CN107705860A - A kind of high proliferation compares reactor core - Google Patents
A kind of high proliferation compares reactor core Download PDFInfo
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- CN107705860A CN107705860A CN201710887724.6A CN201710887724A CN107705860A CN 107705860 A CN107705860 A CN 107705860A CN 201710887724 A CN201710887724 A CN 201710887724A CN 107705860 A CN107705860 A CN 107705860A
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- neutron
- reactor core
- amplification region
- outside
- functional areas
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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
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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
- G21C5/02—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
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma & Fusion (AREA)
- Chemical & Material Sciences (AREA)
- Dispersion Chemistry (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- Particle Accelerators (AREA)
Abstract
The invention discloses a kind of high proliferation than reactor core, and the reactor core is the continuum centered on outside interruption area, and continuum is followed successively by from inside to outside:Amplification region, functional areas and blind zone;The fuel combination of MA nucleic and depleted uranium is placed in amplification region, triggers MA nucleic and poor uranium fission to carry out neutron multiplication using high-energy neutron caused by outside interruption area;Fertile material is placed in functional areas, the neutron to come using amplification region leakage carries out fuel breeding;Blind zone is used to shield the neutron leaked from functional unit.The present invention can realize that the ratio of generation with the consumption of easy fissioning nucleus of easy fissioning nucleus in reactor is high, i.e., in the case where producing identical easily 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 field, and in particular to a kind of high proliferation compares reactor core.
Background technology
External nuclear energy uses has been proven in practice that nuclear energy can be as the main of State Grid production since half a century
The energy or important energy source.But uranium resource existing for nature is close to exhausted and expensive, so development 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 USDOE advocates is recommended, helium gas cooling fast reactor,
Lead (bismuth) cooling fast reactor be fast breeder reactor, have harder neutron energy spectrum and obtain excellent neutron economy, system
With higher Nuclear fuel breeding ability.
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 producing phase
In the case of 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 that fuel kernel often absorbs average secondary neutron population caused by a neutron.
It is relatively more that secondary neutron number caused by a neutron is often absorbed in fast reactor in view of plutonium, so current major part
Propagation fast reactor selection using uranium, plutonium mixture, using fissile nuclide plutonium 239 fission reaction carry out neutron multiplication, enter
And the propagation of nuclear fuel is carried out using unnecessary neutron.Therefore disappearing along with fissile nuclide in the breeding of nuclear fuel
Consume, Nuclear fuel breeding is not than being very high in reactor.
The content of the invention
In view of this, easy fissioning nucleus in reactor can be realized than reactor core the invention provides a kind of high proliferation
Generation and the consumption of easy fissioning nucleus ratio it is high, i.e., in the case where producing identical easily 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, and the reactor core is the continuum centered on outside interruption area, even
Continuous region is followed successively by from inside to outside:Outside interruption area, amplification region, functional areas and blind zone;
The fuel combination of MA nucleic and depleted uranium is placed in the amplification region, is drawn using high-energy neutron caused by outside interruption area
Send out MA nucleic and poor uranium fission carries out neutron multiplication;
Fertile material is placed in the functional areas, the neutron to come using amplification region leakage carries out fuel breeding;
The blind zone is used to shield 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.
Beneficial effect:
1st, for the present invention using the fuel combination that MA nucleic and depleted uranium are placed in amplification region, MA nucleic and depleted uranium belong to non-volatility
Nucleic, more times of generation can be discharged by the one hand often absorbing a neutron under fast neutron effect relative to plutonium using MA nucleic
The characteristics of level neutron population, realize neutron multiplication high efficiency;The nuclear fuel under a kind of no fissile nuclide consumption is realized simultaneously
Propagation, and then realize the high proliferation ratio of reactor;Furthermore the neutron that functional areas shielding of the invention leaks, can subtract
Neutron irradiation damage of few neutron to reactor core peripheral components.
2nd, the present invention uses Fusion Neutron or spallation neutron to have higher energy as neutron source, can be amplification
Area provides the fast neutron that energy is up to million electron volt (MeV), i.e. high-energy neutron.
3rd, moderator is also placed in functional areas of the present invention, on the one hand using the reflex of moderator, amplification region is revealed
The neutron to come over is reflected, and improves the fission rate in amplification region;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 into 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 changed to fissile nuclide
Probability.
Brief description of the drawings
Fig. 1 is the plan of reactor core of the present invention.
Wherein, 1- outside interruptions area, 2- amplification regions, 3- functional areas, 4- blind zones.
Embodiment
The present invention will now be described in detail with reference to the accompanying drawings and examples.
