In his relatively short life of 57 years, Ernest Orlando Lawrence accomplished more than one might believe possible in a life twice as long. The important ingredients of his success were native ingenuity and basic good judgement in science, great stamina, an enthusiastic and outgoing personality, and a sense of integrity that was overwhelming. Many articles on the life and accomplishments of Ernest Lawrence have been published, and George Herbert Childs has written a book-length biography. This biographical memoir, however, has not made use of any sources other than the author's memory of Ernest Lawrence and of things learned from him. A more balanced picture will emerge when Herbert Childs biography is published; this sketch simply shows how Ernest Lawrence looked to one of his many friends.

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This report provides Source and Special Nuclear Material composition of Ending Inventory Reports for the month of January, 1967.

This report itemizes the irradiations performed by Testing for Battelle-Northwest Laboratories. It lists the material being irradiated, awaiting disposition and material shipped during the report period.

The minimum travel time of 79 days observed for /sup 3/H at the point of maximum flow along the riverbank spring-front gives a minimum decay time that can be also applied to other radioisotopes discharged to the crib. Actual travel times of isotopes discharged to the site are dependent on the interaction of the isotopes with the sediments (ion-exchange, chemical, adsorption, etc.). A travel time of 101 days observed for /sup 131/I is an indication of the dependence of actual migration rates on the isotope's interaction with the soil materials. The interaction of most isotopes with sediments is significantly greater than that of iodine. Therefore, most isotopes will have much ionger travel times. Significant quantities of the waste appear to be flowing northeast from the site into the Columbia River below 100-D Area. This would increase the length of flow path and travel times to the river by a factor of 10. Estimates of the distribution of long-lived isotopes at the site are based on laboratory measurements. Field evaluations of the actual distributions of long-lived isotopes are in progress. This study involves drilling and sampling of the sediments in and near the crib. Analyses of radiocontaminants in these samples will …

The infrared imagery data was collected September 13, 1966 from 1010--1013 o`clock, using a mercury-doped germanium detector which was filtered to respond to wave lengths of infrared radiation. The magnetic-tape recorded information was processed with a computer program to obtain quantitative evaluations of river temperature variations and to accurately define surface temperature patterns resulting from the discharge of reactor effluents into the river. The river surface-temperature information collected in the vicinity of the reactor areas was plotted as contours of equal voltage readings which are essentially analogous to isothermal contours. The patterns which developed show clearly: the paths and thermal variations of reactor effluent plumes in the River, points where retention basin subsurface leakage enters the river via the ground water route, and those reaches across from the reactors where the River is recharged by ground water significantly colder than the water released from the Priest Rapids Pool.

The experimental studies were performed in the heat transfer and fluid flow facilities of the Pacific Northwest Laboratory operated by Battelle Memorial Institute. The test section was installed in the high pressure heat transfer apparatus, a stainless steel loop which has a design rating of 2500 psig at 650{degrees}F. Recirculating flow was provided by a 250 gpm, 1450 ft head centrifugal pump, and the flow rate through the test section was adjusted by air-operated control and bypass valves. The loop was pressurized and controlled at the desired operating pressure by a feed-and-bleed arrangement using a positive displacement 3-piston injection pump and an automatically controlled air-operated bleed valve. All feed water passed through a deaerator, a deionizer, and a filter before entering the injection pump. Injection pump pulsations were dampened with a 10-gal accumulator. During operation of the third test section, all recirculating water passed through a porous metal filter unit having a 10 micron removal rating. A three-way valve downstream of the test section was used to adjust the loop flow split through and around a water-cooled heat exchanger. The valve was automatically controlled to maintain the desired water temperature entering the test section.

Approximately 13 kg of U-233 were fabricated into 1 wt % UO/sub 2/-ThO/sub 2/ and 26 wt % UO/sub 2/-ZrO/sub 2/ pellets and enclosed in Zircaloy-2 cladding tubes as 1299 blanket and 377 seed rods. The U-233 contained 38 ppM of U-232, and was purified as two batches of liquid UO/sub 2/(NO/sub 3/)/sub 2/ immediately prior to processing into powder form. All fuel rods were completed within 95 days of this initial solvent extraction of the nitrate. Overall U yield of nitrate to usable materials was over 90%, and only 14 rods were rejected in welding and all without loss of contained fuel. (NSA 21: 14872)

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This document summarizes the amounts of radioactive contamination discharged to ground from chemical separations and laboratory facilities through December, 1966. Detailed data for individual disposal sites are presented on a month-to-month basis for the period of January through December, 1966. Previous publications of this series are listed in the bibliography and may be referred to for specific information on measurements and radioactivity totals prior to January, 1966. Several changes in crib nomenclature were made during 1965. These changes are noted on the individual tables so reference may be made to them in previous reports.

This report discusses a radiation exposure accident of personnel at the Hanford production reactor facilities.

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This document details activities of the Reactor Operation Branch during the months of January, 1967 through December, 1967.

The intent of this document is to recommend a calorimetric radiation detector design that can measure radiation environments adjacent to Aerojet-supplied XE hardware.

It has been found that treating autoclaved, aluminum-clad fuel elements in a relatively strong caustic solution produces surface attack patterns that qualitatively resemble corrosion patterns seen on fuel elements irradiated in the Hanford water-cooled production reactors. It is believed that mechanisms controlling this ex-reactor phenomenon may yield insight into similar processes for in-reactor irradiation conditions. To date, autoclave film tests have been designed to yield comparative results based on differences in the methods of sample fuel preparation. Contained herein are preliminary test results presented in photographic form with explanatory comments and a brief discussion of fuel preparation for a special in-reactor autoclave film comparative study (PWR 95-6).

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