CN106782681A - Three cold type fuel rod and fuel assembly - Google Patents
Three cold type fuel rod and fuel assembly Download PDFInfo
- Publication number
- CN106782681A CN106782681A CN201611209308.2A CN201611209308A CN106782681A CN 106782681 A CN106782681 A CN 106782681A CN 201611209308 A CN201611209308 A CN 201611209308A CN 106782681 A CN106782681 A CN 106782681A
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- involucrum
- pellet
- fuel rod
- cold type
- middle level
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Classifications
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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
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
-
- 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)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a kind of three cold type fuel rod and fuel assembly, three cold type fuel rod includes barred body, and the barred body includes internal layer involucrum, the middle level involucrum and outer layer involucrum, the first pellet being arranged on inside the internal layer involucrum and the second pellet being arranged between the middle level involucrum and outer layer involucrum being sequentially sleeved at outside the internal layer involucrum；Annular space between the middle level involucrum and the internal layer involucrum forms the internal cooling channel passed through for cooling agent.The present invention on the premise of identical reactor core uranium loading amount, can be such that pellet radial thickness significantly reduces, so as to be substantially reduced from screen effect, and then reduce fissile material residual quantity compared to solid pellet of the prior art, the setting and its setting of interior pellet of multilayer cladding；Pellet radial thickness significantly reduces, and the radial thermal expansion amount of pellet can also reduce therewith, so as to reduce the PCMI load under reactor particular incident operating mode, and then reduces the probability that fuel rod occurs PCMI failures.
Description
Technical field
The present invention relates to a kind of nuclear fuel rod, more particularly to a kind of three cold type fuel rod and the fuel using the nuclear fuel rod
Component.
Background technology
The reactor core of pressurized-water reactor nuclear power plant is made up of multiple fuel assemblies, and in existing fuel assembly, the pellet of fuel rod is more
It is solid design.For solid pellet, after thermal neutron incoming fuel rod, absorbed by the fissioner of pellet outer layer first, made
Lower than outer layer into the Thermal neutron flux density inside pellet, causing the fissioner of pellet internal layer can not substantially effectively inhale
Receive thermal neutron.That is, outer layer fissioner has played shielding action to nexine fissioner, and as from screen effect, should be from screen
Effect can cause pellet in radially more past inside, and the fissile material of residual is more, easily causes the waste of fission resource, reduces
The economy of reactor core.
If nuclear reactor occurs the accidents such as similar RIA (reactivity insertion accident), solid pellet is because have larger
Radial thickness, larger pellet radial thermal expansion amount can be produced so that fuel rod be easier occur PCMI (pellet and involucrum
Mechanical interaction) failure.In addition, larger pellet radius can cause pellet central temperature too high, pellet fusing is susceptible to.
The content of the invention
The technical problem to be solved in the present invention is, there is provided one kind reduces pellet radial thickness, improves nuclear reactor safety
With the three cold type fuel rod and the fuel assembly using the nuclear fuel rod of economy.
The technical solution adopted for the present invention to solve the technical problems is：A kind of three cold type fuel rod, including barred body are provided,
The barred body include internal layer involucrum, the middle level involucrum that is sequentially sleeved at outside the internal layer involucrum and outer layer involucrum, be arranged on it is described
The first pellet inside internal layer involucrum and the second pellet being arranged between the middle level involucrum and outer layer involucrum；The middle level
Annular space between involucrum and the internal layer involucrum forms the internal cooling channel passed through for cooling agent.
Preferably, first pellet is cylinder pellet；Second pellet is Annular pellet.
Preferably, the barred body also includes being arranged on the outside wall surface and/or the middle level involucrum inwall of the internal layer involucrum
Several ribs on face.
Preferably, several equal between-line spacings of the rib, and axial direction along the internal layer involucrum and/or middle level involucrum prolongs
Stretch.
Preferably, several rib spiral windings overlay on the outside wall surface and/or the middle level involucrum of the internal layer involucrum
On internal face.
Preferably, the barred body also includes the elastic support structure being arranged in the internal cooling channel.
