Report regarding Hanford Laboratories' 300 Mwe fast supercritical pressure power reactor. This includes descriptions of the plant and reactor, their operations, safety systems, and plant economics. Appendices begin on page 107.

The stability of fluorothene (polytrifluorochloroethylene, Kel-F) to gamma radiation has been investigated to estimate the probable life expectancy of fluorothene equipment exposed to Purex process solutions. Samples of fluorothene were exposed to total gamma radiation dosages up to 10 degree R. The results of these tests substantiate the findings reported by Sisman and Bopp in their compilation of data on the affects of radiation on plastics.

Removal of particles from air is discussed in terms of three classes of filtering media--air-sampling, respirator, and air-cleaning. Plots of efficiency versus filtering velocity are presented. The pressure drop characteristics of the filters are discussed in terms of initial pressure drops of the clean filters, variations in pressure drop of the individual filters, and comparison of loading rates.

From introduction: "The development and demonstration of the natural uranium reprocessed plutonium cycle in power reactors is an important phase of the peaceful applications of nuclear energy."

Report regarding the calcination of full level Purex and Redox waste carried out "in a remotely operated pilot plant consisting of a radiant-heat spray calciner and a pot calciner and their associated off-gas equipment" (p. 4). This contains details of the calcination, effects on the waste, and difficulties encountered.

The results of this investigation indicate that maximum electric power generation can be obtained by selecting the turbine steam temperature within a range of plus/minus 30 degrees C. from an "idealized" steam temperature. This "idealized" steam temperature is shown to depend primarily on the maximum permissible uranium temperature. The minimum available condenser temperature and the temperature rise of the coolant in the pile effect the selection of the turbine steam temperature to lesser extent.

This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).

Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.

This document is a sequel to HW-30226, "Steady State Temperature Distribution in a Solid Slug." A primary feature of the present as well as the former paper is a treatment of the stand heat flow equation in a manner which accounts accurately for the dependence of the thermal conductivity, K, on temperature, v.

Various non-linear calculations for heat conduction in an istropic, homogeneous medium are presented.

Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.

Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.

In 1949 Barad presented two solutions to the general diffusion equation. Basic in both solutions is the assumption that in very stable atmospheres a point source may be replaced by a vertical area of uniform concentration at a short distance downwind. This vertical area is considered to exist at the distance at which the plume finally "levels-off" and assumes a flat ribbon-like appearance. In addition if the distance over which diffusion takes place is limited to one or two miles and if only the stable atmosphere with its narrow range of eddy sizes is considered, the average diffusion co-efficient (K) has a signficance which it does not have in the case of neutral equilibrium.

Three types of stainless steel (309 SCB, Carpenter 20, 304-L) were exposed to both the liquid and vapor phase of each of three types of solutions. The time of exposure totaled ten days during which the specimens were cleaned and weighed periodically. The three synthetic D-12 waste solutions contained respectively chrome-high chloride, chrome-low chloride and high chloride sans chromium. The solutions were renewed at each weighing.

Report describing the thermal hydraulics facilities at Hanford Laboratories as well as its operation, equipment, and systems.

Report describing the experimental facilities of Hanford's Thermal Hydraulics Laboratory, its equipment, personnel, operating schedules, and safety procedures. Appendix begins on page 49.

Series of isothermal transformation studies for improvement in fabrication and reactor performance of uranium fuel elements.

Report describing "computer techniques used in the simulation and parameter determination, how the data were prepared for inclusion in the computer simulation, (and) methods used in presenting the results" (p. 3-4).

Report discussing the dissolution of simulated fuel cores. Equipment and procedures are discussed along with significant characteristics of the core materials.

From introduction: "Five appendices, each of which pertains to a separate phase of the Filtration of Radioactive Aerosols by Glass Fibers program."

The investigation to be described in this paper was one of several undertaken to resolve a curious discrepancy that had arisen in measurements of the diffusion length of graphite. Those diffusion lengths measured with the graphite layups of 100 Area piles were three to six centimeters higher than the value obtained with the Hanford Standard Pile. The fact that the 100 Area structures of the order of 40 ft. X 40 ft. X 30 ft, not including reflector, approximated an infinite medium, whereas sigma piles are of the order of 8 ft. X 8ft. X 10 ft., suggested the possibility that the diffusion length obtained by mensuration of relative fluxes and application of the conventional equations depended in some way on the size of the medium. Therefore, in order to determine if such a dependency actually exists, it was proposed to erect a series of graphite stacks of different dimensions and to make diffusion length measurements in each.

The preparation of radioactive metallurgical specimens for microscopic examination is one of the responsibilities of the Radiometallurgy Sub-Unit. An abrasive cut-off machine development program, based upon a previous experimental model, was undertaken to provide a method for sectioning of irradiated materials without undue personnel exposure or spread of contamination and finally to provide data for the design of an abrasive cutting unit for use in the work cells in the Radiometallurgy Building. A horizontal-feed type set-off machine, powered by a 7 1/2 hp motor with V-belt drive, has been developed for the submerged sectioning of irradiated uranium and is currently being used successfully to obtain samples for metallurgical, chemical and physical investigations without excessive personnel exposure or spread of radioactive contaminates.

In obtaining the results reported here a double focusing magnetic type spectrometer was used. Momentum spread was about 1%, and in most cases 2560 counts per point were taken. An end window Geiger tube was used as a detector. The window was of mica with areal density of 1.6 mg/cm2.

Laboratory studies have shown that the double salt, CaF2-PuF4, can be precipitated by rapid addition of hydro-fluoric acid to solutions containing 25 to 75 g Pu/1, caleium equimolar to plutonium, and 1 to 10 M HNO3. The precipitate, which is subsequently washed with water and dried to 300 degrees C in dehumidified, deoxygenated argon, can be reduced thermally by calcium to give high yields of plutonium metal.