The scintillation camera is a nonscanning instrument for displaying the distribution of radioactive isotopes. It can be used, for example, to show abnormalities in the thyroid gland with I-131, the size, shape and location of kidneys with Hg-203 Neohydrin or to locate brain tumors either with Hg-203 Neohydrin or with the new positron emitting agent, Ga-68 EDTA. For many applications, the scintillation camera has higher sensitivity than conventional isotope scanners, and will produce pictures in less time or with a smaller quantity of isotope present. Alternatively, it produces better pictures if the conventional dosage and exposure factors are retained. Because of the short exposure time, and because the scintillation camera is continuously sensitive to all areas within its field of view, it is well adapted to taking rapid sequences of still pictures or time-lapse motion pictures of subjects in which the distribution of radioactivity is changing. For example, time lapse pictures have been taken showing I-131 Rose Bengal Bengal being excreted from the liver of children with liver disease and of I-131 hippuran going through the kidneys of patients suspected of kidney disease.

Douglas United Nuclear, Inc., has allocated to the Pacific Northwest Laboratory $542,000 of 02 Research and Development funds and $455,000 of Process Technology funds for FY-1967. Of these, $392,000 of 02 Research and Development funds and $420,000 of Process Technology funds are the responsibility of the Research and Engineering Section. The balance in each case is the responsibility of the Production Fuels Section. Representatives of these Sections have met with Pacific Northwest Laboratory personnel to develop programs to be undertaken in FY-1967. This document briefly summarizes the results of the discussions and delineates the work to be accomplished.

The pages of the report show the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials. For further description of column headings and the current discharge goal exposure plan refer to Document DUN-1048.

This report gives the status of production tests control tube loadings in reactor process tubes containing significant amounts of SS material. Data are given in table form. For further description of column headings and the current discharge goal exposure plan refer to Document DUN-3443.

This report details activities at Battelle Pacific Northwest Laboratory for the month of June 1965.

The major objective of the current program is the preparation of high energy hydroxyl-terminated polyester prepolymers from combinations of energetic diols and dicarboxylic acid chlorides. The initial work was based on the reactions of 4,4-dinitropimeloyl chloride (DNPCl) with 2,2,8,8-tetranitro-4,6-dioxa-1,9-nonanediol (DINOL) and 3(dinitrofluoro- ethoxy)-1,2-propanediol (REX-18). In an effort to develop a smooth and rapid polyester polymerization method, reactions between DNPCl and both DINOL and REX-18 have been carried out in THF containing pyridine. It was expected that the pyridine would act as an HCl acceptor, permitting room temperature polymerizations. This was indeed shown to be the case. In fact, when the glycol and DNPCl were dissolved in THF and pyridine added rapidly, a very exothermic reaction took place, with copious quantities of pyridine hydrochloride being precipitated. Slow addition of pyridine to the reaction mixture also resulted in an exotherm. In both cases, brown polymers were produced and they were very difficult to work-up. The next series of polymerizations will be carried out at 0{degrees}C in an effort to control the polymerizations more carefully and avoid color formation. The diacid chloride of 2-fluoro-2,2-dinitroethoxyfumaric acid has apparently been synthesized. Reactions of the acid with thionyl chloride at 50-60{degrees} for several days followed by …

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The technical concept for Project Travois contains one simple analysis of the potential hazard of contaminating the Arrowrock Reservoir on the Boise River with some of the radionuclides produced. This previous analysis assumes homogeneous and prompt mixing of all the tritium and tungsten isotopes. This simple analysis is physically unrealistic sine there is no way of transporting all of these radionuclides to the reservoir, promptly. We shall in this paper reanalyze the contamination problem in such a way that we define the type of site geology and hydrology information that must be developed.

The objective of this supplement is to authorize recharging of the thoria in the fringe zones of the B, C, D, KE, and KW Reactors. Initial charging is described in the parent document. This authorization will serve as an interim measure until Reactor Process Standards have been approved to authorize fringe blanket thoria irradiations.

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This is the concept for a series of post-shot investigations at the Piledriver site, Area 15, Nevada Test Site (NTS), to gain information on: Chimney geometry and associated wall rock conditions resulting from a deeply buried (1500-ft) nuclear explosion in granite; The characteristics and distribution of rubble and radioactivity in the chimney; and Data pertinent to in-situ leaching. These categories define the three phases of this proposal in chronological order. The technical programs under Phases II and III will depend on the results of Phase 1. Presently, it is not known whether or not there has been a collapse of the Piledriver cavity. If collapse occurred, the predicted dimensions of the chimney, based on Hardhat experience, are expected to be 250 ft in diameter and 560 ft high. For the purpose of this discussion, it is assumed this condition exists.

