Definite identification has been made of an isotope of the element with atomic number 98 through the irradiation of Cm{sup 242} with 35 Mev helium ions in the Berkeley Orocker Laboratory 60-inch cyclotron. The isotope which has been identified has an observed half-life of about 45 minutes and probably has the mass number 244. The observed mode of decay of the 98{sup 244} is through the emission of alpha-particles, with energy about 7.1 Mev, which agrees with predictions, and other considerations involving the systematics of radioactivity in this region indicate that it should also be unstable toward decay by electron-capture. The chemical separation and identification of the new element was accomplished through the use of ion exchange adsorption methods employing the resin Dowex-50. The element 98 isotope appears in the eka-dysprosium position on elution curves containing 4.6-hour Bk{sup 243} (formed by a d,n reaction in the same bombardment) and the bombarded Cm{sup 242} as reference points; that is, it preceded berkelium and curium off the column just as dysprosium precedes terbium and gadolinium. The experiments so far have revealed only the tripositive oxidation state of eka-dysprosium character but practically no attempts at oxidation to possible IV and V states have …

As a part of the five year budget study requested by HOO-AEC, a study of separations waste storage requirements for this period was made. This study took into consideration the variant estimates of amount of irradiated uranium to be processed, and the goals in the waste reduction research and development program. The conclusions of this study were at variance, to some extent, with prior studies. Interest has been expressed in publication of this study to permit independent assessment of its bases and assumptions.

Mechanization of the 300 Area slug canning facilities is required to obtain uniform high quality product and to eliminate variables introduced by the human element. The work to be covered by this brochure will cover requirements for mechanization of only the operations occurring within the aluminum-silicon canning bath: can and cap preheating and wetting, canning assembly, and quenching operation. Briefly, this machine will be required to insert a prepared uranium slug into an aluminum can and close the can opening with an aluminum cap. All assembly operations are to be carried out underneath a molten bath of aluminum-silicon bonding alloy. The uranium slug is preheated and prewetted before being transferred to the assembly furnace; however, the process must be so timed that proper preheating and wetting is attained before the slug is inserted. After assembly the completed canned slug is transferred to the quenching station, where the components are to be firmly held together until the molten Al-Si has frozen, forming a homogeneously bonded assembly.

This document consists of three photographs of ruptured fuel elements. The position, date charged, date failed, exposure, power, lot and failure type are given for tube 3655-KE, tube 4153-KE, and tube 3849-KE. (GHH)

Up to one hundred ribless zirconium process tubes are to be installed in C Reactor, and necessary reactor equipment modifications made to permit routine charging of these tubes with self-supported natural uranium fuel elements. This test authorizes continued loading in these tubes until authorized by process standards or until it is deemed impractical to convert C Reactor to this geometry.

Since the installation of Ball 3X equipment on the older reactors, several inadvertent ball drops have been experienced, many of which have required considerable recovery time. Furthermore, it is very probable that these recovery times be significantly increased subsequent to the proposed installation of air accelerated vertical safety rods. Because of this, interest has been expressed by reactor operations personnel toward provision of a ball recovery system which would substantially reduce these outages.

This document presents a summary of work and progress at the Hanford Engineer Works for August 1955. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project Sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Sciences, Employee and Public Relations, and Community Real Estate and Services departments have sections presenting their monthly statistics, work, progress, and summaries.

This report discusses a proposal to measure the corrosion rate of aluminum-clad DOE elements in deionized water in one of the KER Loops at the highest obtainable surface temperatures under conditions where the bulk water adjacent to the elements is saturated with aluminum corrosion product. This will determine whether in-reactor corrosion may be reduced by controlling the aluminum concentration in the water and also provide corrosion data in deionized water at higher temperatures than is now available. A thermocouple slug will be included.

