CN105405475A - Honeycomb-type fuel assembly and long-service-life supercritical carbon dioxide cooled reactor - Google Patents

Honeycomb-type fuel assembly and long-service-life supercritical carbon dioxide cooled reactor Download PDF

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Publication number
CN105405475A
CN105405475A CN201510729024.5A CN201510729024A CN105405475A CN 105405475 A CN105405475 A CN 105405475A CN 201510729024 A CN201510729024 A CN 201510729024A CN 105405475 A CN105405475 A CN 105405475A
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type fuel
fuel assembly
honeycomb type
reactor core
honeycomb
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CN201510729024.5A
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CN105405475B (en
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曹良志
刘保林
吴宏春
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Xian Jiaotong University
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Xian Jiaotong University
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/58Solid reactor fuel Pellets made of fissile material
    • G21C3/62Ceramic fuel
    • G21C3/623Oxide fuels
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C5/00Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02Details
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Ceramic Engineering (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

The invention provides a honeycomb-type fuel assembly and a long-service-life supercritical carbon dioxide cooled reactor. The honeycomb-type fuel assembly has three layers from outside to inside, namely an assembly wall, an air gap layer and a fuel region filling the air gap layer. The reactor comprises a pressure container, wherein the pressure container comprises a pressure shell, and a reactor core and a control rod driving mechanism which are arranged in the pressure shell; the upper and lower parts of the pressure shell are divided into an upper chamber and a lower chamber through upper and lower separation plates respectively; the reactor core is internally and vertically provided with the plurality of honeycomb-type fuel assemblies; a cooling agent channel wall and the assembly wall extend upwards to penetrate through the upper separation plate to be connected with the upper chamber; and air inlet holes are formed in the parts, corresponding to all the honeycomb-type fuel assemblies, at the connection parts of the lower separation plate and the honeycomb-type fuel assemblies in the reactor core. The reactor has the characteristics of small size, high heat efficiency, low working pressure and low outlet temperature of a cooling agent, and low difficulty of realizing engineering.

