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.

Apparent excessive concentrations of atmospheric contamination which were reported to be associated with an inert-gas-shielded consumable electrode arc wielding operation were studied to evaluate the potential health hazards. A study was made of the concentrations of metal fume and gaseous products of the operation as well as the spectrum of ultraviolet radiation. Recommendations for necessary controls were made.

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."

A preliminary report has shown the potential importance of organic reactor coolants to Hanford technology. The salient points are complete avoidance of corrosion problems and accomplishment of DPR performance with low pressure technique. The recommendation of the report that loop tests be made at Hanford is to be acted upon by Recirculation Technology Unit as soon as organic coolant material is received. To insure starting this experimental work fully abreast of the information available, a trip to sites working with organic coolants was made. Specifically, data were sought on practical details of design for handling organic coolants, heat transfer and fouling characteristics, corrosion of materials, and hazards of handling organics.

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.

Report describing the results of the cupferron extraction-copper spark method in determining the impurity elements in plutonium metal. This was required the 234-5 Project analytical program.

Report describing methods of determining trace impurities in plutonium in connection with the Metal Fabrication Process. The methods included are the cupferron extraction-copper spark method and the direct copper spark method.

Facilities are to be designed for installation at Hanford for the reprocessing of irradiated, low enrichment fuels from non-production reactors, see Reference 1 and 2. The initial design of the processing facilities is to be based on processing the fuels discharged from the Dresden, Yankee, Piqua, Pathfinder and Shippingport (blanket elements only) reactors. Properties of the fuels and cladding make it impossible to completely process them in existing equipment, although the separation and decontamination can be performed in existing facilities once the fueks have been placed in solution form.

The measurement of a alpha-particle energy has been used by many radiochemical laboratories for the identification and analysis of alpha-active radio nuclides. The use of the total-ionization method for alpha-active radio-nuclides. The use of the total-ionization method for alpha energy in ionization chamber in which the alpha particle loses all its energy in ionization of the chamber gas. Collection of the electrons thus formed generates a voltage pulse across the chamber capacity which is proportional to the alpha particle energy. This pulse is then amplified using a suitable linear amplifier and fed to a pulses as to amplitude; the information is then recorded or stored. Since the pulse amplitude is proportional to the alpha energy lost to the chamber gas, the pulse height analysis can be used to estimate the energy of the alpha particles and in the case of several alpha emitters of different energies, the relative abundance of the alpha emitters can be determined. An alpha energy analyzer system using the ion collection method has been fabricated for use in radiochemical laboratories required to perform a large number of alpha energy determinations. This report describes the operation, maintenance, and application of this alpha energy analyzer system.

The following report observes infrared measurements in the region of OH bands, the C2O band vicinity, the low frequency end of the spectrum, and the region of the UO2 band on the system hexone - water - uranyl nitrate.

From introduction: "The purpose of this report is to summarize some of the observations on the dispersion and rate of disengaging of liquid-liquid systems and suggest some possible lines of future work."

Extraction systems involving chelating agents are widely used in radiochemical separations on a control basis due to the economy in time and equipment. In the case of waste streams, the element of interest is, by definition, at a very low concentration in the presence of gross fission product activities. The resultant large sample size necessary for a reliable analytical results creates a marked radiation hazard to laboratory personnel.

The following report records a total of forty-nine graphite core samples that have been bored from process tube blocks in the Hanford piles with the intention to provide results to indicate that core boring is an entirely practical operation over bore scraping in obtaining powder samples.

The Hanford water treatment plants were operated for a number of years with alum as a coagulant and activated silica as a coagulant and a polyacrylamide as a filter conditioning agent. (other polyelectrolytes may be used.) Sufficient time has elapsed to make a comparison of the two methods of operation valid and useful. Such a comparison is the purpose of this paper.

A new type of flexible hose connector consisting of a Teflon tube enclosed in a stainless steel wire braid sheath was proposed for use on 105-C rear face in late 1954. A test was initiated to determine the suitability of Teflon, and specifically Fluoroflex Teflon compound for rear face application. Probable useful life limit is estimated at 10⁶ R, which would be attained in about three years in contact with fresh effluent.

This report summarizes the research and development work carried out during March, April and May, 1959, for Budget Activity 2790 - Separations Development for Non-Production Reactors, The effort on Activity 2790 will enable Hanford to begin reprocessing in January, 1962, the fuel elements from power reactors which employ depleted or slightly enriched uranium fuels.

The construction and operation of a fission gas generator, containing about 25 grams of uranium in the form of a powder with a high specific surface, are described in detail. The purpose of the work discussed in this report was to examine the feasibility of producing, separating, and assaying samples of Xe135 in preparation for a proposed measurement of the neutron cross section of this isotope. Krypton and xenon are separated by selective adsorption on charcoal at reduced temperature while iodine is removed by charcoal sorption at room temperature.

This report discusses properties and data regarding the neutralized and concentrated aqueous waste produced during studies of the tributyl phosphate (TBP) solvent extraction process.

Introduction: "The observations reported in this document were obtained by C.H. Pitt during his assignment to the Corrosion Group September through October 1951. The tubes examined were: 1.) 0893-F Discharged for corrosion examination after leaking; 2.) 1488-DR Discharged to determine caused of obstruction; 3.) 2276-D Discharged for corrosion examination; 4.) 2376-D Discharged for corrosion examination; 5.) 1185-H Discharged to evaluate the effect of magnesium front dummies."

The dependence of the resonance integral for thorium upon geometry and thorium temperature has been determined through reactivity coefficient measurements performed in the Hanford Test Pile. The geometry dependence was investigated using thorium cylinders of various diameters in the form of solid elements and shells. The temperature dependence (Doppler broadening) was studied by heating thorium elements and permitting them to cool while observing the change in pile reactivity.

Reactivity measurements conducted in the Hanford Test Pile are interpreted to yield resonance integrals for uranium, uranium oxide, thorium and thorium oxide. The experiments were made using cadmium filters and are discussed in terms of the multiplication factor of the Hanford Test Pile.

Abstract: "A method has been devised and successfully used for marking a leaking pile process tube prior to its removal from the pile, such that subsequent location of the leak is more easily accomplished. An acetone solution of Testor's Dark Red Airplane Dope is poured into the suspect tube. The solution leaks from the hole and stains the surrounding area a light pink. To date the method has been used on tubes 3573F, 0486F, 0867F, and 3670F."

Several tests are being performed and others being planned to investigate the role of heat transfer in corrosion processes. These tests are measuring both corrosion rates of metals (Zr-2 and X-8001 aluminum) under heat transfer, and the temperature rise associated with the buildup of the corrosion product. A brief description of these tests is given in this report.

A report which intends to acquaint the reader with the planning of the radiochemical laboratory designed for the analytical control of the radiolanthanum process and to define the terminal status of the design of this laboratory and its equipment.