Theoretical investigation on the nature of ion exchange of acidified uranyl sulfate solutions with Dowex 21K, a strong base ion exchange resin.

From abstract: The temperature of molten uranium was measured indirectly by an infrared radiation pyrometer. The emissivities of graphite and molten uranium were determined, and a series of equations correlating pyrometer readings with melt temperatures was derived.

From introduction: "This brief paper deals with the subject of radial temperature differences for heat transfer to fluids flowing through concentric annuli under the following conditions and assumptions: a. constant heat flux; b. fully-established turbulent flow; c. heat transfer through inner wall only; d. physical properties independent of temperature."

Technical report outlining the nature and effects of energy loss and radiation in biological materials during radiobiological processes.

Technical report outlining the effects of chromosomal abnormalities in tetraploid Argentine flint maize pollination, and subsequent generations.

From introduction: This report has been prepared to present the details of the heavy water cooled power reactors, including cost estimates, plant design studies, and other work directly related to the current status of D2O reactors.

Abstract: By use of a modified thermobalance and reactor as the primary experimental tool for sample preparation and evaluation, a process has been developed by which parent uranium feed materials of a widely variable reactivity and composition may be converted to a uniformly reactive uranium dioxide.

Abstract: The measurement and calculation of the reactivity absorbed by Xe135 as functions of time after shutdown for the SRE are described.

Abstract: Because of the outstanding heat transfer efficiency of sodium, it is necessary in sodium-cooled reactors to consider and attempt to prevent the occurrence of adverse stresses as a result of thermal transients in the system.

Abstract: A 3000 kw (thermal) bayonet duplex tube model steam generator was performance-tested in a liquid metal test loop at MSA Research Corporation, Callery, Pennsylvania, under the cognizance of Atomics International.

"Mesic decay of hyperfragments is discussed systematically on the basis of a previous model for hyperfragments. The general formalism for the two-body and three-body mesic decay was developed. The polarization-direction correlation and the angular correlation for the two-body and the three-body decays are discussed together with the decay probability. The formalism was developed so as to include the isotopic spin selection rule ( DELTA I = 1/2 and 3/2) for the mesic decays. The theory was applied especially for the low mass number hypergragments where it was found that the branching ratios of the two-body and the three-body mesic decays of /sup 3/H/sub i and /sup 4/H/sub i, (/sup 3/ H/sub i yields /sup 3/He + i/sup -/)/(/sup 3/H/sub i yields D + p+ pi /sup -/) and (/sup 4/H/sub i yields /sup 4/He + pi /sup -/)/(/sup 4/H/ sub i yields /sup 3/H + p + pi /sup -/), could be used for the determination of the spins of both hyperfragments. The fraction of the p-wave decay rate for the free LAMBDA decay obtained from the reaction /sup 5/He/sub i yields /sup 4/He + p + pi where the decay proceeds through two-resonant states (p/sub 3/2/ and p/sub 1/2/) …

Report from Operation Plumbob regarding an experiment investigating secondary missiles created by blast waves from nuclear detonations of three different yeilds.

From abstract: Two 20-ft-long 7-ft-diameter 10-gauge structural-plate pipes, having longitudinal joints with eight bolts per foot, were buried and tested in the Smoky event of Operation Plumbbob at predicted pressure levels of 195 and 265 psi. The depth of burial was 10 ft over the crown of the pipe.

Measurements and visual observations made during the Hardtack II series of underground shots provide basis for conclusions regarding shock-resistant design of protection for cavities in rock and qualitative prediction of permanent displacements in rock due to nuclear detonations. Vibration measurements on blast-resistant construction in soil provided non-nuclear test results which apply to shock resistant design. With varying soil cover, the compressive mode predominated in arch structures and a mass of soil apparently acted with the structure that varied in magnitude in inverse fashion with two depths of cover. Underground structural harmonic response theories were in part verified, for some structures, though the absence of an appreciable flexural mode in buried arch structures was significant.

