CN101377962B - Fusion drive subcritical system and method for producing 252Cf neutron source - Google Patents
Fusion drive subcritical system and method for producing 252Cf neutron source Download PDFInfo
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- CN101377962B CN101377962B CN2008101566393A CN200810156639A CN101377962B CN 101377962 B CN101377962 B CN 101377962B CN 2008101566393 A CN2008101566393 A CN 2008101566393A CN 200810156639 A CN200810156639 A CN 200810156639A CN 101377962 B CN101377962 B CN 101377962B
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Abstract
The invention discloses a method and a system for producing a <252>Cf neutron source by a fusion-driven sub-critical system, the external neutron source is: D-T fusion neutron source; a fuel cycle mode is a U-Pu cycle mode, and the fusion-driven sub-critical system of the U-Pu cycle mode has higher neutron flux. The structure of a cladding layer is as follows: an actinide nuclide treatment area, a target area, a fissile fuel proliferation area or the fissile fuel proliferation area, a fission product treatment area and a reflection and shielding area are sequentially surrounded at the outside of a generation area of the external neutron source, and the various areas are separated by using structural materials. The target area adopts helium as a cooling agent, reaction substances of the target area are formed by stacking in small sphere shape, and the volume of total solids accounts for 60 percent to 90 percent of the total volume. A target ball is taken out after materials of the target area are continuously radiated for about one year in the fusion-driven sub-critical system; the <252>Cf has short half-life and can not be radiated for a long time.
Description
Technical field
The invention belongs to the nuclear energy technology field, is a kind of production
252The system and method for Cf neutron source.
Background technology
The 1950's, U.S. scientist has found for the first time
252The Cf element.
252Cf belongs to the actinium series nucleic, is the tenth element of actinium series nucleic in the periodic table of elements.Afterwards, country such as America and Soviet Union carried out a large amount of about
252Transplutonium nucleic research work such as Cf.
252The applied research of Cf element has obtained the progress of advancing by leaps and bounds, and its range of application expands to aspects such as biomedicine, geologic prospecting from nuclear industry.But, global
252Cf output is very low, about several grams of annual production.
252Cf can spontaneous fission discharge neutron, and neutron yield is 2.31 * 10
12s
-1.g
-1, 2.65 half life period, average energy 2.15MeV.
252Cf costs an arm and a leg, and is the most expensive in the world present metal.
In the nuclear industry field,
252Cf can be used as the neutron source of reactor start up.Can be used to treat malignant tumour at the field of nuclear medicine.Because
252Cf neutron source can be done very little very carefully, and this is that other neutron source is not accomplished, so deliver to organ tumor position in the body cavity to neutron source through flexible pipe, perhaps is implanted in the tumor tissues of human body and treats.Particularly to the cancer of the uterus, carcinoma of mouth, the carcinoma of the rectum, cancer of the esophagus, cancer of the stomach, CARCINOMA OF THE NASAL CAVITY etc.,
252The Cf neutron therapy all has goodish curative effect.At geological exploration field, adopt
252Cf is as neutron source, and the situation of surveying oil, gas, water layer, natural gas reservoir is highly effective,
252Cf neutron source can also be used to exploring mineral reserve such as boron, copper, silver, manganese, tungsten, mercury and REE.
252The neutron that Cf neutron source is emitted is prone to captured and produce gamma-rays by other materials after the collision slowing down, according to the gamma-rays characteristic of measurement, judges the type of mineral matter.
At present,
252Cf produces syntheticly has three kinds with working method: utilize accelerator to synthesize, utilize underground nuclear test thermonuclear explosion method and utilize reactor irradiation transuranic element target to produce through capturing neutron and β decay continuously
252Cf.But accelerator is synthetic
252Cf output is very low, generally is unweighable.Utilize thermonuclear explosion production
252The working method of Cf, spend too big, suitable for mass production not.Transuranic element is placed on the reactor internal radiation, and target nucleus is captured neutron continuously and also taken place repeatedly to decay and generate
252Cf,
239Pu,
242Pu,
241Am with
244Cm etc. can be as target material.The pile neutron flux is to determine it
252An essential condition of Cf yield improves neutron flux, can make
252Cf output increases rapidly.Reactor is to have production
252The ability of Cf is put waste material but fission reactor itself produces a large amount of height.
Summary of the invention
The purpose of this invention is to provide a kind of production
252The method of Cf neutron source and production
252The subcritical system that the fusion of Cf neutron source drives.Nuclear explosion thermonuclear reaction production and fission reactor production have been taken into account
252The advantage of two kinds of methods of Cf, fusion drive subcritical system has higher flux, has made full use of existing nuke rubbish simultaneously, can not produce other nuke rubbish again, and system is in subcritical state, has guaranteed security.
