Introduction: In order to determine the relative corrosion resistance of welded mild and stainless steels in Redox Stream IAW neutralized to pH 0, 2, and 10 a test program, described below, has been carried out.

The following report is based on the observations made during a visit to the Oak Ride National Laboratories of their Redox Pilot Plant equipment.

The following report describes polarographic methods that determine saturated aliphatic carbonyl compounds.

Summary: "This report investigates photographic methods of measuring beta radiation and includes a study of temperature effects on these measurements. Experimental data are submitted to show that an increase in film temperature before and during beta irradiation causes a definite increase in density for the same dosage. Recommendations drawn from experience gained in the experimental works are offered."

The following report discusses the presentation of preliminary density and viscosity data which may explain whether higher viscosities of the Deo Base-TBP systems, and a change in density differences between the two phases will lead to unsatisfactory column operation.

The following report provides data collected during an investigation in the Columbia River. The purpose of this investigation was to research the radioactivity present in the bottom-living organisms of the river.

From introduction: "Since plutonium is manufactured at the Hanford Works, a study of its effect on biological materials is important. To determine the amount of plutonium deposited in a biological sample, it is necessary to have an accurate method for extracting plutonium from these samples. Some of the different methods for plutonium assay are reviewed and given in this paper."

Report describing alternative methods for depleting a large turnings inventory in a short period of time.

From introduction: "This report gives the results of a 1000-hour corrosion test of SAE 1010, low carbon steel, in synthetic Redox waste solutions...The present test was designed to obtain corrosion rates for waste solution temperatures of 180 F, 200 F, and 220 F in solutions neutralized to pH values of 11, 12, and 13.

This report examines the failure of two 18-8 grade stainless steel gate valves used in sulfamic acid and determines the cause of the failures through a series of tests.

Introduction:"A corrosion test program to determine the effect TBP process streams, which contain chlorides, have upon the corrosion resistance of several construction materials, was completed. Data are presented on the performance of Carpenter 20, T-309SCb, T-347. T-316 and tantalum in the RAF and RAW process streams and on the performance of titanium and zirconium in the RAW stream."

This report provides data on production test 105-329-P and solid graphite samples used to analyze damage obtained from controlled natural erosion tests. The data provided will help establish current ideas on the status of filler block graphite and interpretation of the data will assist in establishing pile operating temperature limits based on stored energy.

The following report describes the procedures developed for the x-ray photometric determination of uraniuim in metal oxides and sludge and compares results, precision, and length of time of analyses by the General Electric X-Ray Photometer with analyses by the present titration method.

Summary: "This investigation showed that a sound , weather-resistant coating can be applied to uranium that the surface to be plated is cleaned and etched properly. Using the proposed two-bath plating method at 80 C., a four-mil nickel coat can be deposited in thirteen hours."

From introduction: "The test was performed to gain knowledge which would be useful for evaluating and improving currently planned methods for the design and construction of high density concrete shielding."

The following report discusses laboratory investigations of the suitability of some commercially available limestone for neutralization of slightly acidic distillates.

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."

From objectives: "The objectives of this investigation were to evaluate the hydraulic forces in the pulse column, and determine their effects on pulse column design."

The following document analyzes plutonium in urine which uses nuclear track film for evaluation of the quantity of separated plutonium.

Report describing "the effects of variable graphite conductivity and of the gas layers in the lattice" under the assumptions that "graphice conductivity varies as a power of the distance from the center of each cell" and "uniform distribution of heat sources" - from abstract.

The basic scheme for processing power reactor fuels at Hanford includes the removal of inert endfittings ("hardware") from the active sections of the fuels. Within Hanford Laboratories, research and development studies have been in progress on various types of saws which might be used for hardware cutoff. In the initial phase of the program, high-speed saws were investigated; more recently, studies on low speed saws have been conducted. This report summarizes the high speed saw studies and includes information on abrasive wheels, diamond wheels and metal "friction" blades which cut by actually melting metal ahead of the saw blade. At the completion of the low speed saw testing program currently in progress, basic saw types will be compared and the saw type to be included in the reprocessing complex will be selected.

The first series tests in the KER-REP-1 loop proved that a fisssion product contaminated loop could be decontaminated to a safe level for contact maintenance. The second series of tests ere scheduled for a more thorough evaluation of these processes includes specific decontamination factors, process corrosion rates, loop activity reduction factors (loop decontamination factors), and any preferential decontamination which may be present.

Considerable interest has developed in the use of ion-exchange in the nuclear energy field in the last decade. Aside from the obvious use of providing demineralized coolant water for reactors, the projected uses of ion-exchange include the recovery of fission products from aquaeous waste streams and the separation and purification of fissionable materials from spent reactor fuels. The latter process may be incidental to the over-all operation, as is the case with the Purex anion exchange facility, or it may be the prime separation process, as may be the case in the recovery of Pu or U from spent power reactor (PRTR) fuel elements.

A report which is the ninth report of the research and development activities of the radiological sciences department, Hanford Works, which includes some items charged to control but include for for general interest.