Fractional absorption of gamma photons from a source by uranium or plutonium in solution is measured to determine concentration of these elements.

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.

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.

In order to utilize the advantages of the electron microscope for the study of respirable particles, it is desirable to have an instrument capable of sampling from atmospheres having very sparse dispersions of particles at a rate sufficiently high to result in precipitation densities of approximately one particle per 10/u² of microscope screen for a 10 minute sampling period. In order to avoid qualitative or quantitative alteration of the aerosol, it was desired that the instrument collect the sample directly on an electron microscope screen rather than on a filter material for subsequent transfer to the screen. This paper summarizes work aimed at the development of such an instrument.

periodically the Industrial Hygiene Unit has the occasion to perform efficiency tests on respiratory protective devices and on filter cartridges used with these units. A study of the relative merits of the flame photometer and conductivity meter was made to determine which is more applicable for the determination of NaCl in filter samples.

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.

The purpose of this program is to determine the effects of neutron radiation and reactor gaseous atmospheres on the structural integrity of candidate materials for the PRTR gas-cooled loop. An exploratory investigation is being conducted to select a high temperature resistant alloy for the fabrication of tubes and supporting appliances for the PRTR gas-cooled loop. In addition to a low neutron cross section, the material must be able to withstand the operating conditions outlined in Table 1.

This report is a document summarizing all information available on life aspects of various measures proposed to reduce or eliminate corrosion of Van Stone flanger.

The preparation of radioactive metallurgical specimens for microscopic examination is one of the responsibilities of the Radiometallurgy Sub-Unit. An abrasive cut-off machine development program, based upon a previous experimental model, was undertaken to provide a method for sectioning of irradiated materials without undue personnel exposure or spread of contamination and finally to provide data for the design of an abrasive cutting unit for use in the work cells in the Radiometallurgy Building. A horizontal-feed type set-off machine, powered by a 7 1/2 hp motor with V-belt drive, has been developed for the submerged sectioning of irradiated uranium and is currently being used successfully to obtain samples for metallurgical, chemical and physical investigations without excessive personnel exposure or spread of radioactive contaminates.

At the request of the Hanford Operations Office of the Atomic Energy Commission, a criticality instrumentation meeting was held at Hanford on August 17 and 18, 1959. The purposes of the meeting were: (a) to review types of criticality control and/or alarm instrumentation at each site, their problems, shortcomings and potential obsolescence; (b) to discuss instrumentation in the area if approaching criticality; and (c) to consider for material balance purposes, the feasibility of devising instruments to detect the buildup of plutonium and enriched uranium bearing residues in process systems.

The creep problems associated with zircaloy-2 process tubes and the factors affecting the creep of these tubes were discussed in detail. Emphasis was placed on the determination of the tube wall thickness for an SPR tube, whose minimum thickness is limited by creep considerations. It was concluded that, at the present time, there is not enough information available to design zircaloy-2 process tubes on a realistic basis. Various experiments were suggested to supplement the creep rate testing program being pursued by Battelle Memorial Institute.

Report discussing a method for the stepwise calculation of the number of transfer units utilized in a given solvent extraction operation. "Use of the method results in a very appreciable saving in time of calculation with an error of 1.5% for the runs tested. The error tends to become smaller with increasing total numbers of transfer units involved."

Relations governing the measurement of Stainless Steel corrosion rates by activation analysis are derived and discussed. The principal neutron induced radioactivities are calculated and graphed. Shielding requirements are considered and it is concluded that six inches of lead shielding should be sufficient for the proposed experiments if the samples are allowed to cool for one day in the reactor storage basin.

From introduction: "The present investigation of the properties of boron stainless steel is an outgrowth of a project started in 1947. The problem is to replace the present steel used for drop rods in the Hanford piles with a material much less subject to corrosive attack from the humid atmosphere existing at the location of the rods."

This work was performed to develop a general chemical method for the determination of small amounts of plutonium in solution. The work showed that a coulometric titration based on the preliminary oxidation of the plutonium to Pu (VI) followed by titration with electrolytically-generated ferrous ion to Pu (IV) was such a general method and was subject to few interferences. The significance of the work is that a chemical determination of plutonium can be made for amounts of plutonium heretofore determined only by radioassay methods, and the chemical determination of larger amounts are made more readily and with higher precision than with previous methods. The work also extends the application of coulometric titration methods to a new substance.

Aluminum nitrate solutions are used as salting agents in the redox process and frequently in organic-aqueous extractions in the laboratory. Determination of specific gravity is a convenient means of estimating the concentration of such solutions. However, where an aluminum nitrate solution has been prepared by dissolving aluminum hydrate in nitric acid, the ratio of nitrate to aluminum may intentionally be other than stoichiometric, the solutions being described as acid, neutral, or acid deficient.

The design notes contained herein may assist in preliminary studies concerning feasibility of any proposed gamma monitor system. The minimum and maximum solution concentrations for each type of system are listed. The data is based on 32 ml liquid sample.

Plankton collected from the Columbia River by the net method and by the centrifuge method were compared. The centrifuged plankton (nannoplankton) exceeded the net plankton in weight, in abundance of organisms and in radioactivity. Similar seasonal trends were present in both types of plankton.

The purposes of this study are to review the available information affecting the disposal of Purex cooling water, powerhouse waste water, and B plant cooling water, to consider the feasibility of various disposal schemes, and to prepare recommendations to the Manufacturing Department for the most desirable courses of action.

A laboratory test was performed to determine if a 10% oxalic acid solution could be safely be employed as a substitute to 2% chromic acid plus 5% phosphoric acid for removal of corrosion products from aluminum corrosion samples or slugs.

The purpose of the test used to make this report was to determine if anodizing could become a part of the canning operation prior to autoclaving, other factors permitting, or if it must follow autoclaving.

The objective of this report is to analyze the basic engineering problems involved in the design of a pressurized demonatration reactor to be moderated and cooled with heavy water. Two fundamental concepts of this reactor, here referred to as the HWER, are as follows: (1) a tank-type reactor, in which the moderator pressure is maintained at or near atmospheric conditions, and (2) a pressurized vessel-type reactor in which the moderator pressure is maintained at 1000 to 1300 psi. The fuel and primary coolant channels in either case will be designed for an internal pressure pressure of 1000 to 13000 psi.

Abstract: "A batch of slugs is being prepared for which the U-235 content will be 1.75 per cent, and it is of interest to calculate the minimum number of such slugs required for a critical assembly in water. Using Handbook (CL-697) methods, a critical assembly of these slugs arranged in a lattice with a spacing of 5.5 cm."

This report refutes earlier calculations made in the flux level of exponential piles. The results of the earlier calculations made on subcritical assemblies using critical assembly equations are in error. The calculations used in this report were more successful.