CN107705860B - A kind of high proliferation compares reactor core - Google Patents
A kind of high proliferation compares reactor core Download PDFInfo
- Publication number
- CN107705860B CN107705860B CN201710887724.6A CN201710887724A CN107705860B CN 107705860 B CN107705860 B CN 107705860B CN 201710887724 A CN201710887724 A CN 201710887724A CN 107705860 B CN107705860 B CN 107705860B
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- Prior art keywords
- neutron
- amplification region
- reactor core
- outside
- interruption area
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/12—Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/60—Metallic fuel; Intermetallic dispersions
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—Details
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/18—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone
- G21C5/20—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone wherein one zone contains fissile material and another zone contains breeder material
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G4/00—Radioactive sources
- G21G4/02—Neutron sources
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The invention discloses a kind of high proliferations than reactor core, which is the continuum centered on outside interruption area, and continuum is from inside to outside successively are as follows: amplification region, functional areas and blind zone；The fuel combination that MA nucleic and depleted uranium are placed in amplification region causes MA nucleic using the high-energy neutron that outside interruption area generates and depleted uranium fission carries out neutron multiplication；Fertile material is placed in functional areas, carries out fuel breeding using the neutron that amplification region leakage comes；Blind zone is for shielding the neutron leaked from functional unit.The ratio that the present invention can be realized generation with the consumption of easy fissioning nucleus of easy fissioning nucleus in reactor is high, i.e., in the case where generating identical easy fissioning nucleus, the easy fissioning nucleus of consumption is few, and the breeding ratio of reactor is high.
Description
Technical field
The present invention relates to nuclear reactor fields, and in particular to a kind of high proliferation compares reactor core.
Background technique
External nuclear energy uses has been proven in practice that nuclear energy can be used as the main of State Grid's production since half a century
The energy or important energy source.However uranium resource existing for nature have been approached it is exhausted and expensive, so developing higher proliferation
The fast reactor of energy can support huge nuclear power needs.
Sodium-cooled fast reactor in six kinds of heap-type that generation Ⅳ forum that U.S. Department of Energy is advocated is recommended, helium gas cooling fast reactor,
The cooling fast reactor of lead (bismuth) is fast breeder reactor, has harder neutron energy spectrum and obtains excellent neutron economy, system
Nuclear fuel breeding ability with higher.
The definition of breeding ratio is the ratio of the generation and the consumption of easy fissioning nucleus of easy fissioning nucleus in reactor, that is, is generating phase
In the case where easy fissioning nucleus, the easy fissioning nucleus of consumption is fewer, and the breeding ratio of heap is higher.Influence another factor of reactor multiplication
It is the every average secondary neutron population for absorbing a neutron and generating of fuel kernel.
In view of every secondary neutron number for absorbing the generation of a neutron is relatively more in fast reactor for plutonium, so current major part
Proliferation fast reactor selection use uranium, plutonium mixture, using fissile nuclide plutonium 239 fission reaction carry out neutron multiplication, into
And the proliferation of nuclear fuel is carried out using extra neutron.Therefore disappearing along with fissile nuclide in the breeding of nuclear fuel
It consumes, Nuclear fuel breeding is not than being very high in reactor.
Summary of the invention
In view of this, the present invention provides a kind of high proliferations than reactor core, easy fissioning nucleus in reactor can be realized
Generation and the consumption of easy fissioning nucleus ratio it is high, i.e., in the case where generating identical easy fissioning nucleus, the easy fissioning nucleus of consumption is few,
The breeding ratio of reactor is high.
Specific embodiments of the present invention are as follows:
A kind of high proliferation is than reactor core, which is the continuum centered on outside interruption area, even
Continuous region is from inside to outside successively are as follows: outside interruption area, amplification region, functional areas and blind zone；
The fuel combination that MA nucleic and depleted uranium are placed in the amplification region, is drawn using the high-energy neutron that outside interruption area generates
It sends out MA nucleic and depleted uranium fission carries out neutron multiplication；
Fertile material is placed in the functional areas, carries out fuel breeding using the neutron that amplification region leakage comes；
The blind zone is for shielding the neutron leaked from functional unit.