Description

Honeycomb type fuel assembly and long-life supercritical carbon dioxide cooling rickle
Technical field
The invention belongs to nuclear reactor field of engineering technology, be specifically related to honeycomb type fuel assembly and adopt the long-life supercritical carbon dioxide of honeycomb type fuel assembly to cool rickle.
Background technology
Supercritical carbon dioxide cooled reactor adopts supercritical carbon dioxide as cooling medium.Supercritical carbon dioxide refers to the plan critical point (7.38MPa, 30.98 DEG C) higher than carbon dioxide of the pressure of carbon dioxide, temperature.Compared with piling with the helium gas cooling of brayton cycle, supercritical carbon dioxide cooled reactor core exit temperature can drop to about 650 DEG C even lower from 900 DEG C required by helium gas cooling heap, greatly reduces the requirement to material.Compared with presurized water reactor popular at present, the thermal efficiency more than 40%, good economy performance.And owing to adopting brayton cycle, compared with existing presurized water reactor, supercritical carbon dioxide cooled reactor does not need steam generator, voltage stabilizer, steam-water separator and exsiccator, and its compact conformation also reduces equipment cost during construction.
Current, the supercritical carbon dioxide cooled reactor developed in the world mainly concentrate on high-power on.The employing honeycomb type fuel assembly that reactor core scheme proposes with masschusetts, u.s.a Polytechnics, thermal power are for 2400MWt reactor core scheme is for main representative.Its reactor core working pressure is 20MPa, and in order to realize the higher thermal efficiency (48%), core exit temperature is 650 DEG C.Its power is comparatively large, and relevant device volume is also larger, is not easy at from far-off regions or that power demand is less regional Construction.Reactive in order to flatten power and reduce cavity, be mixed with matrix material beryllia in fuel.Due to the existence of beryllia, reduce the equilibrium temperature of fuel.
Such scheme, in order to realize the high thermal efficiency, have employed higher working pressure and higher material temperature, adds difficulty during Project Realization, also propose higher requirement to material property.
Summary of the invention
For solving the problem, the invention provides a kind of honeycomb type fuel assembly and long-life supercritical carbon dioxide cooling rickle, changing the little heat output of reactor of cooling is 300MWt, the thermal efficiency is 40%, and working pressure is 14MPa, outlet temperature 500 DEG C, there is system simple, volume is little, and security is good, the feature that Project Realization difficulty is low.
In order to achieve the above object, the present invention adopts following technical scheme:
A kind of honeycomb type fuel assembly, this fuel assembly is hexagon, and ecto-entad has three layers, is respectively the fuel region 3 of filling in component walls 1, air gap layer 2 and air gap layer 2; 91 coolant channels are uniform-distribution with in described fuel region 3.
Described coolant channel is made up of coolant channel 4, cooling medium wall 5 and the air gap between coolant channel wall and fuel 6.
The material of described cooling medium wall 5 is ODSMA956 stainless steel.
The material of described component walls 1 is ODSMA956 stainless steel.
The material of described fuel region 3 is mox fuel.
A kind of long-life supercritical carbon dioxide cooling rickle, comprise pressure vessel, described pressure vessel comprises pressure vessel 9 and the reactor core 13 that is placed in pressure vessel 9 and control rod drive mechanisms (CRD) 7, the upper and lower of described pressure vessel 9 is isolated upper chamber 20 and lower chambers 12 by upper division board and lower division board respectively, gap between pressure vessel 9 and core barrel 8 forms descending branch 11, the honeycomb type fuel assembly described in multiple any one of claim 1 to 5 and C&P systems is vertically vertically placed with in reactor core 13, fission gas plenum 18 is had above described honeycomb type fuel assembly, fission gas plenum 18 press against division board above, the control rod cluster 15 of described C&P systems extends up through division board and is connected with the control rod drive mechanisms (CRD) 7 in upper chamber 20, honeycomb type fuel assembly connecting place in lower division board and reactor core 13, air admission hole is had corresponding to each honeycomb type fuel assembly, for regulating charge flow rate.
Described reactor core 13 working pressure is 14MPa, and Core cooling agent outlet temperature is 500 DEG C.
Gap is left between the honeycomb type fuel assembly that described reactor core 13 is placed.
Described C&P systems comprises C&P systems outer wall 33, be arranged on the 37 control rod clusters 15 be inserted with in multiple wall cooling passage 34 on C&P systems outer wall 33 and C&P systems outer wall 33.
Each control rod of described control rod cluster 15 is round section, is made up of control rod involucrum 36 and the boron carbide absorber 35 be placed in control rod involucrum 36.
Compared to the prior art, tool has the following advantages in the present invention:
1, fuel assembly of the present invention adopts honeycomb type fuel assembly, and because fuel adopts MOX, wherein not mixed oxidization beryllium, can increase the equilibrium temperature of fuel like this, be conducive to safety, reduce complexity during fuel making simultaneously.
2, compared with the reactor core scheme proposing 2400MWt with masschusetts, u.s.a Polytechnics, due to the 14MPa that reactor core working pressure is lower, although the thermal efficiency decreases (dropping to 40% from 48%), but still high than the thermal efficiency of common presurized water reactor, and difficulty when reducing Project Realization; Core exit temperature is set as 500 DEG C, like this while guarantee greater efficiency, also reduces the requirement to material, reduces the corrosion that material causes because of high temperature.Heap core volume and the reduction of thermal power, can be applicable to remote districts or the less area of power demand.
