spectral measurements, calculations, and data correlation for reactor irradiation and physics study by various sites. The Testing portion of this study was the irradiation of a wide variety of flux monitors in a special snout capsule holder. The attached sketch shows the capsule holder design, facility design, and the capsule position in relation to adjacent process tubes. A summary of the irradiations performed is provided.

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