Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.

Introduction: "The need for a method of acid determination which could be used for small samples and easily adapted to remote control led to the investigation of the use of electrolytically generated base for the titration of acid in certain solutions. The use of electrolytically generated base for the titration of acetic acid in the presence of nitric acid has been reported (1)."

"The following is an alphabetical listing of terms and units in common usage at Hanford Atomic Products Operation. Other terms and definitions may be added as the need becomes apparent or as revisions or additional terms are issued by the NCRP and ICRP."

A report intended to correlate the RA and RC Column uranium equilibrium data presented in the reports cited in the introduction.

From introduction: "This report provides background information regarding the study results presented in the first volume of this report and provides information resulting from the studies made on the gas cooled reactor concept."

Equations are developed for the computation of MPC's for radioisotopes assuming the excretion or retention to follow a power law rather than an exponential law. Computations are made for four isotopes on which some human data are available. Uncertainties in the initial data due to the use of intravenous injection to obtain the primary data, the definition of retention and the effects of age and diet are discussed.

Study of factors, such as the average particle size and particle-size distribution, which affect the fluidization properties of uranium trioxide powders.

Ten materials in which gold was alloyed with copper, silver, graphite, platinum, nickel or zinc (compositions given in Table 1) were evaluated in this study. Corrosion tests to determine the resistance of the alloys to boiling 60 to 65% nitric acid showed that with the exception of an alloy containing 51 wt % gold and 49 wt % graphite (Gold Graphalloy 811) which dissolved in 48 hr and an alloy containing 90 wt % gold and 10 wt % graphite which lost 2.3 wt % in 240 hr the alloys were essentially corrosion resistant.

From introduction: "The following report presents a body of information obtained in the Health Instrument Development Laboratory from September, 1948, to the present, and is intended to be a preliminary review of [the study of electrodeposition of plutonium]. Many improvements in technique and methods and investigations along lines not explored are suggested by the present work. These will be undertaken as time permits, and reported at a later time."

As potentially suitable alternate methods of installing closure plugs in cored slugs, four different schemes were considered. One of these schemes, whereby a flat chamfered uranium disc is crimped into a counterbored recess at each end of the bare slug after pickling, was developed to a workable state, and partially evaluated prior to reassignment of the job to another group. From the results of initial evaluation tests, this process appears to provide leak-free core closures and offers economic benefits that make it attractive as a production method, should cored slugs be adopted as standard.

Studies are described of the percutaneous absorption and gastrointestinal absorption in the rat of ruthenium administered in the form of "insoluble particulates." Results are also reported on the gastrointestinal holdup of these particulates.

This is the second of two reports describing the phases of a study of the wear and galling of autoclaved Zircaloy-2 by various fuel element support materials. The first report (1) showed that increasing contact area between the autoclaved Zircaloy-2 support and the autoclaved Zircaloy-2 process tube will not significantly improve the fuel support performance, and that a large flat contact area between the fuel supports and the process tube would be impractical to endeavor to achieve and maintain. It also showed that metals softer than Zircaloy-2 do not scratch the process tube but that loss of these metals by abrasion into the reactor coolant might be a problem.