| 序号 | 专利名 | 申请号 | 申请日 | 公开（公告）号 | 公开（公告）日 | 发明人 |
|---|---|---|---|---|---|---|
| 181 | Nuclear Material Tracers | US12412284 | 2009-03-26 | US20100246740A1 | 2010-09-30 | Michael T. Kotschenreuther; Swadesh M. Mahajan; Prashant M. Valanju |
| Disclosed herein are embodiments of systems and methods for creating tracer nuclear materials. In one aspect, a Compact Fusion Neutron Source (CFNS) as described herein, can be used to create tracer isotopes to be added to fissile fuels to aid in anti-proliferation, though other methods of creating isotopes are contemplated. The generation of the isotopes require (n,2n) reactions, which can be caused by the high energy neutrons created by fusion. Potential tracer isotopes include U232, Th228 and Pu236, although other isotopes may be used. Such tracer isotopes can be created (such as by a CFNS), and then added to fissile materials at some stage of their processing. This abstract is intended for use as a scanning tool only and is not intended to be limiting. | ||||||
| 182 | Apparatuses and methods for production of radioisotopes in nuclear reactor instrumentation tubes | US12071455 | 2008-02-21 | US20090213977A1 | 2009-08-27 | William Earl Russell, II; Christopher J. Monetta; David Grey Smith; Russell Edward Stachowski |
| Example embodiments are directed to apparatuses and methods for producing radioisotopes in instrumentation tubes of operating commercial nuclear reactors. Irradiation targets may be inserted and removed from instrumentation tubes during operation and converted to radioisotopes otherwise unavailable from nuclear reactors. Example apparatuses may continuously insert, remove, and store irradiation targets to be converted to useable radioisotopes. | ||||||
| 183 | Placement of target rods in BWR bundle | US11987165 | 2007-11-28 | US20090135990A1 | 2009-05-28 | Cindy Fung Poon; Vernon W. Mills; William Earl Russell, II |
| Exemplary embodiments of the present invention are directed to the placement of one or more isotope production rods in a fuel bundle. The placement may be based on any one of, or a combination of, numerous factors such as relative location of core-monitoring equipment, the type of radioactive isotope being produced, the half-life or length of decay of the radioactive isotope, the neutron absorption rate of the target isotope to produce the radioactive isotope, the desired specific activity of the radioactive isotope being produced, the amount of neutron flux in different areas of the fuel bundle, the duration that the target isotope/radioactive isotope is expected to remain in the reactor until removed (i.e., harvested), etc. | ||||||
| 184 | DIRECT PRODUCTION OF THERMAL ANTINEUTRONS AND ANTIPROTONS | US11850106 | 2007-09-05 | US20080011966A1 | 2008-01-17 | Daniel Schaefer; James Snead |
| A method for obtaining free thermal antineutrons within the cage-like structure of a fullerene molecule comprising irradiating the fullerene molecule with free neutrons causing free neutrons to be trapped within the fullerene molecule wherein the trapped neutron oscillates between the neutron and antineutron states. A method for producing antiprotons comprising irradiating a fullerene molecule with free neutrons and trapping the neutrons within the fullerene molecule such that the neutrons oscillate between neutron and antineutron states and in the antineutron state decay and produce antiprotons. | ||||||
| 185 | Direct production of thermal antineutrons and antiprotons | US11158205 | 2005-06-21 | US20060039521A1 | 2006-02-23 | Daniel Schaefer; James Snead |
| A method for obtaining free thermal antineutrons within the cage-like structure of a fullerene molecule comprising irradiating the fullerene molecule with free neutrons causing free neutrons to be trapped within the fullerene molecule wherein the trapped neutron oscillates between the neutron and antineutron states. A method for producing antiprotons comprising irradiating a fullerene molecule with free neutrons and trapping the neutrons within the fullerene molecule such that the neutrons oscillate between neutron and antineutron states and in the antineutron state decay and produce antiprotons. | ||||||
| 186 | Method and apparatus for the ex-core production of nuclear isotopes in commercial PWRs | US10458479 | 2003-06-10 | US20040105520A1 | 2004-06-03 | Gary Shelton Carter |
| Method and apparatus for utilizing currently operating commercial electric Pressurized Water Reactor (PWR) core former plate cooling water flow holes for the ex-core production of nuclear isotopes. In operating PWRs with existing, or modified, core former plates (3) incorporating in-line coolant flow holes (4), it is possible to directly access and install isotope target materials inside an isotope target holder (2) that is connected to a flow enabler (1). The axial mid-plane of a flow enabler (1) would be located at the elevation of the core former plates (3). Thus by continuing the assembly of an isotope target holder (3) both above and below a flow enabler (1) such that a number of the isotope target holders (2) are located between the former plates, an isotope target holder assembly can be formed. The target holder assembly can then be directly inserted into, (or removed from) certain operating PWRs during normal reactor refueling operations. During refuel operations the upper flow holes (4) are exposed during the process of gaining access to the nuclear core. With the proposed ex-core isotope target holder assembly and integral flow enablers, a highly significant portion of the coolant flow can continue to pass through a selected series of in-line coolant flow holes (4). Thus commercial PWRs will be afforded a method and apparatus to produce commercially viable isotopes without any significant reactor equipment, refuel outage or fuel cycle management modifications. | ||||||
