Preliminary design concepts are presented for a wire scanner for experimentally evaluating spatial variations of neutron flux in the SM-l reactor core. Results of a literature search and determination of optimum criteria for flux mapping the core in minimum time dictated requirements for design concepts and specifications. The utility of both manually instrumented and automatically instrumented wire scanners was analyzed with respect to rapidity of measurement, selectivity of detector location, cost, value of data, plant downtime, and additional factors. (auth)

This report discusses an allocation of $1,320,000 of 02 Reactor and Metallurgy funds which was previously made to the Pacific Northwest Laboratories. The Process Technology work order support which N-Reactor Department expected to provide during FY 1966 was estimated. The R&D allocation was based on the 189 budget proposals which were prepared early in 1965 and program identifications were provided. The integrated five year research and development program was subsequently formulated with the assistance of Pacific Northwest Laboratories and research and development program missions were defined. Revised 189 proposals have been prepared and the work is being reprogrammed in accord with the mission plan. These program discussions outline research and development needs and BNW allocations in accord with the mission requirements. The level of R&D is maintained at the original level specified in reference 1 ($1,320,000), with the exception that $130,000 for the payment of offsite irradiation unit costs is now held within NRD.

This document reports the result of an engineering analysis and evaluation of the Zone Temperature Monitoring System. The main function of the system is to protect the reactor from localized increases in reactor power which would be reflected by increases in the tube outlet temperatures in the affected zones of the reactor. This function has been implemented by the installation of immersion temperature detectors on 109 representative process tubes. The signals from the detectors will be monitored and will automatically annunciate, initiate a power setback, or initiate a reactor scram should the outlet temperature of one, two, or three tubes exceed an adjustable, preset limit.

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On September 29, 1965, at 0150 a purposely defected partially molten fuel rod in the rupture loop test facility of the PRTR reactor failed in an unexpected manner. The rupture which resulted in a loss of about 30% of the UO{sub 2}-PuO{sub 2} fuel from the rod was accompanied by the formation of a hole of approximately 1/2 inch diameter in the surrounding process tube. The subsequent flashing of the highly contaminated superheated water, released a fission product aerosol to the containment vessel atmosphere. This release resulted in about half of the noble gases reaching the containment vessel atmosphere. About 1 percent of the radioiodine and a somewhat smaller fraction of the solid fission products entered the containment vessel atmosphere. A subsequent radiochemical study provided detailed information on the behavior of some 15 fission products and of plutonium in their movement, following the rod failure, through the various liquid and gaseous systems of the reactor and its containment vessel. The ratios of the fission products (other than the noble gases) which were release to the containment vessel atmosphere were not far different from those in the fuel rod showing that relatively little fractionation occurred in the processes of dis- solution …

This report, from the Chemical Processing Department at HAPO, discusses the following: production operation; purex and redox operation; finished products operation; maintenance; financial operations; facilities engineering; research; and employee relations.

The small critical mass of plutonium which limits charge size, coupled with its value necessithting quantitative recovery from all residues, makes the direct recovery of mechanically entrapped plutonium from casting skulls and oxidized turnings an economic necessity. The newest method used at the Los Alamos Scientific Laboratory for the direct recovery of entrapped plutonium involves mechanical stirring and vibration of the plutonium melt to physically break up to spongy skull and oxide film, thus allowing the heavier molten plutonium to settle out at the bottom of the melt. The recovery equipment and procedures are described. (auth)

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