Technical scheme of the present invention is following:
Fusion drive subcritical system is produced
252The method of Cf neutron source; It is characterized in that producing outer source neutron through fusion reaction; These outer source neutrons get into actinium series nucleic treatment regions, and wherein from the long-life actinium series nucleic of Nuclear Power Station's Exhausted Fuels and fissionable plutonium 239 fission reactions take place and produce the new neutron of a large amount of several keV to the hundreds of keV energy range, and these new neutrons get in target areas; With wherein americium 241, curium 244 capture reaction takes place, target nucleus is captured neutron continuously and is also taken place repeatedly to decay and generate
252Cf; The neutron that leaks through the target area gets in the fissionable fuel breeding blanket, with wherein depleted uranium or natural uranium generation neutron-capture reaction, generates fissionable plutonium 239, and extracts plutonium 239 and use with the recycle of supplying with actinium series nucleic treatment region; Reflection and shadow zone are arranged outside the fissionable fuel breeding blanket, and the heat that produces in each district adopts coolant cools, adopts structured material to separate between each district.
Described fusion drive subcritical system production
252The method of Cf neutron source; It is characterized in that the neutron that leaks from the fissionable fuel breeding blanket gets into the fission product treatment region; With the radioactive fission product generation capture reaction that wherein is blended in the neutron moderator; Highly toxic fission product of long-life is transformed into stablizes avirulence or the hypotoxic fission product of short life, the fissionable fuel breeding blanket is coated with structured material, and reflection is positioned at outside the fission product treatment region with the shadow zone.
Described fusion drive subcritical system production
252The method of Cf neutron source; It is characterized in that fusion reaction is meant the D-T fusion reaction; Comprise long-life actinium series nucleic and fissionable plutonium 239 in the actinium series nucleic treatment region from Nuclear Power Station's Exhausted Fuels; Exist with oxide, nitride, carbonide or metal form, concrete content can require to decide through solving system neutron-transport equation and burn up equation in the reload variation limitation of time cycle of operation according to system power density, system's critical factor and they; The target area adopts high-pressure helium as cooling medium, and other district adopts high-pressure helium or Li-Pb alloy as cooling medium, and the reactive material americium 241 of target area, curium 244 are piled up with pellet shapes and formed, and americium 241, curium 244 total solid volumes account for 60%～90% of target area inner volume; Neutron moderator is selected graphite or heavy water for use.
Produce
252The fusion drive subcritical system in Cf source; It is characterized in that: neutron source produces outside the district and is surrounded by actinium series nucleic treatment region successively, target area, fissionable fuel breeding blanket or fissionable fuel breeding blanket, fission product treatment region outside; Separate with structured material between each district reflection and shadow zone; Actinium series nucleic treatment region comprises: long-life actinium series nucleic and fissionable plutonium 239 potpourris and clad structure material from Nuclear Power Station's Exhausted Fuels place cooling medium; The fissionable fuel breeding blanket comprises: natural uranium or depleted uranium and clad structure material place cooling medium; The target area comprises: americium 241, curium 244 elements and clad structure material place cooling medium; The fission product treatment region comprises: height is put fission product and clad structure material, neutron moderator, places cooling medium; Reflection is made up of graphite, boron carbide, stainless steel, lead etc. with the shadow zone, and structured material is meant graphite, silit or steel.
Described production
252The fusion drive subcritical system in Cf source is characterized in that described outer neutron source region is spherical or almost spherical, and ball is surrounded by structured material outward; The actinium series nucleic treatment region that surrounds successively outside the outer neutron source region; The target area, fissionable fuel breeding blanket or fissionable fuel breeding blanket, fission product treatment region, reflection and shadow zone; Its outside surface is spherical or almost spherical, separates through clad structure material separately between each district.
Described production
252The fusion drive subcritical system in Cf source is characterized in that described outer neutron source region is a cylindrical or near cylindrical, and cylinder is coated with structured material; The actinium series nucleic treatment region that surrounds successively outside the outer neutron source region; The target area, fissionable fuel breeding blanket or fissionable fuel breeding blanket, fission product treatment region, reflection and shadow zone; Its outside surface is cylindrical or near cylindrical, separates through clad structure material separately between each district.
Described production
252The fusion drive subcritical system in Cf source is characterized in that described outer neutron source region is an annular ring or sub-circular circle, and annular ring is surrounded by structured material outward; The actinium series nucleic treatment region that surrounds successively outside the outer neutron source region; The target area, fissionable fuel breeding blanket or fissionable fuel breeding blanket, fission product treatment region, reflection and shadow zone; Its outside surface is annular ring or sub-circular circle, separates through clad structure material separately between each district.