Accompanying drawing explanation
Fig. 1 is honeycomb type fuel assembly cross sectional representation.
Fig. 2 is coolant channel cross sectional representation.
Fig. 3 is nuclear reactor structure schematic diagram.
Fig. 4 is 1/6 reactor core display schematic diagram.
Fig. 5 is C&P systems cross sectional representation.
Fig. 6 is control rod cross sectional representation.
Embodiment
Below in conjunction with the drawings and specific embodiments, structure of the present invention is described in detail.
As shown in Figure 1, a kind of honeycomb type fuel assembly of the present invention, this fuel assembly is hexagon, and ecto-entad has three layers, is respectively component walls 1 and air gap layer 2, is filled with fuel region 3 in air gap layer 2, is uniform-distribution with 91 coolant channels in fuel region 3.
The material of filling in preferred described fuel region 3 is mox fuel.
The material of preferred described inner assembly wall is ODSMA956 stainless steel.
As shown in Figure 2, described coolant channel is made up of cooling medium 4, cooling medium wall 5 and the air gap between coolant channel wall and fuel 6.
The material of preferred described cooling medium wall 5 is ODSMA956 stainless steel.
As shown in Figure 3, the long-life supercritical carbon dioxide cooling rickle of to be a thermal power the be employing honeycomb type fuel assembly of 300MWt (electric power is 120MWe), the agent structure of this long-life supercritical carbon dioxide cooling rickle is pressure vessel, pressure vessel comprises pressure vessel 9 and the reactor core 13 that is placed in pressure vessel 9 and control rod drive mechanisms (CRD) 7, the upper and lower of described pressure vessel 9 is isolated upper chamber 20 and lower chambers 12 by upper division board and lower division board respectively, gap between pressure vessel 9 and core barrel 8 forms descending branch 11, vertically multiple honeycomb type fuel assembly described above and C&P systems is vertically placed with in reactor core 13, fission gas plenum 18 is had above described honeycomb type fuel assembly, fission gas plenum 18 press against division board above, the cluster 15 of C&P systems extends up through division board and is connected with the control rod drive mechanisms (CRD) 7 in upper chamber 20, honeycomb type fuel assembly connecting place in lower division board and reactor core 13, air admission hole is had corresponding to each honeycomb type fuel assembly, for regulating charge flow rate.
As shown in Figure 4, reactor core 13 (in 1/6 symmetry) is that multiple honeycomb type fuel assembly of rounded projections arranged and C&P systems form by adopting cross section, and this arrangement mode can reduce reactor core size, thus reduces pressure vessel size.In order to ensure that reactor core can realize not batch turning of not reloading for 20 years, and consider the factor being convenient to control, it is less that the reactive change of reactor core will be tried one's best, and reactor core 13 adopts high leakage cloth scheme, is divided into three Pu content districts.Lower reactor core can be obtained so effectively to rise in value the higher reactor core increment ratio of Summing Factor, thus realize not batch turning of not reloading for 20 years, and the less target that the reactive change of reactor core will be tried one's best.In order to ensure the negative feedback of reactor core application solutions reactor core, core reflector adopts cooling medium supercritical carbon dioxide (S-CO 2), reactor core neutron can be increased like this and reveal, thus the cavity obtaining bearing is reactive.
In order to control the reactivity of reactor core, control rod cluster 15 is inserted with in described C&P systems, be illustrated in figure 5 C&P systems cross sectional representation, in order to the neutronics increasing C&P systems is worth, C&P systems cluster periphery is the C&P systems outside wall surface 33 of thick layer, in order to cool described wall, inside has wall cooling agent passage 34 aperture.
As shown in Figure 6, each control rod of control rod cluster 15 is round section, is made up of control rod involucrum 36 and the boron carbide absorber 35 be placed in control rod involucrum 36.
As shown in Figure 3, the principle of work of long-life supercritical carbon dioxide cooling rickle of the present invention is: during reactor operation, reactor core pressure is 14MPa, temperature is that the air inlet of 300 DEG C normally runs after air intake opening 10 enters pressure vessel 9 from reactor core, enter lower chambers 12, by the coolant channel wall 5 that is connected with lower division board and the component walls 1 fuel assembly district 14 through each honeycomb type fuel assembly and inter-component spacings, behind fuel assembly district 14 fully heating, normally run gas outlet 19 outflow pressure shell 9 by reactor core.During outlet, temperature has reached 500 DEG C, flow to supercritical pressure turbine 21 subsequently, pushing generator 24 generates electricity, first flow to high-temperature heat-exchanging 26 afterwards, enter cryogenic heat exchanger 27 again, after diverting valve 28, a part flows to precooler 30, a remaining part flows to secondary compressor 23, main compressor 25 is flow to from precooler 30 air-flow out, after main compressor 25, flow to cryogenic heat exchanger 27 again, from cryogenic heat exchanger 27 out after converge through manifold valve 29 and the air-flow flowed out from secondary compressor 23, then high-temperature heat-exchanging 26 is flow to together, normally run air intake opening 10 enter pressure vessel 9 by entering reactor core after heating, complete a thermodynamic cycle.
Under considering accident conditions, emergency episode gas outlet 16 is opened, and gas flows out from pressure vessel 9 thus, enters emergency episode heat interchanger 31, enters pressure vessel 9 more afterwards by emergency episode air intake opening 17, the state thus guarantee reactor core 13 is cooled.Emergency episode heat interchanger 31 provides heat-exchange working medium by external water tank 32.