Preferably, the elastic support structure along the internal cooling channel axially or radially extension, its opposite sides
The outside wall surface of the internal layer involucrum and the internal face of middle level involucrum are abutted respectively.
Preferably, the elastic support structure includes that at least one is arranged on the support ring in the internal cooling channel,
The circumference of the support ring is in wavy；Or, the elastic support structure includes at least one along the internal cooling channel
Axially extending strip shape body, its opposite sides face abuts the outside wall surface of the internal layer involucrum and the inwall of middle level involucrum respectively
Face, in addition opposite sides face be provided with the recess for mutually concaving.
Preferably, the three cold type fuel rod also includes being separately mounted to the first end plug on the barred body both ends and the
Two end plugs.
The present invention also provides a kind of fuel assembly, including the three cold type fuel rod described in any of the above.
Beneficial effects of the present invention：Compared to solid pellet of the prior art, in the present invention setting of multilayer cladding and
The setting of its interior pellet, on the premise of identical reactor core uranium loading amount, can be such that pellet radial thickness significantly reduces, so as to be substantially reduced
From screen effect, and then reduce fissile material residual quantity；Pellet radial thickness significantly reduces, and the radial thermal expansion amount of pellet also can
Reduce therewith, so as to reduce the PCMI load under reactor particular incident operating mode, and then reduce fuel rod generation PCMI failures
Probability.Additionally, smaller pellet radial thickness can significantly reduce the maximum temperature of pellet.
Three cold type fuel rod of the invention has less reaction compared to the fuel rod of prior art in the low burn consumption stage
Property, there is larger reactivity in the high burnup stage；In the case of identical uranium loading amount, this changes of reactivity feature can make
The length of the cycle of reactor is longer, is also easier to be controlled the initial reactivity of reactor.
Brief description of the drawings
Below in conjunction with drawings and Examples, the invention will be further described, in accompanying drawing：
Fig. 1 is the cross-sectional view of the three cold type fuel rod of first embodiment of the invention；
Fig. 2 be first embodiment of the invention three cold type fuel rod on internal layer involucrum rib structural representation；
Fig. 3 be second embodiment of the invention three cold type fuel rod between internal layer involucrum and middle level involucrum (radial direction) portion
Separation structure schematic diagram；
Fig. 4 be third embodiment of the invention three cold type fuel rod in structural representation between internal layer involucrum and middle level involucrum
Figure；
Fig. 5 is infinite multiplication of the three cold type fuel rod of the invention with prior art fuel rod under the premise of uranium loading amount is equal
Coefficient with burnup burnup variation tendency schematic diagram；
Fig. 6 is the structural representation of the fuel assembly of one embodiment of the invention.
Specific embodiment
In order to be more clearly understood to technical characteristic of the invention, purpose and effect, now compare accompanying drawing and describe in detail
Specific embodiment of the invention.
The three cold type fuel rod of first embodiment of the invention, for fuel assembly for nuclear reactor.The three cold type fuel rod bag
Include barred body.
As shown in figure 1, barred body includes internal layer involucrum 1, the middle level involucrum 2 and outer layer bag being sequentially sleeved at outside internal layer involucrum 1
Shell 3；Also include being arranged on the first pellet 4 inside internal layer involucrum 1 and being arranged between middle level involucrum 2 and outer layer involucrum 3
Second pellet 5.Middle level involucrum 2 is spaced internal layer involucrum 1, and annular space between the two forms the internal cooling passed through for cooling agent
Passage 6.The circulation of the cooling agents such as the reclaimed water of internal cooling channel 6, while being cooled down to internal layer involucrum 1 and middle level involucrum 2；Outer layer
Involucrum 3 is then cooled down by the cooling agent of outside circulation.
Wherein, internal layer involucrum 1, middle level involucrum 2 and outer layer involucrum 3 are the tubular structure that internal diameter increases one by one.Also, internal layer
Annular space is respectively kept between involucrum 1 and middle level involucrum 2, between middle level involucrum 2 and outer layer involucrum 3.