The U-Pu recycle design that system adopts fusion to drive, the fusion drive subcritical system of U-Pu recycle design has higher neutron flux, and neutron flux can reach 1E+15cm
-2s
-1Magnitude.
Americium 241, curium 244 are converted into through neutron irradiation in fusion drive subcritical system
252The process of Cf is formula as follows:
Americium 241 in the target area, curium 244 elements are that radioactive fission product refers to from the fission Nuclear Power Station's Exhausted Fuels
99Tc,
129I,
137Cs etc.
Behind the about year of target area material Continuous irradiation in fusion drive subcritical system, the target ball is taken out;
252The Cf half life period is short, can not cross long-time irradiation.
The present invention has following advance:
(1) the transmuting nuke rubbish time, production prices are expensive, broad-spectrum
252Cf neutron source;
(2) this kind method has been taken into account nuclear explosion thermonuclear reaction production and fission reactor production
252The advantage of two kinds of methods of Cf, fusion drive subcritical system has higher flux, can not produce other nuke rubbish simultaneously again;
(3) system is in subcritical state, has guaranteed security.
Description of drawings
Fig. 1 is a structural representation of the present invention.
Embodiment
This accompanying drawing is the cross section view of spherical structure.The planform of actual device can be column type, sphere and annular or their approximate shapes, depends primarily on outer neutron source generation device kind.Whether the 5th district in the synoptic diagram can according to circumstances select to add.
The 1st district is D-T fusion neutron source region, and neutron source is produced by the D-T fusion.
The 2nd district is an actinium series nucleic treatment region, comprises long-life actinium series nucleic and fissionable fuel plutonium 239 potpourris and clad structure material from Nuclear Power Station's Exhausted Fuels, places cooling medium.
The 3rd district is the target area, and americium 241, curium 244 elements and clad structure material place cooling medium.
The 4th district is the fissionable fuel breeding blanket, and natural uranium or depleted uranium and clad structure material place cooling medium.
The 5th district is the fission product treatment region, and height is put fission product and clad structure material, neutron moderator, places cooling medium.
The 6th district is made up of graphite, boron carbide, stainless steel, lead etc. for reflection and shadow zone.
Claims (7)
1. fusion drive subcritical system production
252The method of Cf neutron source; It is characterized in that producing outer source neutron through fusion reaction; These outer source neutrons get into actinium series nucleic treatment regions, and wherein from the long-life actinium series nucleic of Nuclear Power Station's Exhausted Fuels and fissionable plutonium 239 fission reactions take place and produce the new neutron of a large amount of several keV to the hundreds of keV energy range, and these new neutrons get in target areas; With wherein americium 241, curium 244 capture reaction takes place, target nucleus is captured neutron continuously and is also taken place repeatedly to decay and generate
252Cf; The neutron that leaks through the target area gets in the fissionable fuel breeding blanket, with wherein depleted uranium or natural uranium generation neutron-capture reaction, generates fissionable plutonium 239, and extracts plutonium 239 and use with the recycle of supplying with actinium series nucleic treatment region; Reflection and shadow zone are arranged outside the fissionable fuel breeding blanket, and the heat that produces in each district adopts coolant cools, adopts structured material to separate between each district.
2. fusion drive subcritical system production according to claim 1
252The method of Cf neutron source; It is characterized in that the neutron that leaks from the fissionable fuel breeding blanket gets into the fission product treatment region; With the radioactive fission product generation capture reaction that wherein is blended in the neutron moderator; Highly toxic fission product of long-life is transformed into stablizes avirulence or the hypotoxic fission product of short life, the fissionable fuel breeding blanket is coated with structured material, and reflection is positioned at outside the fission product treatment region with the shadow zone.
3. fusion drive subcritical system production according to claim 2
252The method of Cf neutron source; It is characterized in that fusion reaction is meant the D-T fusion reaction; Comprise long-life actinium series nucleic and fissionable plutonium 239 in the actinium series nucleic treatment region from Nuclear Power Station's Exhausted Fuels; Exist with oxide, nitride, carbonide or metal form, concrete content requires to decide through solving system neutron-transport equation and burn up equation in the reload variation limitation of time cycle of operation according to system power density, system's critical factor and they; The target area adopts high-pressure helium as cooling medium, and other district adopts high-pressure helium or Li-Pb alloy as cooling medium, and the reactive material americium 241 of target area, curium 244 are piled up with pellet shapes and formed, and americium 241, curium 244 total solid volumes account for 60%～90% of target area inner volume; Neutron moderator is selected graphite or heavy water for use.