Further, the outside interruption area uses Fusion Neutron or spallation neutron as neutron source.
Further, moderator is also placed in the functional areas, moderator uses solid-state slowing material.
Further, the fertile material uses depleted uranium or thorium.
The utility model has the advantages that
1, for the present invention using the fuel combination for placing MA nucleic and depleted uranium in amplification region, MA nucleic and depleted uranium belong to non-volatility
Nucleic, on the one hand using MA nucleic, relative to plutonium, one neutron of every absorption under fast neutron effect can discharge generation more times
The characteristics of grade neutron population, realize neutron multiplication high efficiency；The nuclear fuel under a kind of no fissile nuclide consumption is realized simultaneously
Proliferation, and then realize reactor high proliferation ratio；Furthermore functional areas of the invention shield the neutron leaked, can subtract
Neutron irradiation damage of few neutron to reactor core peripheral components.
2, the present invention uses Fusion Neutron or spallation neutron as neutron source, and energy with higher can be amplification
Area provides the fast neutron that energy is up to million electron volt (MeV), i.e. high-energy neutron.
3, moderator is also placed in functional areas of the present invention, on the one hand utilizes the reflex of moderator, amplification region is revealed
The neutron to come over is reflected, and the fission rate in amplification region is improved；It is acted on simultaneously using the slowing down of moderator, amplification region is revealed
The neutron to come over carries out slowing down, and the neutron energy in functional areas is reduced to resonance energy area or thermal energy range, the two energy ranges
Neutron is easier to be captured absorption, increases the capture absorption cross-section of fertile nuclide, and then increases it and convert to fissile nuclide
Probability.
Detailed description of the invention
Fig. 1 is the plan view of reactor core of the present invention.
Wherein, 1- outside interruption area, the amplification region 2-, the functional areas 3-, the blind zone 4-.
Specific embodiment
The present invention will now be described in detail with reference to the accompanying drawings and examples.
The present invention provides a kind of high proliferations than reactor core, and design principle is: first is that reducing the easy fissioning nucleus of consumption
Element, second is that increase secondary neutron number, the reactor core be it is cylindric, be followed successively by from inside to outside centered on outside interruption area 1
Outside interruption area 1, amplification region 2, functional areas 3 and blind zone 4, outside interruption area 1, amplification region 2, functional areas 3 and blind zone 4 are same
Axis, as shown in Figure 1.
Outside interruption area 1 use Fusion Neutron perhaps spallation neutron as neutron source Fusion Neutron or spallation neutron all
Energy with higher can provide the fast neutron that energy is up to MeV for amplification region 2.
Amplification region 2 is located at 1 periphery of outside interruption area, between outside interruption area 1 and functional areas 3.Depleted uranium and MA nucleic
Non- fissile nuclide is belonged to, fission cross section is smaller under low-energy neutron effect, is difficult that fission reaction occurs, but work as neutron
When energy reaches MeV or more, fission cross section increases with the increase of neutron energy, can directly fission.In addition, MA
Nucleic fission every time under superhard power spectrum generation neutron population it is more than plutonium, therefore be relatively beneficial to neutron population purpose amplification.
Therefore, the fuel combination that MA nucleic and depleted uranium are placed in amplification region 2, in the high energy generated using outside interruption area 1
Son causes MA nucleic and uranium 238 fission carries out neutron multiplication.MA nucleic one neutron of every absorption under fast neutron effect can be split
Raw more fission neutrons are sold of one's property, realize more effective neutron multiplication effect, uranium 238 is every under fast neutron effect to be absorbed in one
Son can also discharge multiple fission neutrons；Moreover, uranium 238 and MA nucleic belong to non-fissile nuclide, therefore use MA nucleic
Carrying out neutron multiplication with depleted uranium can be avoided the consumption of fissile nuclide, improve breeding ratio.
Amplification region 2 further includes basis material, coolant and structural material, and coolant selection acts on moderation of neutrons small liquid
The materials such as state metal to Core cooling and convert out energy, guarantee that the neutron energy spectrum in amplification region 2 is fast spectrum；Basis material choosing
It is selected as neutron absorption cross-section and moderating effect is small as far as possible, the stable material of performance under high temperature fluent metal environment, such as MgO；Knot
Structure materials'use stainless steel, for carrying the material placed in one's respective area.
