Techniques for on-demand production of medical isotopes such as Mo-99/Tc-99m and radioactive iodine isotopes including I-131
원문보기
IPC분류정보
국가/구분
United States(US) Patent
등록
국제특허분류(IPC7판)
G21G-001/00
G21G-001/06
G21G-001/08
출원번호
US-0627977
(2015-02-20)
등록번호
US-9576691
(2017-02-21)
발명자
/ 주소
Tsang, Francis Y
출원인 / 주소
Global Medical Isotope Systems LLC
대리인 / 주소
Knobbe, Martens, Olson & Bear, LLP
인용정보
피인용 횟수 :
0인용 특허 :
12
초록▼
A system for radioisotope production uses fast-neutron-caused fission of depleted or naturally occurring uranium targets in an irradiation chamber. Fast fission can be enhanced by having neutrons encountering the target undergo scattering or reflection to increase each neutron's probability of causi
A system for radioisotope production uses fast-neutron-caused fission of depleted or naturally occurring uranium targets in an irradiation chamber. Fast fission can be enhanced by having neutrons encountering the target undergo scattering or reflection to increase each neutron's probability of causing fission (n, f) reactions in U-238. The U-238 can be deployed as one or more layers sandwiched between layers of neutron-reflecting material, or as rods surrounded by neutron-reflecting material. The gaseous fission products can be withdrawn from the irradiation chamber on a continuous basis, and the radioactive iodine isotopes (including I-131) extracted.
대표청구항▼
1. Apparatus for producing radioactive iodine isotopes comprising: a neutron generator that is not a nuclear reactor;an irradiation chamber comprising a number of regions configured to receive NEU material to be fissioned upon irradiation by neutrons generated by the neutron generator, at least one
1. Apparatus for producing radioactive iodine isotopes comprising: a neutron generator that is not a nuclear reactor;an irradiation chamber comprising a number of regions configured to receive NEU material to be fissioned upon irradiation by neutrons generated by the neutron generator, at least one non-moderating neutron-reflecting region, a gas inlet port, and a gas outlet port;wherein the gas inlet port, the gas outlet port, and the number of regions configured to receive NEU material are in gas communication; andwherein the at least one non-moderating neutron-reflecting region comprises one or more walls of the irradiation chamber formed of non-moderating neutron-reflecting material. 2. The apparatus of claim 1 wherein the neutron generator provides neutrons with an energy above a fast fission threshold for U-238. 3. The apparatus of claim 1 wherein the mechanism for separating at least some of the radioactive iodine comprises a silver zeolite trap. 4. The apparatus of claim 1, and wherein the at least one non-moderating neutron-reflecting region comprises at least one interior non-moderating neutron-reflecting region disposed within the irradiation chamber and further comprises one or more walls of the irradiation chamber; wherein the at least one non-moderating neutron-reflecting region is configured to increase the path length traveled by at least some of the neutrons before those neutrons leave the irradiation chamber. 5. The apparatus of claim 1 wherein the NEU material comprises depleted uranium material. 6. The apparatus of claim 1 wherein the NEU material comprises one of the following forms: solid material, crushed solid material, metallic shavings, metallic filings, sintered pellets, liquid solutions, molten salts, molten alloys, slurries, sheets, plates, rods, and granular material. 7. The apparatus of claim 1 wherein the irradiation chamber further comprises a fill port configured to allow the introduction of the NEU material and a drain port configured for removal of the NEU material. 8. The apparatus of claim 1 wherein the irradiation chamber comprises at least two sections. 9. Apparatus for producing radioactive iodine comprising: a compact, stand-alone neutron generator;an irradiation chamber, the irradiation chamber comprises at least one region configured to receive NEU material to be fissioned upon irradiation by neutrons generated by the neutron generator, at least one non-moderating neutron-reflecting region, a gas inlet, and a gas outlet;means for introducing a carrier gas into the gas inlet to form a gas mixture with a fission products;means for withdrawing the gas mixture from the gas outlet;means for separating at least a portion of the fission products from the gas mixture; andwherein the at least one non-moderating neutron-reflecting region comprises one or more walls of the irradiation chamber formed of non-moderating neutron-reflecting material. 10. The apparatus of claim 9 wherein the compact, stand-alone neutron generator provides neutrons with an energy above a fast fission threshold for U-238. 11. The apparatus of claim 9 wherein the means for separating at least a portion of the fission products comprises a silver zeolite trap. 12. The apparatus of claim 9 wherein the NEU material comprises one of the following forms: solid material, crushed solid material, metallic shavings, metallic filings, sintered pellets, liquid solutions, molten salts, molten alloys, slurries, sheets, plates, rods, and granular material. 13. The apparatus of claim 9 wherein the NEU material comprises depleted uranium material. 14. The apparatus of claim 9 wherein the irradiation chamber further comprises a fill port configured to allow the introduction of the NEU material and a drain port configured for removal of the NEU material. 15. The apparatus of claim 9 wherein the irradiation chamber comprises at least two sections. 16. The apparatus of claim 1 wherein the NEU material comprises NEU in the form of flat plates. 17. The apparatus of claim 1 wherein the irradiation chamber comprises a rectangular-prism-shaped irradiation chamber. 18. The apparatus of claim 9 wherein the NEU material comprises NEU in the form of flat plates. 19. The apparatus of claim 9 wherein the irradiation chamber comprises a rectangular-prism-shaped irradiation chamber.
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이 특허에 인용된 특허 (12)
Marwick Edward F. (5149 Morse Ave. Skokie IL 60077) Juhl Nis H. (5405 Wallbridge Midland MI 48640), Contained fission explosion breeder reactor system.
Schmitt Jerome J. (265 College St. (12N) New Haven CT 06510), Method and apparatus for the deposition of solid films of a material from a jet stream entraining the gaseous phase of s.
Anav Maurice (Villemoisson-sur-Orge FRX) Duhayon Jacques (Clamart FRX) Goumondy Jean-Pierre (Vitry-sur-Seine FRX) Leseur Andre (Fontenay-aux-Roses FRX) Zellner Edmond (Gif-sur-Yvette FRX), Method of extraction, trapping and storage of radioactive iodine contained in irradiated nuclear fuels.
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