The feasibility of adding four ``corner`` rods to the K Reactor`s 20-rod HCR system is being investigated. It is necessary to compare the costs and production gains of this method for gaining additional reactivity and heat distribution control with other supplementary control systems. This document presents the results of an investigation of the production gains that could be made by adding four rods to the KE Reactor HCR system.

Sections of the dummies furnished by Radiological Engineering, Process Reactor Development Operation were machined into 1/4 inch diameter by 1 inch long cylinders and irradiated in the Quickie Facility at F area. The pieces were discharged directly into a holder one foot from the Beckman chamber. The transient time from in-pile to the chamber is approximately 30 seconds. The readings were taken using a Beckman chamber, Beckman Micro-Micro Ammeter and Recorder. This system has been calibrated with Co{sup 60} sources obtained from the Oak Ridge National Laboratory. We are including data taken from a sample of 61-S and 99.998 per cent aluminum which may be of interest.

Fission product distribution, fission product activities, and decontamination factors are terms of general usage in the Chemical Development Section. Specific values for some of these terms have been based upon data procured several years ago. In many cases more accurate basic numbers are now available. This report sets forth in tabular form detailed information on fission product activities as a function of decay time for certain conditions. It attempts to quality the use of the theoretical curie as a unit of activity to a unit having a more direct practical significance, the ``countable curie.``

Increases in process water flows will be needed as the current program of increasing pile power levels continues. The future process water flows that will be required are known to be beyond the present maximum capacities of component parts of the water system. It is desirable to determine the present maximum capacities of each major component part so that plans can be mode for modifications and/or additions to the present equipment to meet future required flows. The apparent hydraulic limit of the present piles is about 68,000 gpm. This figure is based on a tube inlet pressure of 400 psi, a tube flow of 34 gpm, and 2,000 effective tubes. In this document the results of tests and calculations to determine the present maximum capacities of each major component part of the 100-B water system will be presented. Emergency steam operated pumps will not be considered as it is doubtful of year around operation of a steam driven pump could be economically justified. Some possible ways to increase the process water flows of each component part of the water system to the ultimate of 68,000 gpm are given.

An analysis is made of the heat produced by the absorption of gamma rays in a sample placed into a reactor. It is clearly shown that enormous local (space) variations in gamma flux exist in current reactors. An application to the Hanford reactors is treated in some detail. Although the estimates obtained may be good to but a factor of two, it is clearly shown that in most cases the major portion of the heating is due to (n, {gamma}) reactions within the sample itself, and in some cases to the gamma rays generated in liners and cans, and not from the gamma rays generated in fission, nor from the moderator. Some implications of these results are discussed, among the most important being their application to radiation chemistry in reactors. Several mathematical results for absorption and generation of gamma rays in various bodies which should be useful in estimating dosage rates for samples irradiated in reactors are given (Appendix II). A method for making the calculations for an arbitrary absorption law are given (Appendix III). This method may be used with the true absorption law for gamma rays or even for the calculation of the absorption of the energy of …

The APPR-I is described and the various hazards are reviewed. Because of the reactor's location near the nation's Capitol, containment is of the utmost importance. The maximum energy release in any possible accident is 7.4 million Btu's which is completely contained within a 7/8 inch thick steel cylindrical shell with hemispherical ends. The vapor container is 60 ft high and 32 ft in diameter and is lined on the inside with 2 ft of reinforced concrete which provides missile protection and is part of the secondary shield. All possible nuclear excursions are reviewed and the energy from any of these is insignificant compared to the stored energy in the water. The maximum credible accident is caused hy the reactor running constantly at its maximum power of 10 Mw and through an extremely unlikely sequence of failures, causing the temperature of the water in the primary and secondary systeras to rise to saturation; whereupon a rupture occurs releasing the stored energy of 7.4 million Btu's into the vapor container. If the reactor core melts during the incident, a maximum of 10/sup 8/ curies of activity is released. While it appears impossible for a rupture of the vapor container to oecur except …

This investigation is the second study of short period flow decay in the Hanford reactors. The first study was made on the D-Reactor. As in the analysis for D-Reactor quantitative analyses were made for ruptures that might result from sabotage. A visual inspection of the entire process water piping system was also made to check for any glaring deficiencies with respect to earthquake resistance. A brief discussion of the earthquake resistance of the system is also included in this report.