4. produce
252The fusion drive subcritical system in Cf source; It is characterized in that: neutron source produces outside the district and is surrounded by actinium series nucleic treatment region successively, target area, fissionable fuel breeding blanket or fissionable fuel breeding blanket, fission product treatment region outside; Separate with structured material between each district reflection and shadow zone; Actinium series nucleic treatment region comprises: long-life actinium series nucleic and fissionable plutonium 239 potpourris and clad structure material from Nuclear Power Station's Exhausted Fuels place cooling medium; The fissionable fuel breeding blanket comprises: natural uranium or depleted uranium and clad structure material place cooling medium; The target area comprises: americium 241, curium 244 elements and clad structure material place cooling medium; The fission product treatment region comprises: height is put fission product and clad structure material, neutron moderator, places cooling medium; Reflection is made up of graphite, boron carbide, stainless steel, lead with the shadow zone, and structured material is meant graphite, silit or steel.
5. production according to claim 4
252The fusion drive subcritical system in Cf source is characterized in that it is spherical or almost spherical that described outer neutron source produces the district, and ball is surrounded by structured material outward; Outer neutron source produces the outer actinium series nucleic treatment region that surrounds successively in district; The target area, fissionable fuel breeding blanket or fissionable fuel breeding blanket, fission product treatment region, reflection and shadow zone; Its outside surface is spherical or almost spherical, separates through clad structure material separately between each district.
6. production according to claim 4
252The fusion drive subcritical system in Cf source is characterized in that it is a cylindrical or near cylindrical that described outer neutron source produces the district, and cylinder is coated with structured material; Outer neutron source produces the outer actinium series nucleic treatment region that surrounds successively in district; The target area, fissionable fuel breeding blanket or fissionable fuel breeding blanket, fission product treatment region, reflection and shadow zone; Its outside surface is cylindrical or near cylindrical, separates through clad structure material separately between each district.
7. production according to claim 4
252The fusion drive subcritical system in Cf source is characterized in that it is an annular ring or sub-circular circle that described outer neutron source produces the district, and annular ring is surrounded by structured material outward; Outer neutron source produces the outer actinium series nucleic treatment region that surrounds successively in district; The target area, fissionable fuel breeding blanket or fissionable fuel breeding blanket, fission product treatment region, reflection and shadow zone; Its outside surface is annular ring or sub-circular circle, separates through clad structure material separately between each district.
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| JP5629089B2 (en) * | 2009-12-16 | 2014-11-19 | 浜松ホトニクス株式会社 | Fusion target material, fusion device, and fusion method |
| CN103093849A (en) * | 2011-10-31 | 2013-05-08 | 长春工业大学 | 14MeV neutron slowing-down material |
| CN102610284B (en) * | 2012-03-30 | 2015-05-27 | 中国科学院合肥物质科学研究院 | Hybrid reactor cladding for realizing long-term energy amplification by using fast-thermal coupling mixed energy spectrum |
| CN103137221A (en) * | 2013-01-15 | 2013-06-05 | 西安交通大学 | Subcritical wrapping layer of transmutation of pressure pipe type long-lived fission product |
| CN103578578B (en) * | 2013-10-16 | 2016-08-17 | 中国核电工程有限公司 | A kind of fusion-fission subcritical energy source reactor core fuel assembly of advanced person |
| CN108766591A (en) * | 2018-06-20 | 2018-11-06 | 中国科学院合肥物质科学研究院 | A kind of subcritical traveling wave heap |
| CN109741838B (en) * | 2019-02-01 | 2019-12-20 | 中国原子能科学研究院 | Anti-neutron trap type first critical method for research of reactor |
| CN113299420A (en) * | 2021-05-14 | 2021-08-24 | 中国核动力研究设计院 | High-flux experimental reactor irradiation target and irradiation americium production252Cf method |
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Patent Citations (4)
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|---|---|---|---|---|
| US4663110A (en) * | 1982-03-12 | 1987-05-05 | Ga Technologies Inc. | Fusion blanket and method for producing directly fabricable fissile fuel |
| CN1103894A (en) * | 1993-12-17 | 1995-06-21 | 清华大学 | Method for separating americium (copper) from rare earth elements of fission products |
| CN1591700A (en) * | 2003-08-26 | 2005-03-09 | 中国科学院等离子体物理研究所 | Method and system for subcritical nuclear rubbish treatment and nuclear fuel production based on fissioner neutron breeding |
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| 叶熙良.浅淡252cf中子源.《医疗装备》.2000,(第7期),9-10. * |
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