EA200101225A1 - METHOD OF OBTAINING ENERGY BY DIVIDING FROM RADIOACTIVE WASTE - Google Patents
METHOD OF OBTAINING ENERGY BY DIVIDING FROM RADIOACTIVE WASTEInfo
- Publication number
- EA200101225A1 EA200101225A1 EA200101225A EA200101225A EA200101225A1 EA 200101225 A1 EA200101225 A1 EA 200101225A1 EA 200101225 A EA200101225 A EA 200101225A EA 200101225 A EA200101225 A EA 200101225A EA 200101225 A1 EA200101225 A1 EA 200101225A1
- Authority
- EA
- Eurasian Patent Office
- Prior art keywords
- reaction
- energy
- mev
- accelerator
- nuclear fuel
- Prior art date
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
- G21G1/04—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators
- G21G1/12—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators by electromagnetic irradiation, e.g. with gamma or X-rays
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- Particle Accelerators (AREA)
- Physical Or Chemical Processes And Apparatus (AREA)
Abstract
Предложен способ, согласно которому в линейном ускорителе в предпочтительном варианте монохроматического типа производят ускорение электронов до энергии около 10 МэВ, которые направляют на мишень из вещества, имеющего большой атомный номер Z, например из вольфрама, осуществляя генерацию гамма-излучения. Это излучение направляют на вещество, служащее в качестве ядерного топлива, например на уран-238 (U), что приводит к возникновению реакции (γ,f), в результате которой высвобождается энергия около 200 МэВ. Чтобы ядерный реактор, созданный согласно этому принципу, развивал мощность около 20 МВт, необходимо создавать возбуждение посредством ускорителя с мощностью 1 МВт. Реакция не является самоподдерживающейся и останавливается при прекращении подачи пучка. Ядерный реактор с возбуждением посредством ускорителя может быть легко использован для "сжигания" отработанного ядерного топлива, полученного из ядерных реакторов деления, в том случае, когда его функционирование осуществляют при энергии 10 МэВ. Реакция фотонного деления приводит к фоторасщеплению таких типичных побочных продуктов отработанного ядерного топлива, как цезий-137 (Cs) и стронций-90 (Sr), посредством реакции (n,γ), в результате чего получают короткоживущие или устойчивые продукты реакции.Отчет о международном поиске был опубликован 2002.06.13.A method is proposed according to which in a linear accelerator, in the preferred embodiment of a monochromatic type, electrons are accelerated to an energy of about 10 MeV, which are sent to a target from a substance having a large atomic number Z, for example from tungsten, through gamma radiation. This radiation is directed to a substance that serves as a nuclear fuel, for example, to uranium-238 (U), which leads to the reaction (γ, f), as a result of which energy of about 200 MeV is released. In order for a nuclear reactor constructed according to this principle to develop a power of about 20 MW, it is necessary to create an excitation through an accelerator with a power of 1 MW. The reaction is not self-sustaining and stops when the beam is stopped. A nuclear reactor with excitation through an accelerator can be easily used to "burn" spent nuclear fuel obtained from nuclear fission reactors, in the case when its operation is carried out at an energy of 10 MeV. The photon fission reaction leads to the photodisintegration of such typical by-products of spent nuclear fuel, such as cesium-137 (Cs) and strontium-90 (Sr), by means of the (n, γ) reaction, which results in short-lived or stable reaction products. The search was published on 2002.06.13.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US31670099A | 1999-05-21 | 1999-05-21 | |
| PCT/US2000/013922 WO2000072329A2 (en) | 1999-05-21 | 2000-05-19 | Apparatus for generating power from fission of spent nuclear waste |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| EA200101225A1 true EA200101225A1 (en) | 2003-06-26 |
Family
ID=23230263
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| EA200101225A EA200101225A1 (en) | 1999-05-21 | 2000-05-19 | METHOD OF OBTAINING ENERGY BY DIVIDING FROM RADIOACTIVE WASTE |
Country Status (18)
| Country | Link |
|---|---|
| EP (1) | EP1234309A2 (en) |
| JP (1) | JP2003525424A (en) |
| KR (1) | KR20020043456A (en) |
| CN (1) | CN1421037A (en) |
| AU (1) | AU5149600A (en) |
| BG (1) | BG106217A (en) |
| BR (1) | BR0011595A (en) |
| CA (1) | CA2371484A1 (en) |
| CZ (1) | CZ20014161A3 (en) |
| EA (1) | EA200101225A1 (en) |