Functional areas 3 are located at the periphery of amplification region 2, between amplification region 2 and blind zone 4, by moderator, fertile material,
Coolant and structural material composition.On the one hand moderator material utilizes moderator using good slowing materials of reflecting effects such as berylliums
Reflex the neutron that comes revealed to amplification region 2 reflect, improve the fission rate of amplification region 2, while utilizing moderator
Slowing down effect, the neutron that comes is revealed to amplification region 2 and carries out slowing down, by 3 neutron energy of functional areas be reduced to resonance energy area or
Thermal energy range, increases the capture absorption cross-section of fertile material, and then increases its probability converted to fissile nuclide.Convertible material
Material is that perhaps thorium completes Nuclear fuel breeding by the conversion of U-Pu or Th-U to depleted uranium.Coolant uses and amplification region 2 is identical
Coolant material.Structural material uses stainless steel, for carrying the material placed in one's respective area.
Blind zone 4 is located at the outside of functional areas 3, for shielding the neutron leaked from functional areas 3, uses boron carbide etc.
Shielding material reduces the neutron irradiation damage that neutron loses reactor core periphery.
In conclusion the above is merely preferred embodiments of the present invention, being not intended to limit the scope of the present invention.
All within the spirits and principles of the present invention, any modification, equivalent replacement, improvement and so on should be included in of the invention
Within protection scope.
Claims (3)
1. a kind of high proliferation compares reactor core, which is characterized in that the reactor core is the company centered on outside interruption area
Continuous region, continuum is from inside to outside successively are as follows: outside interruption area, amplification region, functional areas and blind zone；Outside interruption area is put
Great Qu, functional areas and blind zone are coaxial；
The fuel combination that MA nucleic and depleted uranium are placed in the amplification region causes MA using the high-energy neutron that outside interruption area generates
Nucleic and depleted uranium fission carry out neutron multiplication, and using liquid metal as coolant, stainless steel is as structural material；
Fertile material is placed in the functional areas, carries out fuel breeding using the neutron that amplification region leakage comes；The function
Moderator is also placed in area, moderator uses solid-state slowing material；
The blind zone is for shielding the neutron leaked from functional unit.
2. high proliferation as described in claim 1 compares reactor core, which is characterized in that the outside interruption area uses in fusion
Son or spallation neutron are as neutron source.
3. high proliferation as described in claim 1 compares reactor core, which is characterized in that the fertile material using depleted uranium or
Person's thorium.
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| CN201710887724.6A CN107705860B (en) | 2017-09-27 | 2017-09-27 | A kind of high proliferation compares reactor core |
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| CN201710887724.6A CN107705860B (en) | 2017-09-27 | 2017-09-27 | A kind of high proliferation compares reactor core |
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| CN107705860A CN107705860A (en) | 2018-02-16 |
| CN107705860B true CN107705860B (en) | 2019-11-12 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN115662659B (en) * | 2022-11-25 | 2023-05-05 | 中国科学院合肥物质科学研究院 | Heat pipe pile high specific power reactor core structure |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1945751A (en) * | 2006-11-21 | 2007-04-11 | 中国原子能科学研究院 | Accelerator driven fast-thermally coupled subcritical reactor |
| RU2556036C1 (en) * | 2014-02-25 | 2015-07-10 | федеральное государственное автономное образовательное учреждение высшего профессионального образования "Национальный исследовательский ядерный университет МИФИ" (НИЯУ МИФИ) | Fast-neutron nuclear reactor |
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2017
- 2017-09-27 CN CN201710887724.6A patent/CN107705860B/en active Active
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1945751A (en) * | 2006-11-21 | 2007-04-11 | 中国原子能科学研究院 | Accelerator driven fast-thermally coupled subcritical reactor |
| RU2556036C1 (en) * | 2014-02-25 | 2015-07-10 | федеральное государственное автономное образовательное учреждение высшего профессионального образования "Национальный исследовательский ядерный университет МИФИ" (НИЯУ МИФИ) | Fast-neutron nuclear reactor |
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