Radiation damage to graphite has several consequences of practical importance. The growth of graphite under radiation (Wigner's disease) in production reactors has always been a serious concern. The thermal conductivity of graphite decreases greatly with time of irradiation and is important in long range studies of reactor temperature problems.

This report is a summary of the neutron attenuation data which have been obtained at the Brookhaven shielding facility on a mock-up of the fuel-rod-unloading plug used in the KAPL Reactor. Before this program was initiated, a number of small scale tests had been made in the ORNL lid tank on carbon steel mock-ups of components of the rotating plug. The results of the tests indicated considerable neutron streaming through the vertical steel and air members of the plug. However, the lid tank source strength and dimensions did not permit the tests to be extended to the full plug height. In view of the concern aroused by the ORNL tests and the absence of fundamental information on the transmission of neutrons through steel and the addition height (12') available here resulted in a request for BNL to construct and test a mock-up of a sector of the SIR top plug in accordance with KAPL specifications.

This report is a record of experimentation conducted intermittently over a period of two years and directed toward preventing deposition of transport corrosion products on fuel elements and other critical components in high-temperature, circulating water nuclear reactor. It includes the postulated mechanism for deposition, a description of experimental equipment, experimental data, results obtained from the experiments, and recommendations for future study.

A spectrometer has been used with a hollow prism electrically heated to 70 C to measure the refractive indices of solutions of uranium hexafluoride in bromine trifluoride and uranium hexafluoride in bromine pentafluoride. The refractive indices of the two binary systems have been expressed as a function of composition.

Three types of stainless steel (309 SCB, Carpenter 20, 304-L) were exposed to both the liquid and vapor phase of each of three types of solutions. The time of exposure totaled ten days during which the specimens were cleaned and weighed periodically. The three synthetic D-12 waste solutions contained respectively chrome-high chloride, chrome-low chloride and high chloride sans chromium. The solutions were renewed at each weighing.

An improved method for the determination of boron in plutonium is reported. Precipitation of plutonium (III) acid oxalate prior to color development with curcumin results in increased precision, greater speed, and lower costs. Results are presented of a statistical study involving all variables.

This report describes the objective of this production test which is to simulate with a few tubes operation of the old piles with small water annulus at power levels in the range of 800--900 MW.

Fragments of radioactive materials were deposited in the Redox area during August, 1953. By radiation monitoring, the location, physical properties, and dosage were determined. The cause was assumed to be the buildup of ammonium nitrate containing ruthenium on the filters of the Redox stack. The amount of occupational exposure, and the reasons why this incident happened were also discussed.

The objective of the production test described in this report is to provide the authority and mechanism to remove process tubes from the piles for inspection. The test is intended to provide a more positive tube inspection program than was previously provided under production test number 105-9-P, ``Corrosion of Slugs and Tubes``, document number 7-3928.

The results of the fall-out monitoring program at fixed stations more than 200 miles from the test site following the series of atomic tests in Nevada during the spring of 1952 are shown in a series of maps. Trajectories of debris from the individual bursts are given, together with a discussion of meteorological phenomena associated with the transport of atomic debris.

The following document describes data collected from a 14-month period of analyzing crustaceans containing radioactivity. Provided is information based on the change of radioactivity through seasonal changes.

Introduction: "The problem of determining the properties and necessary controls on the TBP Plant waste disposal to eliminate transport line plugging and to permit higher concentration prior to return of this to the tank farms was studied. A report of preliminary findings was made to L. W. Finsh on January 31, 1953. This report compiles information in the aforementioned report and findings since its issuance. Previous studies related to this problem are summarized in the U. R. Technical Manual, HW-19140."

The following report analyzes whether there is a difference between the neutron streaming in the "armor plate" and 347 stainless steel.

Abstract: "A precise potentiometric method for the determination of uranium in essentially pure uranium oxides is described. Ten gram samples of oxides are reduced in a Jones reductor and titrated potentiometrically to U+4, using platinum and tungsten electrodes. A weighed amount of solid Bureau of Standards potassium dichromate is then used to oxidize at least 99 percent of the uranous ion, and the oxidation is completed by titration with 0.01 N potassium dichromate using calomel and platinum electrodes. This method, which is based on a primary chemical standard, has a precision of +/- 0.015% on a single determination at the 95 percent confidence interval."

Quarterly report of the Chemistry Division at the University of California Radiation Laboratory providing updates for each department about current findings and ongoing research.

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Analysis indicates that, in order to achieve supersonic flight with nuclear powered aircraft, a reactor -power plant combination capable of operating at temperatures considerably in excess of current practice must be developed. It is pointed out that there exist two general avenues of approach toward the goal of attaining high temperature reactors and power plants. The first approach involves the continuation and augmentation of research along the lines pursued by the conventional turbo-jet engine manufacturer, namely a search for material coatings or materials that will retain structural strength in high temperature oxidizing atmospheres. The second approach seeks to take advantage of the peculiar characteristics of the compressor-jet engine that permit the operation of the high temperature components in a non-oxidizing atmosphere. The results of a preliminary design study of a supersonic aircraft powered by a high temperature sodium, liquid vapor compressor -jet engine are summarized. The analysis considered, in as much detail as was warranted by the limited experimental information available, the characteristics of the reactor, power plant and airframe involved in determining performance. This study has been conducted for the purpose of guiding future, long -t e r rn , research work along the lines of high temperature reactors …

The feasibility of the use of a water-boiler type reactor as a production test facility for making reactivity tests on various forms of uranium and uranium compounds was investigated. It is concluded that the reactor should be very useful for production testing of materials with the danger coefficient techniqus. A suggested production procedure is outlined. (auth)

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