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Segrè Page · Resources with Additional Information
US 2,206,634 PROCESS FOR THE PRODUCTION OF RADIOACTIVE SUBSTANCES -- Fermi, E. ; Amaldi, E. ; Rasetti, F. ; Segrè, E. ; Pontecorvo, B.; July 2, 1940 (to the U.S. Atomic Energy Commission)
The process, for production of isotopes including transuranic elements by reaction of neutrons, employs means for generating neutrons having a high average energy, slowing down and scattering the neutrons by projecting them though a medium of an element of a class including H, He, Be, C, Si, and Pb, and then passing the neutrons into a mass of material containing an element capable of forming a radioactive isotope by neutron capture, including radioactive isotopes capable of emitting β rays.
US 2,491,220 NEUTRON DETECTOR – Segrè, Emilio G.; Wiegand, Clyde E.; December 13, 1949 (to the U.S. Atomic Energy Commission)
An improved neutron detector of extreme sensitivity to detect the presence of small numbers of neutrons is described; all γ-ray effects on the meter are eliminated. The instrument consists of a long metal tube, open at one end, and a second superimposed tube (enclosed within a material designed to slow fast neutrons) having elongated lateral walls, an enclosing end wall and an open end. A gas impermeable barrier is provided between the open end of the second tube and the opposite exterior wall of the first tube, and a gas medium (boron tri-fluoride at increased pressure) with a low capture cross section with respect to fast neutrons and a high cross section with respect to thermal energy neutrons is sealed between the two tubes; an electrical potential is maintained between the two tubes. The slowed neutrons cause α-particle emission in the medium, subsequent ionization and potential discharge in the medium and ultimate detection.
A detector of two metal cylinders co-axially mounted, the inner cylinder being open at one end and the space between the inner and outer cylinder being closed and filled with boron tri-fluoride at a pressure of about 2 atm. The large cylinder is connected to the negative side of a high voltage supply and the inner cylinder to the positive side. A neutron slowing material such as paraffin completely surrounds the outer cylinder. The instrument is particularly adapted to detecting thermal neutrons from weak sources in the presence of gamma radiation.
US 2,493,935 HIGH ENERGY NEUTRON COUNTER – Wiegand, Clyde E.; Segrè, Emilio G.; January 10, 1950 (to the U.S. Atomic Energy Commission)
An ion chamber utilizing bismuth for the measurement of high energy neutrons. The ion chamber contains a series of parallel aluminum plates which are covered with a layer of bismuth. An electrical potential is applied between alternate plates. The presence of high energy neutrons is indicated by the fission of bismuth and subsequent ionization of the filling gas and conduction between the plates.
US 2,521,656 IONIZATION CHAMBER – Segrè, E. G.; Chamberlain, O.; September 5, 1950 (to the U.S. Atomic Energy Commission)
This patent is concerned with an improved ion chamber wherein hydrogenous material performs the dual function of insulatingly supporting the various metal portions of the chamber while substantially filling the interior portion of the chamber to provide improved scattering, diffusing, and slowing of fast neutrons to thermal energies.
US 2,573,069 METHOD AND APPARATUS FOR MEASURING STRONG ALPHA EMITTERS – Segrè, E. G.; October 30, 1951 (to the U.S. Atomic Energy Commission)
This patent describes an apparatus and method for the determination of the strength of a strong alpha emitter. The apparatus is so arranged that the alpha particles impinge upon a material which emits neutrons as a result of such bombardment. The neutrons so obtained in turn impinge upon a monitoring material and cause radioactivity in such monitoring material. By determining the amount of radioactivity in the last-named material under standardized conditions, one obtains the relative strength of the alpha emitter.
US 2,597,535 RADIOACTIVE ASSAY APPARATUS – Segrè, E. G.; May 20, 1952 (to the U.S. Atomic Energy Commission)
This suitably shielded apparatus, adapted to assay fissionable material, is so designed that a single source of neutrons may be utilized to simultaneously irradiate one or more of a plurality of samples of fissionable material placed in separate ionization chambers positioned around the neutron source.
US 2,849,285 METHOD FOR PURIFYING URANIUM – Kennedy, J. W.; Segrè, E. G.; August 26, 1958 (to the U.S. Atomic Energy Commission)
A method is presented for obtaining a compound of uranium in an extremely pure state and in such a condition that it can be used in determinations of the isotopic composition of uranium. Uranium deposited in calutron receivers is removed therefrom by washing with cold nitric acid and the resulting solution, containing uranium and trace amounts of various impurities, such as Fe, Ag, Zn, Pb, and Ni, is then subjected to various analytical manipulations to obtain an impurity-free uranium containing solution. This solution is then evaporated on a platinum disk and the residue is ignited converting it to U3O8. The platinum disk having such a thin film of pure U3O8 is suitable for use with isotopic determination techniques.
US 2,908,621 PRODUCING ENERGY AND RADIOACTIVE FISSION PRODUCTS – Segrè, E.; Kennedy, J. W.; Seaborg, G. T.; October 13, 1959 (to the U.S. Atomic Energy Commission)
This patent broadly discloses the production of plutonium by the neutron bombardment of uranium to produce neptunium which decays to plutonium, and the fissionability of plutonium by neutrons, both fast and thermal, to produce energy and fission products.
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