First pellet 4 is arranged on the inside of internal layer involucrum 1, is solid cylinder pellet (such as cylinder).Second pellet 5 is
Annular pellet, is arranged in the annular space between middle level involucrum 2 and outer layer involucrum 3.Between internal layer involucrum 1 and middle level involucrum 2
Annular space do not set pellet, form internal cooling channel 6.Relative to the first solid pellet 4, the second pellet 5 is hollow
Pellet；There are internal layer involucrum 1, middle level involucrum and internal cooling channel 6 to separate between the two.
The setting of multilayer cladding, internal cooling channel 6, the first pellet 4 and the second pellet 5, with entirety of the prior art
Solid pellet is compared, and on the premise of identical reactor core uranium loading amount, pellet radial thickness can be made significantly to reduce, so as to be substantially reduced certainly
Screen effect, and then reduce fissile material residual quantity, more fully using the fissile material in pellet, improve reactor
Economy.In addition, pellet radial thickness significantly reduces, the radial thermal expansion amount of pellet can also reduce therewith, so as to reduce reaction
PCMI load under heap particular incident operating mode, and then reduce the probability that fuel rod occurs PCMI failures.Additionally, smaller pellet is radially
Thickness can significantly reduce the maximum temperature of pellet.
Additionally, compared with unitary solid pellet of the prior art, it is of the invention under the premise of identical reactor core uranium loading amount
Three cold type fuel rod has larger fuel rod outer diameter, with reference to three layers of involucrum so that the moment of inertia of fuel rod is also larger, does not allow more
Easily there is the phenomenon of fuel rod bending.
In the barred body of three cold type fuel rod, the radial thickness between internal layer involucrum 1, middle level involucrum 2 and outer layer involucrum 3 can be
Unanimously, also can be inconsistent.The selection inconsistent for radial thickness, the radial direction of outer layer involucrum 3, middle level involucrum 2 and internal layer involucrum 1
Thickness preferably successively decreases successively.
Further, to prevent from causing internal layer involucrum 1 and middle level to wrap due to the different bending of outskirt in three cold type fuel rod
Shell 2 is contacted, so influence interior coolant passage 6 heat transfer, barred body also include be arranged on internal layer involucrum 1 outside wall surface and/or
Several ribs 7 on the internal face of middle level involucrum 2.
Several ribs 7 protrude above setting in the outside wall surface and/or the internal face of middle level involucrum 2 of internal layer involucrum 1, are preventing internal layer
Involucrum 1 does not influence circulation of the cooling agent internally in coolant channel 6 while contact with middle level involucrum 2.
Preferably, equal between-line spacing between several ribs 7, and along the axially extending of internal layer involucrum 1 and/or middle level involucrum 2.
Rib 7 can be integrally formed on internal layer involucrum 1 and/or middle level involucrum 2, also can be fixed on internal layer involucrum 1 by modes such as welding
And/or on middle level involucrum 2.
As shown in Fig. 2 in the present embodiment, the spiral winding of several ribs 7 overlays on the outside wall surface and/or middle level bag of internal layer involucrum 1
On the internal face of shell 2.The spiral winding of rib 7 covers mode can also strengthen the cooling agent effect of mixing in internal cooling channel 6, so that
Enhancing heat transfer effect.
It is to be appreciated that the bearing of trend of rib 7 can also parallel innerlayers involucrum 1 and/or middle level involucrum 2 axial direction, or
Person is other around covering mode, as long as not influenceing circulation of the cooling agent internally in coolant channel 6.
Further, three cold type fuel rod also include being separately mounted to the first end plug (not shown) on barred body both ends and
Second end plug (not shown), and air cavity spring etc., the first end plug, the second end plug and air cavity spring etc. can refer to prior art
In end plug and air cavity spring, wherein the first end plug and the second end plug correspondence barred body end set.