A reinforced-concrete steel-plate-lined vault and steel vault door were exposed to a nuclear detonation (shot Priscilla, about 37 kt, balloon suspended, at 700 ft) at the predicted 75-psi peak incident pressure level (1150 ft from Ground Zero). The vault was designed by the ultimate-strength theory to utilize the additional strain energy available in the elastoplastic and plastic ranges. Flexural and thrust capacities were determined, and shear capacity was computed. It was established that above-ground structures can be designed and constructed to survive the pressure levels experienced by this structure. The vault and door provided adequate blast and thermal protection for normal usage, and the structure was adequate to resist overturning and excessive sliding under conditions of the test.

Abstract; The fission product data obtained during SM-1 Core I operation (June 1957 - May 1960) is reviewed briefly and interpreted. Evidence is presented to indicate that a fuel element defect was responsible for the high fission product activity level observed in the primary coolant. Relative escape coefficients are calculated and the defect size estimated. Anticipated fission product levels during SM-1 Core II and SM-1A Core I operation are estimated from alpha surface contamination data on completed fuel elements. The importance of in-line sampling for monitoring fission product activity is stressed as well as the need for failed fuel element detection methods.

Abstract: Test procedures for special tests involving in-core SM-1 temperature and flow instrumentation are described (Task XIV Package Tests). These tests involve in-core steady state flow and temperature measurements, loss of flow transients, load transients, reduced primary system pressure operations and reduced element flow. The thermal and hydraulic conditions prevailing in these tests, including steady state and transient burnout rations, are developed. The effects of reduced system pressure and flow on the burnout ratios are determined as are the expected stuck rod conditions when Task XIV test elements are installed. The effect on the maximum credible accident is included and a recommendation to conduct these Task XIV package tests is made.

Abstract: The natural circulation, direct cycle, boiling water reactor reference design presented in this technical report is the alternate to the preferred preliminary design developed under Phase I of the PL-3 contract. The report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant equipment, waste disposal, buildings and tunnels, services, operation and maintenance, logistics, erection, cost information and training program outline.

Abstract: The pressurized water reactor preliminary design presented in this volume is the preferred design developed under Phase I of the PL-3 contact. This technical report presents plant design criteria, summary of plant selection, plant description, reactor and primary system description, thermal and hydraulic analysis, nuclear analysis, control and instrumentation description, shielding description, auxiliary systems, power plant equipment, waste disposal, buildings and tunnels, services, operation and maintenance, logistics, erection, cost information and a training program outline.

From abstract: "Lactates of all the rare earths except lanthanum, cerium, and praseodymium were prepared and studied. In the case of lanthanum, cerium, and praseodymium the lactates are apparently so soluble that they cannot be crystallized directly from aqueous solution. Products obtained by addition of anhydrous ethanol to sirupy solutions of the light-rare-earth lactates were not well characterized and were deliquescent. Neodymium lactate trihydrate was prepared only by the addition of alcohol to a sirupy solution. Since it was not as deliquescent as the lactates of lanthanum, cerium, and praseodymium, some of its properties could be studied. The lactates of all the other rare earths, samarium through lutetium, as well as the lactate of yttrium, separated readily from aqueous media as trihydrates--the solubility of the hydrated lactate decreasing as the atomic number of the rare earth increased. Thermal decomposition of the crystalline lactates, except those of neodymium and samarium, proceeded through dihydrated and anhydrous states to a composition corresponding roughly to LnlacCO3 at a temperature of about 290-300°C. Ln2(CO3)3 or Ln2O(Co3)2 were observed. In order to make a comparison, thermal decomposition of the rare-earth glycolates was studied also. Solubilities in water at both 20 and 60°C have been tabulated."

From abstract: "Electrical measurements have been made on CaB6, SrB6, BaB6, YB2, YB4, YB6, and YB12 for the purpose of testing models of the electronic structure of the boron atoms in the four boride types represented. The compounds CaB6, SrB6, and BaB6 were found to be semiconductors. The Hall coefficients of YB4 was also measured, but could not be interpreted because the free electron theory does not provide a theoretical value for comparison with experiment. The results are in agreement with the models proposed."

From summary: "The report contains descriptions and discussions on nuclear safety testing."

Chemical engineering analysis and stress analysis for design of the 3 megawatt intermediate heat exchanger and steam generator for service with a liquid sodium heat transfer fluid.

Report describing the design, feasibility, and economic concerns of a small-scale reprocessing plant.