This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the materials being irradiated, awaiting disposition and materials shipped during the month of October 1967.

From abstract: A high speed motion picture study was conducted of boiling flow in a vertical, rectangular channel at atmospheric pressure. Three different visual flow regimes were defined and described.

From introduction: The goal of engineers associated with nuclear power plants is the achievement of safe plants with low generating costs.One possible means of lowering costs is to increase the power generating capability for a single generating unit. To accomplish this, the sizes of nuclear reactors have been increased.

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A test was made to determine if there is sufficient excess reactivity in the core to override a peak xenon transient and to obtain dath for rod-worth calculations. After 149.8 EFPH's of plant operation on seed 2, there was sufficient excess reactivity to override peak xenon. Criticality during peak xenon was maintained with group III and group IV rods inserted, group I rods withdrawn to approximately -69 in., and group II rods withdrawn to approximately - 29 in. The override of peak xenon occurred 8 hr and 45 min after shutdown. (W.L.H.)

Cesium Recovery from Ores. Adaptation of the phenol extraction (Phenex) process to the recovery of cesium from ore leach liquors continued to show promise. In roast-leach tests, 98 to 99% of the cesium was dissolved from pollucite ore by roasting the ore at 800 deg C with 1.8 parts of Na/sub 2/CO/sub 3/ plus 1.2 parts of NaCl and leaching with water. More than 99% of the cesium was recovered from the leach liquor and separated from other alkali metals by extracting with 4-sec-butyl-2-( alpha -methylbenzyl)phenol (BAMBP) in diisopropylbenzene and stripping with hydrochloric acid. Santophen-1 also extracted cesium effectively, but, because of the limited solubility of the cesiumSantophen-1 complex in the diluent, the utility of this phenol in ore processing is questionable. Separation of Alkali Metals. The extraction and separation of alkali metals from nitrate solutions was studied with several different types of extractants, including substituted phenols, alkylphosphoric acids, sulfonic acids, carboxylic acids, and mixtures of some of these. With all of these reagents, cesium was extracted more strongly than rubidium, which in turn was extracted more strongly than the other alkali metals. Separation factors were higher with the phenols than with the other extractants. Acid Recovery by Amine Extraction. …

"Nuclear Science Series" on the National Research Council. Committee on Nuclear Science.

An evaluation under simulated Pathfinder reactor operating conditions of a prototype Pathfinder control rod drive (described) indicated that the unit will perform satisfactorily under all Pathfinder operating conditions. Tests were performed on individual components of the drive and on the assembled drive. (D.C.W.)

Uniform, dense coatings of alumina about 5 to 150 mu thick were applied to uranium dioxide particles 44 to 350 mu in diameter by hydrolysis of aluminum chloride vapor in a fluidized bed of the particles at 1830 deg F. The coated particles were resistant to nitric acid leaching, to oxidation in 1830 deg F air, and to thermal cycling from 6OO to 2500 deg F. After low neutron exposures, the coated particles showed excellent fission-gas retention at temperatures up to 2400 deg F in inert gas. Although not optimized in the study, the coating process appears to have commercial feasibility. (auth)

A helium coolant side-stream purification system consisting of parallel sections for radioactive and nonradioactive decontamination was designed for the proposed Pebble Bed Reactor Experiment. Primary equipment components are two gas coolers, gas heater, charcoal delay trap, CuO oxidizer, molecular sieve adsorber, and full flow filter. The charcoal delay trap is sized to provide a hold-up of 30 min for Kr isotopes. 6 hr hold-up for Xe isotopes, and 99.9% retention of iodine isotopes resulting in "decontamination factors" varying from 1 for Kr/sup 85/ to 556 for I/sup 131/. Nonradioactive decontamination will result in a steady state concentration of CO/sub 2/ in the coolant of 20.8 ppm or less. Total cost of the system excluding auxiliary equipment and containment is estimated to be .690. (auth)

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The purpose of this report is to document the evaluation and capabilities of the Core Radial Displacement Transducer. Pertinent details of the transducer history (Measurement Definition, Basic Design Evaluation Program) are included to substantiate the evolution.

An analysis is presented of the deflecting mode in an iris-loaded synchrotron waveguide which is not based on the concept of TE and TM modes as generating fields. The solutions employed are derived from the transverse components of the electric and magnetic Hentzian factors. Their use avoids the singnlarities in the field expressions for phase velocities equal to that of light, which must occur with TE and TM modes. The fundamental properties of the hybrid solutions are exposed. The lowest mode of the hybrid group is the desired deflecting mode. The exact relation between frequency, phase velocity, and geometry of the structure can be derived for the deflecting mode in the form of an infinite determinant. Transverse and hybrid solutions are tabulated. (J.R.D.)