This memorandum provides an estimate of the uranium requirements for the third and fourth quarters of calendar year 1955.

This document presents a summary of work and progress at the Hanford Engineer Works for September 1955. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project Sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Services departments have sections presenting their monthly statistics, work, progress, and summaries.

The following criteria outlines the basis, objectives, and fundamental methods that shall govern the preparation of final design for ``Project CGI-839, Modification to Fuel Element Test Facilities -- 1706 KER.`` These modifications will provide the equipment to test NPR size fuel elements in the KER recirculating loops. The 1706-KER Recirculation Test Facility of KE Reactor is operated to obtain experimental data regarding high temperature reactor coolant technology and high temperature fuel element testing. The facility consists of four in-pile recirculating loops. These loops will permit testing of fuel elements with the existing process tubes of 2.1 inches I.D. To provide adequate in-reactor fuel element test facilities to support the development of NPR fuel, two KER loops, {number_sign}3 and {number_sign}4 will be converted to provide a process tube of 2.7 inches ID that will be operated at typical NPR irradiation conditions. The remaining loops No. 1 and 2, will be modified to provide additional flow and heat transfer capacity for greater flexibility in the testing of high temperature fuel elements smaller than the NPR size. New pumps, heat exchangers, and minor piping modifications will be required in all loops.

Recent attempts to separate fission products from urine salts in a form suitable for measurement by beta counting have involved the use of ion exchange resins to remove the ions present in macro quantities leaving the trace elements behind as a {open_quotes}thin{close_quotes} sample for counting techniques. The separation of Cs from Na and K was chosen as the starting point because of the relative difficulty of separating these elements with ordinary chemical techniques. This report describes the testing of a method for the separation of cesium from macro quantities of sodium and potassium using the ion exchange resin Dowex 50. The results obtained on the preliminary work with solutions containing only the elements in question were deemed of sufficient interest to warrant reporting separately. Other difficulties from interfering ions in urine are now being studied.

Sufficient changes in the original projection fuel testing schedule have occurred to make the original schedules confusing. It is the intent of this document to revise an up-date those schedules so as to be a more realistic guide for associated development programs.

Using the 1.19-Bev/c antiproton beam recently discovered at the Berkeley Bevatron of the University of California, we have measured the attenuation cross section in beryllium and copper. These cross sections are compared to attenuation measurements made with the same geometry using positive protons of the same incident energy (497 MeV).

Varying amounts of radiation decomposition during storage in the dry form have been found in the cases of C{sup 14}-labeled valine, norvaline, norleucine, choline chloride, calcium glycolate and cholesterol. These data indicate that investigators using labeled organic compounds should make frequent checks of the purity of these compounds in order to exclude the possibility of the presence of decomposition products.

The targets and probes will be introduced 6-inches below the median plane so that adequate mechanical support can be effectively utilized without reducing the aperture. Probe heads will be of such configuration as to allow monitoring of any desired vertical strip of the aperture. It is probable that some space will be available in the quadrants after first performance tests have been on the machine. No targets or probes will be located in that 1-foot x 4-foot aperture initially. Provision will be made for driving the inner radius targets on the west tangent tank into the aperture during acceleration. The drive mechanism will locate the target (within an adjustable radius) in 1/2 a second. Because of the asymmetry in geometry of pole tip magnets with respect to the magnet yokes and the curvature of the quadrants, it will be difficult to remove positive charged meson beams. A re-entrant side plate on the inside radius of the west tangent tank is under study. While such a plate would provide a location for bending magnets and collimators for positive particles and would simplify the construction of some beam monitoring probes, its presence may introduce a first harmonic distortion in the magnet field …

None