Because of various evaluation studies on fuel stability, it is proposed that Coors Porcelain Company change their recipe for fueled tubes. Specifically, zirconyl nitrate should be used. in addition to uranyl nitrate. The detailed changes to be made are provided.

This study investigates the scaling of dimensions of craters formed by nuclear explosive sources as well as the problem of making consistent estimates of other geonuclear effects including maximum base surge radius, vented fraction of the gamma emitting radionuclides appearing in close-in fallout, and main cloud dimensions. Input to the proposed scaling method includes the Froude number as determined by the depth of burial and the mound surface velocity at vent time, and the pressure in the cavity at vent time. These inputs are provided from long-running cratering-mechanincs numerical calculations. Illustrations are given of the use of the method for 1 Mt and 200 kt cratering events. 10 refs., 10 figs., 7 tabs.

It is desired to develop an empirical formula of the type Y=KD[sup n] where Y is the yield in kilotons and D is the `effective diameter` in feet corrected for temperature and pressure variations if necessary.

This report defines the plan and purpose for the Palanquin post-shot exploration program. This program is necessary to obtain data that is needed in the understanding of the Palanquin experiment, and related explosion phenomena, which can be obtained in no other way.

This report provides reactor physics calculations for prompt burst reactors similar to the Los Alamos SUPO reactor. A discussion of the water boiler runaway at Hanford on November 15, 1951 is also provided.

The continuing concern with efficient utilization of manpower at the Nevada Test Site (NTS) and the seemingly high cost of individual nuclear shots, together with the recent evolution of the L-12 scope, generated some fresh thoughts concerning more efficient procedures for the `average` test. Every time anyone looks at the problem., they tend to analyze the existing conventional approach and try to find the one or two most expensive and `lossy` factors in the can of worms. Usually this turns out to be a problem within the realm of specialization of the particular analyst! People not so directly concerned with the program tend to look for, or wish for, or even `invent` miracles`. Our present techniques appear to be the sum (and possibly even the product) of many small contributions which have all been beaten down to the same level of importance. Such a situation in any systemic problem is usually symptomatic of the need for fairly violent departures in the aver-all system approach, at least in thinking. This report proposes and details a modular nuclear testing concept.

This memorandum elaborates on items discussed in a meeting held July 13, 1961 a suggested Spade and Snoopy Program for the Pluto effort. Topics were specific Tory II-C features, basic studies, and miscellaneous items.

Another interesting application of nuclear excavation would be a sea- level canal 160 miles long across Israel, connecting the Mediterranean with the Gulf of Aqaba (and thus the Red Sea and the Indian Ocean). Such a canal would be a strategically valuable alternate to the present Suez Canal and would probably contribute greatly to the economic development of the surrounding area. The difference in elevation between sea level and the Dead Sea (30 miles away and 1286 feet below sea level) might also be used to generate hydroelectric power. The maximum depth of excavation to be encountered is on the order of 1500 feet. Conventional methods of excavation of this magnitude are prohibitively expensive, if indeed possible, but it appears that nuclear explosives could be profitably applied to this situation.

The Tory II-C lateral suspension has been designed for 4 g`s of lateral acceleration of the duct. Calculations and model tests indicate that this requirement has been met or exceeded. In order to have a more realistic model to test, Tory II-C springs are going to be fitted around the full scale core slice which was previously built up. Instrumented accelerations of this assembly should give the most direct demonstration that is possible of the response of the system to flight. This memorandum discusses, knowing the capabilities of the present system, the design changes necessary to suit different maximum accelerations by increasing the capacity of the Tory II-C side support system.

This report presents details of the activities of Douglas United Nuclear at the Hanford site during the month of June 1968.

This document presents details about the activities of Douglas United Nuclear at the Hanford site during the month of June 1967.

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The sodium silicate addition to the coolant reduced the effluent concentrations of certain radionuclides. Nothing was observed during the course of the test to indicate that sodium silicate could not be used at all plants. However, the reductions obtained in effluent activity are not believed commensurate with the cost of silicate usage.