As shown in figure 3, the three cold type fuel rod of second embodiment of the invention, and unlike above-mentioned first embodiment：Rod
Body can also include elastic support structure, and elastic support structure replaces rib 7, is arranged in internal cooling channel 6, and it prevents interior
Layer involucrum 1 with middle level involucrum 2 while contact, it is also possible to bear internal layer involucrum 1 and middle level involucrum 2 because thermal expansion, irradiation growth,
Irradiation creep etc. makes the mechanical compatibility problem that the gap of interior coolant passage 6 changes and produces.
Elastic support structure can be made of metal materials such as zircaloy or inconel.
Elastic support structure can respectively abut internal layer along the axially or radially extension of internal cooling channel 6, its opposite sides
The outside wall surface of involucrum 1 and the internal face of middle level involucrum 2, to be supported between internal layer involucrum 1 and middle level involucrum 2.Also, elasticity branch
Support structure is internally not filled with whole internal cooling channel 6 in cooling duct 6, to ensure cooling agent internally in cooling duct 6
Circulation.
In the present embodiment, elastic support structure includes that at least one is arranged on the support ring 8 in internal cooling channel 6, branch
The circumference of pushing out ring 8 in wavy so that crest and trough can abut respectively internal layer involucrum 1 outside wall surface and middle level involucrum 2 it is interior
Wall.The wavy setting of support ring 8 causes that support ring 8 will not be full of the sagittal plane where it, and cooling agent can be along support
The surface of ring 8 by and internally in cooling duct 6 circulate.
When elastic support structure includes multiple support rings 8, multiple support rings 8 can be along the axially spaced-apart of internal cooling channel 6
Distribution.
In other embodiments, the length of support ring 8 also can be along the branch of the axially extending formation of internal cooling channel 6 annular
Stay tube, cooling agent can along the surface of support tube by and internally in cooling duct 6 circulate.
As shown in figure 4, the three cold type fuel rod of third embodiment of the invention, and unlike above-mentioned second embodiment：Bullet
Property supporting construction include at least one strip shape body 9, strip shape body 9 is axially extending along internal cooling channel 6.The periphery of strip shape body 9
Shape is not limited, as long as may be supported between internal layer involucrum 1 and middle level involucrum 2 and do not block the circulation of cooling agent.
In the present embodiment, the periphery of strip shape body 9 is polygon, along radially extending for internal cooling channel 6, wherein relative two
Side abuts the outside wall surface of internal layer involucrum 1 and the internal face of middle level involucrum 2 respectively, and opposite sides face is provided with and mutually concaves in addition
Recess 91.The setting of recess 91 can reduce the space that elastic support structure is internally taken in cooling duct 6, it is ensured that cooling agent
The flow in cooling duct 6 and circulation internally.
When elastic support structure includes multiple strip shape bodies 9, multiple strip shape bodies 9 can be along the circumferentially-spaced of internal cooling channel 6
Distribution.
In addition, in three cold type fuel rod of the invention, the material of the first pellet 4 and the second pellet 5 can be by prior art reality
It is existing.Or, the matrix material of the first pellet 4 and the second pellet 5 can select the additive pellet with high heat conductance feature, such as
Uranium dioxide addition BeO, uranium dioxide addition SiC, uranium dioxide addition Nano diamond, FCM pellets or metal mold pellet
Etc., so as to further reduce pellet maximum temperature.
With reference to 5 figures, it is the fuel rod of three cold type fuel rod of the invention and prior art under the premise of uranium loading amount is equal
Infinite multiplication factor (kinf) with burnup burnup (effective full power days, EFPD) variation tendency schematic diagram.It is unlimited to increase
Grow coefficient (kinf) be defined as newborn generation neutron population in Infinite medium and produce it directly under the ratio between previous generation neutron populations.Its
In, transverse axis is effective full power days, and the longitudinal axis is infinite multiplication factor；Origin is prior art fuel rod, and side's point is the present invention
Three cold type fuel rod.
From figure 5 it can be seen that consuming the stage in low burn, three cold type fuel rod has relatively small reactivity；In Gao Ran
Consumption stage, three cold type fuel rod has relatively large reactivity；Relatively flat changes of reactivity feature can make in identical uranium
In the case of loading amount, present invention fuel rod compared to existing technology can make the length of the cycle of reactor longer, while easily right
The initial reactivity of reactor core is controlled.