Claims (10)

1. a honeycomb type fuel assembly, it is characterized in that: this fuel assembly is hexagon, ecto-entad has three layers, is respectively the fuel region (3) of filling in component walls (1), air gap layer (2) and air gap layer (2); 91 coolant channels are uniform-distribution with in described fuel region (3).
2. a kind of honeycomb type fuel assembly according to claim 1, is characterized in that: described coolant channel is made up of coolant channel (4), cooling medium wall (5) and the air gap between coolant channel wall and fuel (6).
3. a kind of honeycomb type fuel assembly according to claim 2, is characterized in that: the material of described cooling medium wall (5) is ODSMA956 stainless steel.
4. a kind of honeycomb type fuel assembly according to claim 1, is characterized in that: the material of described component walls (1) is ODSMA956 stainless steel.
5. a kind of honeycomb type fuel assembly according to claim 1, is characterized in that: the material of described fuel region (3) is mox fuel.
6. a long-life supercritical carbon dioxide cooling rickle, comprise pressure vessel, it is characterized in that: described pressure vessel comprises pressure vessel (9) and the reactor core (13) that is placed in pressure vessel (9) and control rod drive mechanisms (CRD) (7), the upper and lower of described pressure vessel (9) is isolated upper chamber (20) and lower chambers (12) by upper division board and lower division board respectively, gap between pressure vessel (9) and core barrel (8) forms descending branch (11), the honeycomb type fuel assembly described in multiple any one of claim 1 to 5 and C&P systems is vertically vertically placed with in reactor core (13), fission gas plenum (18) is had above described honeycomb type fuel assembly, fission gas plenum (18) press against division board above, the control rod cluster (15) of described C&P systems extends up through division board and is connected with the control rod drive mechanisms (CRD) (7) in upper chamber (20), honeycomb type fuel assembly connecting place in lower division board and reactor core (13), air admission hole is had corresponding to each honeycomb type fuel assembly, for regulating charge flow rate.
7. a kind of long-life supercritical carbon dioxide cooling rickle according to claim 6, it is characterized in that: described reactor core (13) is that multiple honeycomb type fuel assembly of rounded projections arranged and C&P systems form by adopting cross section, the working pressure of reactor core (13) is 14MPa, and Core cooling agent outlet temperature is 500 DEG C.
8. a kind of long-life supercritical carbon dioxide cooling rickle according to claim 6, is characterized in that: leave gap between the honeycomb type fuel assembly that described reactor core (13) is placed.
9. a kind of long-life supercritical carbon dioxide cooling rickle according to claim 6, is characterized in that: described C&P systems comprises C&P systems outer wall (33), be arranged on the 37 control rod clusters (15) be inserted with in multiple wall cooling passage (34) on C&P systems outer wall (33) and C&P systems outer wall (33).
10. a kind of long-life supercritical carbon dioxide cooling rickle according to claim 9, it is characterized in that: each control rod of described control rod cluster (15) is round section, be made up of control rod involucrum (36) and the boron carbide absorber (35) be placed in control rod involucrum (36).
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Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106128517A (en) * 2016-06-24 2016-11-16 西安交通大学 A kind of supercritical carbon dioxide cooling rickle using rod shape fuel assembly
CN108648834A (en) * 2018-04-19 2018-10-12 西安交通大学 Honeycomb briquet type fuel assembly and small size long-life lead bismuth cool down fast reactor reactor core
CN109273105A (en) * 2018-09-13 2019-01-25 中国核动力研究设计院 A kind of supercritical carbon dioxide reactor fuel assemblies
CN110534210A (en) * 2019-08-31 2019-12-03 华南理工大学 A kind of air cooling rickle and its method of controlling security transported for long-distance
CN112242204A (en) * 2020-10-21 2021-01-19 中国科学院合肥物质科学研究院 Molybdenum-based metal ceramic nuclear fuel pellet and preparation method thereof
CN113871033A (en) * 2020-06-30 2021-12-31 哈尔滨工程大学 Reactor core of spherical fission nuclear reactor
WO2022206072A1 (en) * 2021-03-29 2022-10-06 中国核电工程有限公司 Gas-cooled micro-reactor core and gas-cooled micro-reactor