| 187 | Method and apparatus for producing radioisotopes | US10077204 | 2002-02-16 | US06678344B2 | 2004-01-13 | Patrick O'Leary; Claude W. Mays |
| A method and apparatus for optimizing the production of Pu-238 in a nuclear reactor during normal reactor operation is disclosed wherein the production of Pu-238 is confined to one or more selectively replaced fuel cells with target cells located in the inside of the active volume of the reactor core to maximize the neutron flux for target irradiation. The target cells are modified existing nuclear fuel assembly cells having some fuel rods replaced with target rods of Np-237 forming a cluster array and having rings of water filled rods surrounding the target cluster to produce the desired optimal Pu-238 production. | ||||||
| 188 | Method of separating and recovering rare FP in spent nuclear fuels and cooperation system for nuclear power generation and fuel cell power generation utilizing the same | US10157236 | 2002-05-30 | US20030099322A1 | 2003-05-29 | Masaki Ozawa; Yuichi Sano; Yoshihiko Shinoda |
| A method of separating and recovering useful rare FP contained in spent nuclear fuels (platinum group element (Ru, Rh, Pd), Ag, Tc, Se, Te) selectively and at high recovery percentage is provided. Nitric acid solution to be processed containing useful rare FP in spent nuclear fuels is electrolytically reduced by using Pd2null or Fe2null as a catalyst and rare FP are collectively deposited on an electrode and then deposits on the electrode are collectively dissolved by electrolytic oxidation. Then, the deposit-dissolved solution is electrolytically reduced at low current density, medium current density and high current density, successively, whereby Ag.Pd group, Se.Te group and Ru.Rh.Tc group are separately deposited and recovered, group by group. A cooperation system for nuclear power generation and fuel cell power generation can be provided by utilizing the recovered rare FP as electrode materials and production and purification catalysts for hydrogen fuel in fuel cell. | ||||||
| 189 | Method and apparatus for the transmutation of nuclear waste with tandem production of tritium | US10189995 | 2001-10-31 | US20030058980A1 | 2003-03-27 | El-Badawy A. El-Sharaway |
| The transmutation of radioactive material using a hybrid transmutation reactor is disclosed wherein a kinetic proton source is used to collisionally induce the transmutation of radioactive material with the generation of thermal neutrons as a byproduct. Additionally, a system and method for the production of Tritium utilizing the thermal neutrons generated in the transmutation process is further described. The present invention offers advantages and improvements over existing nuclear reactor technologies in that nuclear waste may be rendered inert, or otherwise at least partially deactivated and/or made less dangerous, with the substantially simultaneous production of energy and/or Tritium as a byproduct of the transmutation process. | ||||||
| 190 | Method for fabricating .sup.99 Mo production targets using low enriched uranium, .sup.99 Mo production targets comprising low enriched uranium | US911265 | 1997-08-14 | US6160862A | 2000-12-12 | Thomas C. Wiencek; James E. Matos; Gerard L. Hofman |
| A radioisotope production target and a method for fabricating a radioisotope production target is provided, wherein the target comprises an inner cylinder, a foil of fissionable material circumferentially contacting the outer surface of the inner cylinder, and an outer hollow cylinder adapted to receive the substantially foil-covered inner cylinder and compress tightly against the foil to provide good mechanical contact therewith. The method for fabricating a primary target for the production of fission products comprises preparing a first substrate to receive a foil of fissionable material so as to allow for later removal of the foil from the first substrate, preparing a second substrate to receive the foil so as to allow for later removal of the foil from the second substrate; attaching the first substrate to the second substrate such that the foil is sandwiched between the first substrate and second substrate to prevent foil exposure to ambient atmosphere, and compressing the exposed surfaces of the first and second substrate to assure snug mechanical contact between the foil, the first substrate and the second substrate. | ||||||
| 191 | Medical isotope production reactor | US339264 | 1994-11-10 | US5596611A | 1997-01-21 | Russell M. Ball |
| Medical isotopes are produced using a lower power, low cost nuclear reactor which permits the use of all the fission products produced in the reactor. Medical isotopes such as Molybdenum-99 are produced in a reactor operating at a power of 100 to 500 kilowatts. | ||||||
| 192 | Method and system for generating and collecting a radionuclide eluate | US3774035D | 1971-07-12 | US3774035A | 1973-11-20 | LITT G |
| A method and system for filling a vial with an eluate containing a radionuclide by coupling a vial containing a prepackaged amount of eluant to both an inlet to a radionuclide generator column and a vent outlet and coupling an evacuated vial to an outlet from the radionuclide column. The method and system may utilize a filter which includes an eluate repellent portion.