It is than reactor core, design principle the invention provides a kind of high proliferation:First, reduce the easy fissioning nucleus of consumption
Element, second, increase secondary neutron number, the reactor core are cylindric, it is 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
Axle, as shown in Figure 1.
Outside interruption area 1 uses Fusion Neutron or spallation neutron, and as neutron source, Fusion Neutron or spallation neutron are all
Can be that amplification region 2 provides the fast neutron that energy is up to MeV with higher energy.
Amplification region 2 is located at the periphery of outside interruption area 1, 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, it is difficult to which fission reaction occurs, but works as neutron
When energy reaches more than MeV, its fission cross section increases with the increase of neutron energy, can directly fission.In addition, MA
Neutron population caused by fission is more than plutonium every time under superhard power spectrum for nucleic, therefore is relatively beneficial to the amplification of neutron population purpose.
Therefore, the fuel combination of MA nucleic and depleted uranium is placed in amplification region 2, using in high energy caused by outside interruption area 1
Son triggers MA nucleic and uranium 238 fission to carry out neutron multiplication.MA nucleic often absorbs a neutron under fast neutron effect and can split
Become and produce more fission neutrons, realize more effective neutron multiplication effect, uranium 238 is often absorbed in one under fast neutron effect
Son can also discharge multiple fission neutrons;Moreover, uranium 238 and MA nucleic belong to non-fissile nuclide, therefore use MA nucleic
The consumption of fissile nuclide can be avoided by carrying out neutron multiplication with depleted uranium, improve breeding ratio.
Amplification region 2 also includes matrix material, cooling agent and structural material, and cooling agent selection acts on moderation of neutrons small liquid
The materials such as state metal, to Core cooling and energy is changed out, it is fast spectrum to ensure the neutron energy spectrum in amplification region 2;Matrix material selects
Be selected as neutron absorption cross-section and moderating effect is as far as possible small, under high temperature fluent metal environment stable performance material, 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,
Cooling agent and structural material composition.On the one hand moderator material utilizes moderator using good slowing materials of reflecting effect such as berylliums
Reflex the neutron that comes revealed to amplification region 2 reflected, improve the fission rate of amplification region 2, while utilize moderator
Slowing down effect, the neutron that comes is revealed to amplification region 2 and carries out slowing down, by the neutron energy of functional areas 3 be reduced to resonance energy area or
Thermal energy range, increases the capture absorption cross-section of fertile material, and then increases its probability changed to fissile nuclide.Convertible material
Expect for depleted uranium or thorium, pass through U-Pu or Th-U conversion, complete Nuclear fuel breeding.Cooling agent 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, reduce the neutron irradiation damage that neutron loses to reactor core periphery.
In summary, presently preferred embodiments of the present invention is these are only, is not intended to limit the scope of the present invention.
Within the spirit and principles of the invention, any modification, equivalent substitution and improvements made etc., it should be included in the present invention's
Within protection domain.
Claims (4)
1. a kind of high proliferation compares reactor core, it is characterised in that the reactor core is the company centered on outside interruption area
Continuous region, continuum is followed successively by from inside to outside:Outside interruption area, amplification region, functional areas and blind zone;
The fuel combination of MA nucleic and depleted uranium is placed in the amplification region, triggers MA using high-energy neutron caused by outside interruption area
Nucleic and poor uranium fission carry out neutron multiplication;
Fertile material is placed in the functional areas, the neutron to come using amplification region leakage carries out fuel breeding;
The blind zone is used to shield the neutron leaked from functional unit.
2. high proliferation as claimed in claim 1 compares reactor core, it is characterised in that the outside interruption area is used in fusion
Son or spallation neutron are as neutron source.
3. high proliferation as claimed in claim 1 compares reactor core, it is characterised in that also places slowing down in the functional areas
Agent, moderator use solid-state slowing material.
4. high proliferation as claimed in claim 1 compares reactor core, it is characterised in that the fertile material using depleted uranium or
Person's thorium.
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CN107705860B CN107705860B (en) | 2019-11-12 |
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Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN115662659A (en) * | 2022-11-25 | 2023-01-31 | 中国科学院合肥物质科学研究院 | High specific power reactor core structure of heat pipe reactor |
Citations (2)
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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 |
-
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 |
Non-Patent Citations (2)
Title |
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周乃君: "《核能发电原理与技术》", 31 March 2014, 中国电力出版社 * |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN115662659A (en) * | 2022-11-25 | 2023-01-31 | 中国科学院合肥物质科学研究院 | High specific power reactor core structure of heat pipe reactor |
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 |
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