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.

The following documents are progress reports that follow chemical research studies in subjects such as ruthenium tetroxile distillations, extraction-scrub studies of zirconium and niobium, and oxidation of plutonium and stabilization of plutonium(VI) during extraction of IAF solutions.

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."

From introduction: "This report presents the apparent viscosities of supernate-sludge slurries prepared synthetically to simulate the conditions known to exist in the waste storage tanks, but with fission products and plutonium absent."

From statement of objectives: The purposes of the work described in this report are to provide data useful for designing and operating the dissolver solution clarification equipment to be installed in the Redox production plant.

Report describing how the neutralized aqueous waste from the TBP Metal Recovery Process will be concentrated by evaporation to minimize the requirements for underground storage tank capacity.

It is desirable that a reactor exhibit a self-regulating effect. If this were not true any disturbance to the reactor would result in a continual increase in the magnitude of the disturbance and the reactor would be unstable. In this investigation the reactor is considered to have two reactivity feed-backs: metal temperature and water temperature reactivity effects. These two variables through a metal temperature coefficient and water temperature coefficient determine not only the reactor stability but also determine many operational characteristics.

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.

Zirflex cladding waste is to be neutralized to pH 10 before transfer to waste storage tanks. This treatment causes the precipitation of zirconium oxide or hydroxide, which may lead to flow difficulties during transfer. The purpose of this investigation was to determine the physical properties and flow characteristics of the neutralized slurry to assist in the selectin of satisfactory transfer equipment and storage conditions.

The purpose of the Analytical Laboratory Manual is to assemble the basic procedures to be used for the analyses of materials employed within the Fuels Preparation Department. The methods appear in detailed steps suitable for laboratory use. This document replaces the "Essential Material Analytical Manual, " HW-25375 and "Metal Preparation Analytical Manual," HW-30862.

This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating personnel may be used to provide analytical coverage on those routine analyses that are needed on around-the-clock basis with a savings of both time and money.

From abstract: "The purpose of this investigation was to establish basic rates of formation of chemical films deposited on aluminum surfaces from water flowing over such surfaces. It was desired to obtain specific information, within certain ranges, as to the influence of temperature, water velocity, and type of aluminum on the rate of film formation."

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.

One of the UO2 fuel element designs proposed for use in the PTRT is the nested tubular concepts. This configuration compromises a central fuel todo surrounded by two concentric tubes of fuel (see sketch, appenx I.) . These UO2 shapes are to be jacketed in the Zircaloy and must be separated from each other and the procuresses tyvm vt annular spaces for the passage of coolant. The annuli are established and and maintained by the longitudinal ribs on the outer surface of all three jacketed fuel elements.

Two water quality control labs are being provided for the the NPR. One, a "cold" lab, is located in the183 Building adjacent to the control room. Its primary purpose is to provide facilities for quality control of the output of the filter plant and the demineralizer plant. The other, a "hot" lab, is located in the 190 Building. Its primary purpose is to provide facilities for the quality control of the primary and secondary coolants, and the moderator coolant.

Early in the U.S. gas-cooled reactor program, it was recognized that a considerable research and development effort would be needed to utilize the full potential of gas cooling. Hanford Laboratories contribution to this program began in August, 1958 when a graphite studies program was initiated. The primary objectives of the Hanford program are: (1) to secure improved knowledge of the reaction of gas coolants with protected and unprotected graphites over a range of conditions of practical interest for gas cooled power reactors with tolerable damage to the graphite moderator.

From introduction: "In this report an attempt was made to summarize the results of recent research on the effective height of smoke stacks. In this summary attention is paid only to the case in which the density of the stack effluent is the same as that of the surrounding air."

Report discussing changes in parameters regarding Sutton's diffusion hypothesis, which is used in calculations of plant stacks' atmospheric pollutant distribution. An explanation of the computation and results are given.

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.

Photographic observations of the behavior of uranium dioxide at high temperatures are of great value in designing and evaluating fuel elements. This paper reports the growth of uranium dioxide crystals by vapor deposition during out-of-reactor and in-reactor experiments.

It is well known that neutron damage generally causes increases in the yield and ultimate strength and a decrease in ductility of a metal. There is a continuing program at HAPO to determine the extent of these changes in Zircaloy-2 as functions of integrated neutron exposure, irradiation temperature, and reactor atmosphere. Three investigations from this program will be described and the results summarized. The first investigation deals with both annealed and cold worked Zircaloy-2 irradiated at approximately 50 C. and the other two investigations deal with annealed Zircaloy-2 irradiated at approximately 100 and 280 C respectively. In each investigation tensile testing was performed at room temperature.