A preliminary evaluation of the autoclave corrosion behavior of a series of U-low C alloys and a series of U-low Zr alloys prepared by Fuels Fabrication Development Operation has been made. The corrosion testing was conducted by Coatings and Corrosion Operation by the experimental methods and procedure outlined in HW-61378.

This document describes required laboratory space and lists major equipment items necessary for a routine water quality laboratory in the P. R. T. R. Building. During discussions with R. D. Widrig and V. L. Rooney about the analytical sample program for the Plutonium Recycle Test Reactor, the author was asked to summarize equipment and space needs for a water control laboratory to provide routine analytical coverage on some of the water systems. Based upon 1706-KE-KER experience, some operating personnel may be used to provide analytical coverage on those routine analyses that are needed on around-the-clock basis with a savings of both time and money.

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 being submitted to provide information and data on the planning and installation of a new mechanized drawing system which utilizes a new drawing index system and a 35mm microfilm image in a standard IBM card. The communication of engineering information to date has been primarily the full size contact print produced by exposing and developing light sensitive material. This method produces legible copies; but, it has the following disadvantages : (a) the original drawings are fragile, and become dirty and worn through excessive use and handling; (b) the sensitized paper has a limited shelf life; (c) the reproduction cycle is slow because it requires hand feeding and adjustment of the reproduction machine to the condition of the original; (d) the prints are large and unwieldy to handle as working documents; and (e) the filling of originals and copies is slow and expensive. In addition, providing reference prints which are accessible to engineering personnel in the widely separated areas from a central file and reproduction facility is slow, expensive and time consuming.

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.

The attached survey information comprises a cross section of Air and Gas Cleaning Operations as used in the Chemical Processing Department at the Hanford Atomic Products Operation, Richland, Washington. Most of the information as requested by J. T. Fitsgerald, Harvard University, is included in these surveys, certain cost information was difficult to isolate in the manner requested and may, therefore, be only roughly approximate. The numerical significance of the data will indicate this in most instances.

The region in which Hanford's chemical processing plant areas (separation areas) are located in the central portion of the Hanford Works area on a plateau, shaped like a giant bar, of glaciofluviatile materials. The general locations of these areas is shown in Figure 1. The region studied rises from 200 to 300 feet above the surrounding area and encompasses approximately 40 square miles or somewhat less than 8% of the Hanford reservation (Figure 2). Within the region are located the chemical separation plants and most of the major waste disposal sites.

The computation of liquid-boiling heat exchanger performance under a wide variety of operating conditions is a cumbersome, time-consuming procedure. Rapid evaluation of a design requires the use of some form of computational aid. Exchanger equations covering the case of liquid-boiling heat transfer have been derived and evaluated for a specific correlation of local boiling condition. Examination of various data as presented by Bonilla and McAdams indicates that the boiling coefficients are not fully reproducible and appear to be sensitive to surface conditions, gases, geometry, etc. It therefore is believed advantageous to extend the reference analysis to cover a wide range of surface and pool boiling conditions. In this manner, the effects of potential errors in both boiling and liquid film coefficients may be investigated with minimum effort.

In recent months, relatively large quantities of neptunium-237 have been recovered from Hanford irradiated uranium. The over-all recovery process consisted of 1) isolation from Purex plant solutions by solvent extraction, to yield an impure neptunium nitrate solution contaminated principally with uranium, plutonium, and fission products (2) purification by anion exchange 3) precipitation of neptunium (IV) oxalate; and 4) calcination of the oxalate to yield neptunium (IV) oxide, NpO2. This paper describes the oxalate precipitation process investigations and results.

In HW-56161(1), the preliminary background, bases, and advantages which could be visualized in the study and establishment of reactor concepts utilizing boiling mercury- 204 were presented. The attractive chemical and metallurgical properties of mercury which make it particularly suitable for use in special non-rigid fuel systems as well as its potential for heat transfer applications were considered to be of significant interest to the Plutonium Recycle Program also, since the issuance of the original document, continued study of the potentials for an economical isotope separations process for mercury has shown attractive possibilities for a method based on photochemical activation (HW-59329). (2) The prospectas(3) for this process appear so favorable that earlier opinions and expectations seem to have been conservative. Although the desired level of initial effort in related studies has not yet been realized, particularly in the area of chemical engineering, reactor engineering, and economics, it appears advisable to revise the earlier document to recognize the impact of the favorable outlook for economical mercury isotope production, to present other related information which has been developed, and to recommend the beginning of a research and development program.

The instability of the steel tank bottom of 113SX waste storage tank was postulated to have been caused by a pressure underneath the steel liner which was in excess of the hydrostatic liquid load of the waste resting on the steel bottom.

The methods for the separation of the elements from thorium to americium having wide use are those employing solvent extraction techniques (1) (2). During recent years the behavior of these elements on anion exchangers has been studied, resulting in the wide application of these resins to the separation of the actinides (3) (4) (5) (6) (7).

In HAPO solvent extraction processes there are two independent aspects of nitrous acid chemistry. One concern the decomposition of the solvent through nitration reactions and the attendant problems. These reactions are autocatalytic in the presence of nitric acid and have threshold values for both temperature and nitric acid concentration for a given solvent below which nitrous acid disappears and above which it is generated with continuous destruction of the solvent. These reactions are identical to those found in the prior study of the hexone system.

In solvent extraction purification processes such as are used at Hanford, the fuel elements or "slugs" from the reactor containing uranium, plutonium, and fission products are dissolved in nitric acid, adjusted to the required feed composition, and pumped to the solvent extraction columns. Figure 1 in a schematic diagram of such a solvent extraction process. In the A column, the uranium and the plutonium are extracted into an organic phase while the bulk of the fission products remain in the aqueous phase and leave as waste with the column raffinate.

The fixation of aqueous radioactive wastes in a stable solid media by means of calcination has been the subject of considerable research and development effort. Several methods of doing this on a continuous basis have been devised and a few have been demonstrated to be feasible for the handling of non-radioactive or low activity simulated wastes. Currently an investigation of calcination by means of radiant-heat spray drying is being carried on by the Chemical Research Operation of the Hanford Laboratories Operation. The process consists of atomizing the liquid to be treated into the top of a cylindrical column, the walls of which are maintained at a high temperature. The resultant suspension of droplets in the water vapor formed by evaporation passes through successive zones of drying, calcination, possible chemical reaction or melting, and partial cooling as it proceeds down the tower. Separation of the resultant solids, steams, and uncondensable gas is made by conventional methods.

From objective: "The objective of this work was to design, develop, assemble, and test and automatic analyzing monitor for recording the prominent isotopes in reactor effluent cooling water."