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2001330692A (en) * 2000-05-19 2001-11-30 Tokyo Inst Of Technol Direct cycle fast reactor
CN101777392A (en) * 2009-11-17 2010-07-14 华北电力大学 Accident buffering and removing device for nuclear power station by supercritical CO2
CN102354539A (en) * 2011-09-15 2012-02-15 西安交通大学 Annular fuel element and annular fuel supercritical water reactor
CN103093838A (en) * 2013-01-15 2013-05-08 西安交通大学 Sleeve type rod-shaped fuel assembly and supercritical water-cooling nuclear reactor utilizing same
US20140321590A1 (en) * 2010-01-29 2014-10-30 Advanced Reactor Concepts LLC Small, fast neutron spectrum nuclear power plant with a long refueling interval

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2001330692A (en) * 2000-05-19 2001-11-30 Tokyo Inst Of Technol Direct cycle fast reactor
CN101777392A (en) * 2009-11-17 2010-07-14 华北电力大学 Accident buffering and removing device for nuclear power station by supercritical CO2
US20140321590A1 (en) * 2010-01-29 2014-10-30 Advanced Reactor Concepts LLC Small, fast neutron spectrum nuclear power plant with a long refueling interval
CN102354539A (en) * 2011-09-15 2012-02-15 西安交通大学 Annular fuel element and annular fuel supercritical water reactor
CN103093838A (en) * 2013-01-15 2013-05-08 西安交通大学 Sleeve type rod-shaped fuel assembly and supercritical water-cooling nuclear reactor utilizing same

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
CHRISTOPHER S. HANDWERK: "Optimized core design of a supercritical carbon dioxide-cooled fast reactor", 《THESIS(PH.D)-MASSACHUSETTS INSTITUTE OF TECHNOLOGY,DEPT OF NUCLEAR SCIENCE AND ENGINEERING,2007》 *
黄彦平等: "超临界二氧化碳在核反应堆系统中的应用", 《核动力工程》 *

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106128517A (en) * 2016-06-24 2016-11-16 西安交通大学 A kind of supercritical carbon dioxide cooling rickle using rod shape fuel assembly
CN108648834A (en) * 2018-04-19 2018-10-12 西安交通大学 Honeycomb briquet type fuel assembly and small size long-life lead bismuth cool down fast reactor reactor core
CN108648834B (en) * 2018-04-19 2019-04-09 西安交通大学 Honeycomb briquet type fuel assembly and the cooling fast reactor reactor core of small size long-life lead bismuth
CN109273105A (en) * 2018-09-13 2019-01-25 中国核动力研究设计院 A kind of supercritical carbon dioxide reactor fuel assemblies
CN109273105B (en) * 2018-09-13 2022-03-25 中国核动力研究设计院 Supercritical carbon dioxide reactor fuel assembly
CN110534210A (en) * 2019-08-31 2019-12-03 华南理工大学 A kind of air cooling rickle and its method of controlling security transported for long-distance
CN113871033A (en) * 2020-06-30 2021-12-31 哈尔滨工程大学 Reactor core of spherical fission nuclear reactor
CN112242204A (en) * 2020-10-21 2021-01-19 中国科学院合肥物质科学研究院 Molybdenum-based metal ceramic nuclear fuel pellet and preparation method thereof
WO2022206072A1 (en) * 2021-03-29 2022-10-06 中国核电工程有限公司 Gas-cooled micro-reactor core and gas-cooled micro-reactor

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