As shown in fig. 6, fuel assembly of the invention, including several fuel rod groups, on each fuel rod group involucrum is several
The three cold type fuel rod stated.Fuel assembly also include the upper base 10 that is oppositely arranged and bottom nozzle 20, several grid spacers 30 with
And several guide pipes 40.Several grid spacers 30 are arranged at axially spaced intervals between upper base 10 and bottom nozzle 20 along fuel assembly,
Guide pipe 40 is through grid spacer 30 and is arranged on upper base 10 and bottom nozzle 20, and three cold type fuel rod is held on positioning lattice
Among the lattice cell of frame 30.
Grid spacer 30 can be using with the screen work for mixing function so that cooling agent is more flowed to inside grid spacer 30
Participation is mixed, so as to have more preferable cooling agent to mix performance, improves thermal technology's safe operation allowance of reactor.
Bottom nozzle 20 may include matching disc and the supporting leg being connected to below matching disc, and matching disc is provided with for fixed guide
The fixing hole of pipe and the runner passed through for cooling agent.Upper base 10 may also comprise matching disc, and matching disc is provided with for fixed guide
The fixing hole of pipe and the runner passed through for cooling agent.
Embodiments of the invention are the foregoing is only, the scope of the claims of the invention is not thereby limited, it is every to utilize this hair
Equivalent structure or equivalent flow conversion that bright specification and accompanying drawing content are made, or directly or indirectly it is used in other related skills
Art field, is included within the scope of the present invention.
Claims (10)
1. a kind of three cold type fuel rod, it is characterised in that including barred body, the barred body includes internal layer involucrum, is sequentially sleeved at institute
State middle level involucrum and outer layer involucrum outside internal layer involucrum, the first pellet being arranged on inside the internal layer involucrum and be arranged on institute
State the second pellet between middle level involucrum and outer layer involucrum；Annular space shape between the middle level involucrum and the internal layer involucrum
Into the internal cooling channel passed through for cooling agent.
2. three cold type fuel rod according to claim 1, it is characterised in that first pellet is cylinder pellet；It is described
Second pellet is Annular pellet.
3. three cold type fuel rod according to claim 1, it is characterised in that the barred body also includes being arranged on the internal layer
Several ribs in the outside wall surface of involucrum and/or the middle level involucrum internal face.
4. three cold type fuel rod according to claim 3, it is characterised in that several equal between-line spacings of rib, and edge
The internal layer involucrum and/or middle level involucrum it is axially extending.
5. three cold type fuel rod according to claim 4, it is characterised in that several rib spiral windings are overlayed in described
In the layer outside wall surface of involucrum and/or the internal face of the middle level involucrum.
6. three cold type fuel rod according to claim 1, it is characterised in that the barred body also includes being arranged on the inside
Elastic support structure in cooling duct.
7. three cold type fuel rod according to claim 6, it is characterised in that the elastic support structure is cold along the inside
But the axially or radially extension of passage, its opposite sides abuts the outside wall surface of the internal layer involucrum and the inwall of middle level involucrum respectively
Face.
8. three cold type fuel rod according to claim 7, it is characterised in that the elastic support structure includes at least one
The support ring in the internal cooling channel is arranged on, the circumference of the support ring is in wavy；Or, the resilient support knot
Structure include at least one along the internal cooling channel axially extending strip shape body, its opposite sides face abut respectively it is described in
Layer involucrum outside wall surface and the internal face of middle level involucrum, in addition opposite sides face be provided with the recess for mutually concaving.
9. the three cold type fuel rod according to claim any one of 1-8, it is characterised in that the three cold type fuel rod is also wrapped
Include the first end plug and the second end plug being separately mounted on the barred body both ends.