| FI (1) | FI20012249A (en) |
| HU (1) | HUP0301807A2 (en) |
| IL (1) | IL146657A0 (en) |
| MX (1) | MXPA01011907A (en) |
| NO (1) | NO20015656L (en) |
| PL (1) | PL364809A1 (en) |
| SK (1) | SK16862001A3 (en) |
| WO (1) | WO2000072329A2 (en) |
Families Citing this family (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101469374B (en) * | 2007-12-29 | 2011-03-02 | 中国核动力研究设计院 | Method and equipment for extracting medical strontium-89 from homogenous water solution nuclear reactor gas loop |
| US8320513B2 (en) | 2009-04-16 | 2012-11-27 | The Invention Science Fund I, Llc | Nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system |
| KR101690349B1 (en) * | 2009-04-16 | 2016-12-27 | 테라파워, 엘엘씨 | A nuclear fission reactor, flow control assembly, methods therefor and a flow control assembly system |
| US9613726B2 (en) | 2009-05-28 | 2017-04-04 | Northrop Grumman Systems Corporation | Systems and methods for reducing the storage time of spent nuclear fuel |
| ITGE20120004A1 (en) * | 2012-01-16 | 2013-07-17 | Clean Nuclear Power Llc | NUCLEAR REACTOR WORKING WITH A NUCLEAR FUEL CONTAINING ATOMES OF ELEMENTS HAVING LOW ATOMIC NUMBER AND LOW NUMBER OF MASS |
| WO2015077554A1 (en) * | 2013-11-21 | 2015-05-28 | Stuart Martin A | Dielectric wall accelerator and applications and methods of use |
| WO2015160407A2 (en) * | 2014-01-22 | 2015-10-22 | Bodi Robert F | Method and system for generating electricity using waste nuclear fuel |
| CN113238270A (en) * | 2021-06-25 | 2021-08-10 | 清华大学 | Detection method, device, system, equipment and medium for uranium ore |
| US20230411034A1 (en) * | 2022-06-15 | 2023-12-21 | Westinghouse Electric Company Llc | Use of sub-critical neutron multiplication driven by electronic neutron generators to produce radioisotopes |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4713581A (en) * | 1983-08-09 | 1987-12-15 | Haimson Research Corporation | Method and apparatus for accelerating a particle beam |
| JPH0638119B2 (en) * | 1989-03-02 | 1994-05-18 | 動力炉・核燃料開発事業団 | Radioactive waste extinction processing device and extinction processing method |
| RU2003191C1 (en) * | 1993-01-18 | 1993-11-15 | Игорь Петрович Еремеев | Method of transmutation of isotopes |
| WO2000000986A1 (en) * | 1998-06-26 | 2000-01-06 | Brown Paul M | Remediation of radioactive waste by stimulated radioactive decay |
-
2000
- 2000-05-19 CZ CZ20014161A patent/CZ20014161A3/en unknown
- 2000-05-19 CA CA002371484A patent/CA2371484A1/en not_active Abandoned
- 2000-05-19 CN CN00810605A patent/CN1421037A/en active Pending
- 2000-05-19 PL PL00364809A patent/PL364809A1/en not_active Application Discontinuation
- 2000-05-19 MX MXPA01011907A patent/MXPA01011907A/en not_active Application Discontinuation
- 2000-05-19 KR KR1020017014905A patent/KR20020043456A/en not_active Application Discontinuation
- 2000-05-19 HU HU0301807A patent/HUP0301807A2/en unknown
- 2000-05-19 AU AU51496/00A patent/AU5149600A/en not_active Abandoned
- 2000-05-19 SK SK1686-2001A patent/SK16862001A3/en unknown
- 2000-05-19 WO PCT/US2000/013922 patent/WO2000072329A2/en not_active Application Discontinuation
- 2000-05-19 EA EA200101225A patent/EA200101225A1/en unknown
- 2000-05-19 BR BR0011595-9A patent/BR0011595A/en not_active Application Discontinuation
- 2000-05-19 JP JP2000620637A patent/JP2003525424A/en active Pending
- 2000-05-19 IL IL14665700A patent/IL146657A0/en unknown
- 2000-05-19 EP EP00936135A patent/EP1234309A2/en not_active Withdrawn
-
2001
- 2001-11-20 FI FI20012249A patent/FI20012249A/en unknown
- 2001-11-20 NO NO20015656A patent/NO20015656L/en not_active Application Discontinuation
- 2001-12-13 BG BG106217A patent/BG106217A/en unknown
Also Published As
| Publication number | Publication date |
|---|---|
| AU5149600A (en) | 2000-12-12 |
| NO20015656L (en) | 2002-01-15 |
| WO2000072329A2 (en) | 2000-11-30 |
| HUP0301807A2 (en) | 2003-09-29 |
| FI20012249A (en) | 2002-01-21 |
| SK16862001A3 (en) | 2002-07-02 |
| CZ20014161A3 (en) | 2002-06-12 |
| PL364809A1 (en) | 2004-12-13 |
| WO2000072329A3 (en) | 2002-06-13 |
| MXPA01011907A (en) | 2009-08-31 |
| NO20015656D0 (en) | 2001-11-20 |
| CA2371484A1 (en) | 2000-11-30 |
| BG106217A (en) | 2002-07-31 |
| JP2003525424A (en) | 2003-08-26 |
| BR0011595A (en) | 2003-07-01 |
| EP1234309A2 (en) | 2002-08-28 |
| KR20020043456A (en) | 2002-06-10 |
| IL146657A0 (en) | 2002-07-25 |
| CN1421037A (en) | 2003-05-28 |
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