Thermal neutron flux perturbation by dysprosium-aluminum foils in water and uranyl fluoride - water solutions
Thermal neutron flux perturbation measured for dysprosium-aluminum alloy in water and in uranyl fluoride solution
RADIATION MEASUREMENT↗
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Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
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Uranyl phthalocyanines show promise in the treatment of brain tumors
Processes synthesize sulfonated and nonsulfonated uranyl phthalocyanines for application in neutron therapy of brain tumors. Tests indicate that the compounds are advantageous over the previously used boron and lithium compounds.
Frigerio, N. A.↗
Analysis of uranyl fluoride solution reactors containing voided tubes
Critical experiments analysis of uranyl fluoride solution reactors containing large-diameter voided tubes
Mayo, W.↗
Criticality experiments and analysis of molybdenum reflected cylindrical uranyl fluoride water solution reactors
Clean criticality data were obtained from molybdenum-reflected cylindrical uranyl-fluoride-water solution reactors. Using ENDF/B molybdenum cross sections, a nine energy group two-dimensional transport calculation of a reflected reactor configuration predicted criticality to within 7 cents of the experimental value. For these reactors, it was necessary to compute the reflector resonance integral by a detailed transport calculation at the core-reflector interface volume in the energy region of the two dominant resonances of natural molybdenum.
Fieno, D.↗
Critical mass studies with the NASA Zero Power Reactor II. II - Heterogeneous arrays of cylindrical voids
Zero Power Reactor II used for determining critical cylindrical configurations of aqueous uranyl fluoride that contain heterogeneous arrays of void
CRITICAL MASS↗
Simple colorimetric method determines uranium in tissue
Simple colorimetric micromethod determines concentrations of uranium in tissue. The method involves dry ashing organic extraction, and colorimetric determination of uranyl ferrocyanide. This uranium determination technique could be used in agricultural research, tracer studies, testing of food products, or medical research.
Doran, D.↗
Fast neutron reactivity effects for refractory metallic samples measured in a thermal homogeneous reactor
Fast neutron reactivity effects of reactor materials measured in thermal uranyl fluoride-water-solution reactor
Pierce, C. R.↗
Movable-molybdenum-reflector reactivity experiments for control studies of compact space power reactor concepts
An experimental reflector reactivity study was made with a compact cylindrical reactor using a uranyl fluoride - water fuel solution. The reactor was axially unreflected and radially reflected with segments of molybdenum. The reflector segments were displaced incrementally in both the axial and radial dimensions, and the shutdown of each configuration was measured by using the pulsed-neutron source technique. The reactivity effects for axial and radial displacement of reflector segments are tabulated separately and compared. The experiments provide data for control-system studies of compact-space-power-reactor concepts.
Fox, T. A.↗
Removal of histological sections from glass for electron microscopy - Use of Quetol 651 resin and heat
A number of approaches have been used to separate stained conventional histological sections from glass slides in preparation for a study with the electron microscope. However, in each reported case some problems were encountered with respect to the separation process. The present investigation is concerned with the use of the epoxy resin Quetol 651 as an embedding medium for this procedure, taking into account the simple application of heat (62-64 C) for performing the separation step. After the tissue has been removed from the glass by the considered technique, it is thin sectioned, and stained with uranyl acetate-lead citrate.
Kraft, L. M.↗
Consistent Pl Analysis of Aqueous Uranium-235 Critical Assemblies
The lethargy-dependent equations of the consistent Pl approximation to the Boltzmann transport equation for slowing down neutrons have been used as the basis of an IBM 704 computer program. Some of the effects included are (1) linearly anisotropic center of mass elastic scattering, (2) heavy element inelastic scattering based on the evaporation model of the nucleus, and (3) optional variation of the buckling with lethargy. The microscopic cross-section data developed for this program covered 473 lethargy points from lethargy u = 0 (10 Mev) to u = 19.8 (0.025 ev). The value of the fission neutron age in water calculated here is 26.5 square centimeters; this value is to be compared with the recent experimental value given as 27.86 square centimeters. The Fourier transform of the slowing-down kernel for water to indium resonance energy calculated here compared well with the Fourier transform of the kernel for water as measured by Hill, Roberts, and Fitch. This method of calculation has been applied to uranyl fluoride - water solution critical assemblies. Theoretical results established for both unreflected and fully reflected critical assemblies have been compared with available experimental data. The theoretical buckling curve derived as a function of the hydrogen to uranium-235 atom concentration for an energy-independent extrapolation distance was successful in predicting the critical heights of various unreflected cylindrical assemblies. The critical dimensions of fully water-reflected cylindrical assemblies were reasonably well predicted using the theoretical buckling curve and reflector savings for equivalent spherical assemblies.
Fieno, Daniel↗