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| 193 | Purifying radioactive isotopes | US3438855D | 1966-12-02 | US3438855A | 1969-04-15 | FITZGERALD JOSEPH J |
| 194 | Polonium recovery | US44311465 | 1965-03-26 | US3271320A | 1966-09-06 | MOORE RAYMOND H |
| 195 | Method of preparing a gamma radiation material | US25661363 | 1963-02-06 | US3234099A | 1966-02-08 | BALDWIN GEORGE C; NEISSEL JOHN P; LEWI TONKS |
| 196 | Process for making high purity radioactive iodine-131 | US31853163 | 1963-10-24 | US3226298A | 1965-12-28 | GEMMILL WAYNE J |
| 197 | Yttrium-90 generator | US12126461 | 1961-06-30 | US3156532A | 1964-11-10 | DOERING ROBERT F; TUCKER WALTER D |
| 198 | IRRADIATION TARGET PROCESSING SYSTEM | EP16700970.3 | 2016-01-18 | EP3257053B1 | 2018-12-26 | RICHTER, Thomas Fabian; SYKORA, Alexander; KANNWISCHER, Wilfried; JAAFAR, Leila |
| An irradiation target processing system for insertion and retrieving irradiation targets into and from an instrumentation tube in a nuclear reactor core comprises, a target retrieving system, target insertion system and transport gas supply system, mounted on a movable support, wherein: the target retrieving system comprises a target exit port coupled to a target storage container and exhaust system; the target insertion system comprises a target filling device, target retention tubing with target supply junction connectable to the instrumentation tube, and a target diverter coupled to the target filling device, target retention tubing and target retrieving system; and the transport gas supply system comprises a first gas supply tubing coupled to the exit port of the target retrieving system, a second gas supply tubing coupled to a junction for supplying gas to the instrumentation tube, and a transport gas supply junction coupled to the first and second gas supply tubing. | ||||||
| 199 | METHOD FOR PRODUCING BETA EMITTING RADIOPHARMACEUTICALS | EP14833237.2 | 2014-12-18 | EP3100279B1 | 2018-10-10 | ANDRIGHETTO, Alberto |
| The present invention relates to a method for producing beta emitting radiopharmaceuticals. The method provides to produce, through a primary accelerator, a low energy proton beam, namely with an energy lower than 70 MeV, preferably with an energy ranging from 32 to 45 MeV, more preferably with energy ranging from 38 to 42 MeV; the low energy proton beam is irradiated on a source target so as to generate a neutral atom beam; the neutral atoms are ionized, extracted by acceleration and preferably subjected to a first focusing; the first focused beam is subjected to a mass separation such to generate a isobaric beam of radioisotopes. The isobaric beam therefore is preferably subjected to a second focusing and it is sent for a predetermined time on a deposition target. Then the irradiated deposition target is subjected to chemical treatment so as to obtain pure beta emitting radiopharmaceuticals. | ||||||
| 200 | TARGETED ISOTOPE PRODUCTION SYSTEM | EP15818657.7 | 2015-01-27 | EP3167457B1 | 2018-08-29 | GULER, Cenk; HEIBEL, Michael D.; CONGEDO, Thomas V.; SUTTON, Joanna C. |
| A system and method for employing the in-core movable detectors of a commercial nuclear powered electric generating facility to transmute a user-specified target material into a desired isotope. The process is conducted remotely resulting in a shielded end product available for shipment for further processing. | ||||||
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