10. a kind of fuel assembly, it is characterised in that including the three cold type fuel rod described in claim any one of 1-9.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201611209308.2A CN106782681B (en) | 2016-12-23 | 2016-12-23 | Three cold type fuel rod and fuel assembly |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201611209308.2A CN106782681B (en) | 2016-12-23 | 2016-12-23 | Three cold type fuel rod and fuel assembly |
Publications (2)
| Publication Number | Publication Date |
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| CN106782681A true CN106782681A (en) | 2017-05-31 |
| CN106782681B CN106782681B (en) | 2018-09-28 |
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| CN201611209308.2A Active CN106782681B (en) | 2016-12-23 | 2016-12-23 | Three cold type fuel rod and fuel assembly |
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Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109036591A (en) * | 2017-06-08 | 2018-12-18 | 中广核工程有限公司 | Nuclear reactor |
| CN109935350A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of fixed two-sided cooling annular fuel rod in lower end |
| CN109935371A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of two-sided cooling annular fuel rod with wrapping wire |
| CN110827998A (en) * | 2019-11-21 | 2020-02-21 | 中国核动力研究设计院 | Beryllium oxide moderated metal cooling reactor miniaturization design method and reactor |
| CN111477354A (en) * | 2020-05-25 | 2020-07-31 | 中国原子能科学研究院 | Co-extrusion annular fuel rod |
| CN111968767A (en) * | 2020-09-10 | 2020-11-20 | 中国工程物理研究院核物理与化学研究所 | Rib type temperature control irradiation device and application thereof |
| CN112669999A (en) * | 2020-12-23 | 2021-04-16 | 南京航空航天大学 | Liquid-solid dual fuel space nuclear reactor power supply |
| CN113409963A (en) * | 2021-06-17 | 2021-09-17 | 中国核动力研究设计院 | Fuel rod and fuel assembly for overcoming pellet cladding mechanical interaction |
| CN115050488A (en) * | 2022-06-24 | 2022-09-13 | 中国核动力研究设计院 | Fuel pipe for improving thermal performance, fuel sleeve structure and fuel assembly |
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Cited By (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109036591B (en) * | 2017-06-08 | 2021-10-15 | 中广核工程有限公司 | Nuclear reactor core |
| CN109036591A (en) * | 2017-06-08 | 2018-12-18 | 中广核工程有限公司 | Nuclear reactor |
| CN109935350A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of fixed two-sided cooling annular fuel rod in lower end |
| CN109935371A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of two-sided cooling annular fuel rod with wrapping wire |
| CN110827998A (en) * | 2019-11-21 | 2020-02-21 | 中国核动力研究设计院 | Beryllium oxide moderated metal cooling reactor miniaturization design method and reactor |
| CN110827998B (en) * | 2019-11-21 | 2021-05-18 | 中国核动力研究设计院 | Beryllium oxide moderated metal cooling reactor miniaturization design method and reactor |
| CN111477354A (en) * | 2020-05-25 | 2020-07-31 | 中国原子能科学研究院 | Co-extrusion annular fuel rod |
| CN111968767A (en) * | 2020-09-10 | 2020-11-20 | 中国工程物理研究院核物理与化学研究所 | Rib type temperature control irradiation device and application thereof |
| CN111968767B (en) * | 2020-09-10 | 2024-05-28 | 中国工程物理研究院核物理与化学研究所 | Rib type temperature control irradiation device and application thereof |
| CN112669999A (en) * | 2020-12-23 | 2021-04-16 | 南京航空航天大学 | Liquid-solid dual fuel space nuclear reactor power supply |
| CN112669999B (en) * | 2020-12-23 | 2024-05-17 | 南京航空航天大学 | Liquid-solid dual fuel space nuclear reactor power supply |
| CN113409963A (en) * | 2021-06-17 | 2021-09-17 | 中国核动力研究设计院 | Fuel rod and fuel assembly for overcoming pellet cladding mechanical interaction |
| CN115050488A (en) * | 2022-06-24 | 2022-09-13 | 中国核动力研究设计院 | Fuel pipe for improving thermal performance, fuel sleeve structure and fuel assembly |
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| Publication number | Publication date |
|---|---|
| CN106782681B (en) | 2018-09-28 |
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