The Zirflex process was studied extensively at Hanford in the development of technology for the interim reprocessing of power reactor fuels. The process involves the dissolution of Zircaloy in aqueous ammonium fluoride - ammonium nitrate solution. It is of particular interest at Hanford because of the impending fuel recovery from Zircaloy-clad PRTR and NPR elements. The chemical kinetics of the Zirflex reaction were not fuily defined at the end of the original studies. However, a pseudo first order reaction with free'' fluoride (fluoride not complexed with Zr) was deemed to describe the kinetics adequately for engineering calculations. The refined kinetic equation and the analog computer solution on model of the system are discussed. The results of thirty computer simulated dis solutions are also presented, and the data are used to illustrate the effects of the process variables on the Zirflex dissolution time cycle. The data from a selected few of the runs are directly applicable to the reprocessing of PRTR fuel elements in Redox. It was found that the Zirflex reaction kinetics are dependent on free'' fluoride ion to the 2.0l7 power and on H ion to the 0.457 power according to laboratory data secured after completion of the original …

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It was the practice for several years to estimate the potential dose rate to the gastrointestinal from sanitary water sources by evaluating the results of radiochemical analysis of individual nuclides. The proposed method estimates the GI tract dose from Pasco and Richland domestic water from measurements of the total beta activity, and permits more frequent and more economical evaluation of a variable source of radiation exposure. Beginning with 1964 data, the GI tract dose rate for Richland and Pasco sanitary water has been obtained by multiplying the total beta count by a conversion factor derived from the historical relationship between the radiochemical analyses and the total beta counts. Either the accumulation of more data or changes in the relative abundance of the more significant nuclides in the water may result in changes in this factor.

River temperature traverse data within and just the plant boundary are quite limited. For this report, traverse temperatures were calculated by first averaging the depth measurements vertically at each traverse point, and then weighing the average for the cross section by the depth at each point and the span between points. Calculated {Delta} T`s were determined by dividing the total reactor power level above the traverse line by the river flow, with the appropriate factor to obtain the correct units. No attempt has been made to apply corrections for atmospheric effects or the diurnal cycle.

It was the practice for several years to estimate the potential dose rate to the gastrointestinal from sanitary water sources by evaluating the results of radiochemical analysis of individual nuclides. The proposed method estimates the GI tract dose from Pasco and Richland domestic water from measurements of the total beta activity, and permits more frequent and more economical evaluation of a variable source of radiation exposure. Beginning with 1964 data, the GI tract dose rate for Richland and Pasco sanitary water has been obtained by multiplying the total beta count by a conversion factor derived from the historical relationship between the radiochemical analyses and the total beta counts. Either the accumulation of more data or changes in the relative abundance of the more significant nuclides in the water may result in changes in this factor.

Technical report. From Abstract : "The silver-1,10-phenanthroline system has been studied and the stability constants determined for the 1:1 and 2:1 complexes using the silver electrode. This known system was then used to study the complexes of 1,10-phenanthroline with other metals. The log βn values found for the over-all stoichiometric stability constants are as follows: Ag, 5.02, 12.07; Mn, 3.88, 7.04, 10.11; Cd, 5.93, 10.52, 14.30; Zn, 6.83, 12.05, 16.92. The stoichiometric stability constants determined for copper are log k2 = 6.42 and log k2k3 = 11.05."

The oscillator of the 88-in. cyclotron which is being built in Berkeley is tunable from 5.3 to 16.5 Mc. It delivers a maximum c-w power of 300 kw. At the rated doc voltage of 75 kv the resonator stores 4.5 joules of electrical energy. The transients produced by this amount of energy, during sparking, place unusual requirements upon the design of the oscillator tube. The features of the RCA 6949 which make it particularly well-suited to this type of application are discussed in this paper. Other topics covered are the oscillator anode power supply, the hard-tube modulator, protective equipment, and oscillator instrumentation.

The rf particle separator, proposed in 1959 by W.K.H. Panofsky and now in preparation for the Brookhaven Alternating Gradient Synchrotron, required a rf structure which gives a transverse impulse to a passing relativistic particle. In order to produce an accumulative transverse deflection of a traveling charged particle with an electromagnetic field, it is necessary that the field contains a synchronous component and in principle, waveguides and cavities are equivalent with respect to the particle dynamics. It was pointed out by H.G. Hereward, that the electric and magnetic deflection of a transverse electric mode (i.e., with no electric field component parallel to the direction of the particle velocity) cancel exactly at all particle velocities. The deflecting force of a transverse magnetic mode on a synchronous particle with the velocity v is proportional to the factor 1-(v/c)2 and vanishes therefore in the case of relativistic particles.

The Fuel Cycle Program is an integrated program of investigation in the Vallecitos Boiling Water Reactor (VBWR) and other facilities to improve the technological limits of boiling water reactors.

A helium coolant side-stream purification system consisting of parallel sections for radioactive and non-radioactive de-contamination was designed for the proposed Pebble Bed Reactor Experiment. Primary equipment components are two gas coolers, gas heater, charcoal delay trap, CuO oxidizer, Molecular Sieve adsorber, and full flow filter. The charcoal delay trap is sized to provide a hold-up of 30 minutes for Kr isotopes, 6hr hold-up for Xe isotopes, and 99.9% retention of iodine isotopes resulting in "de-contamination factors" varying from l for Kr85 to 556 for I131. Non-radioactive de-contamination will result in a steady state concentration of CO2 in the coolant of 20.8ppm or less.