CN106128516A - A kind of thorium base fuel assembly and small-sized presurized water reactor - Google Patents
A kind of thorium base fuel assembly and small-sized presurized water reactor Download PDFInfo
- Publication number
- CN106128516A CN106128516A CN201610557308.5A CN201610557308A CN106128516A CN 106128516 A CN106128516 A CN 106128516A CN 201610557308 A CN201610557308 A CN 201610557308A CN 106128516 A CN106128516 A CN 106128516A
- Authority
- CN
- China
- Prior art keywords
- fuel
- fuel assembly
- thorium
- assembly
- small
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Classifications
-
- 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
- G21C5/14—Moderator or core structure; Selection of materials for use as moderator characterised by shape
- G21C5/16—Shape of its constituent parts
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Dispersion Chemistry (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The present invention relates to a kind of thorium base fuel assembly and small-sized presurized water reactor, fuel core body is with thorium oxide (ThO2) it is main, uniformly mix235U abundance is about the UO of 20%2Fuel or239Pu abundance is about the PuO of 18%2Fuel.Fuel rod uses tight lattice arrangement, and fuel rod is spaced about 1.0mm, and by square or triangular lattice arrangement, recycling assembly housing constitutes square or hexagonal fuel assembly.Reactor uses periodical duty, i.e. every some skies of Power operation, shutdown more than about 30 days.The fuel assembly of present invention proposition and small-sized presurized water reactor, have stronger reactive control ability and higher reactor core transfer capability, thus obtain the longer refulling cycle, significantly improve neutron economy and safety.
Description
Technical field
The present invention relates to nuclear reactor technology field, be specifically related to a kind of thorium base fuel assembly and small-sized presurized water reactor.
Background technology
Small-sized presurized water reactor has the outstanding advantages such as system simplification, flexible operation, its purposes widely, such as: outlyingly
District and marine power supply, low-temperature heat supply, desalinization and other purposes hot coproduction of water power etc..In order to improve economy and the market competition
Power, its refulling cycle needs to reach 5 ~ 10 years, and uses monoblock type to reload mode, 12 ~ 18 months batches used with nuclear power plant
There is bigger difference in secondary reloading.
At present, the design of small-sized pressurized water reactor core is mainly by increasing burnable poison loading amount and control rod layout quantity, or adopts
In coolant, add boric acid mode with nuclear power plant, improve reactor core reactivity control ability, to increase length of the cycle.These are arranged
Execute and core loading conceptual design can be caused to complicate, and the reactor reloading pattern cycle does not the farthest reach 5 ~ 10 years, impairs simultaneously
The economy of small-sized presurized water reactor and security advantages.Therefore, it is highly desirable to, for small-sized pressurized water reactor core operation characteristic, i.e. transport
Row power is indefinite, frequent shutdown etc., proposes novel reactor core assembly and method for designing, ensure its system simplify, flexible operation
Under conditions of advantage so that it is the refulling cycle reaches 5 ~ 10 years, thus improves its economy and the market competitiveness.
Summary of the invention
It is an object of the invention to provide a kind of refulling cycle reaches the thorium base fuel assembly of 5 ~ 10 years, to solve existing reactor core
The problem that refulling cycle does not reaches 5 ~ 10 years.
Moreover, it relates to the small-sized presurized water reactor being made up of thorium base fuel assembly.
The present invention solves the problems referred to above and be the technical scheme is that a kind of thorium base fuel assembly, including some fuel rods,
Guide pipe, the fuel core body of described fuel rod is thorium base fuel core body.
The design of existing small-sized pressurized water reactor core is mainly by increasing burnable poison loading amount and control rod layout quantity, or adopts
In coolant, add boric acid mode with nuclear power plant, improve reactor core reactivity control ability, to increase length of the cycle.These are arranged
Execute and core loading conceptual design can be caused to complicate, and the reactor reloading pattern cycle does not the farthest reach 5 ~ 10 years, impairs simultaneously
The economy of small-sized presurized water reactor and security advantages;Thorium base fuel core body of the present invention specifically refers to a kind of with thorium anhydride
It is main fuel core body, can obtain with neutron bombardment thorium233U.The present invention makes full use of232Th can make reactor core neutron energy spectrum harden
Neutronics characteristic, it is achieved lower reactor core initial reactivity, the mildest reactivity is with burnup change curve, thus has
Higher reactive control ability, adds length of the cycle, and then extends the reactor reloading pattern cycle.
Further, thorium base fuel core body, with thorium anhydride as matrix, mixes in thorium anhydride matrix235U abundance is
The UO of 20%2Fuel or239Pu abundance is the PuO of 18%2Fuel.
Further, the external diameter of guide pipe and the external diameter of fuel rod are identical.
Preferably, being arranged by the external diameter of fuel rod and be about 9.1mm, employing large scale fuel rod is joined with thorium base fuel core body
Closing, reactor core neutron energy spectrum can be made significantly to harden, conversion capability is substantially improved.
Further, the spacing between adjacent guide pipe, fuel rod and between adjacent 2 fuel rods is 1.0mm.
I.e. thorium base fuel assembly uses tight lattice to arrange, and then improves thorium base fuel assembly in small-sized presurized water reactor
Quantity, can not only make reactor core neutron energy spectrum significantly harden further, and conversion capability is substantially improved, and can improve thorio combustion
The reactive control ability of material assembly, increases length of the cycle, extends the reactor reloading pattern cycle.
Further, fuel rod, guide pipe are evenly distributed according to square grid, constitute square fuel assembly, peripheral
There is square shaped module box.
Further, fuel rod, guide pipe are evenly distributed according to triangular lattice, constitute regular hexagon fuel assembly, outward
It is with regular hexagon assembly housing.
A kind of small-sized presurized water reactor formed such as above-mentioned thorium base fuel assembly, including some square fuel assemblies or positive hexagonal
Shape fuel assembly.
Further, small-sized presurized water reactor uses control rod to control reactor core excess reactivity and loss compensates, and reactor is adopted
Use cycling service pattern.
Reactor uses periodical duty, i.e. every some skies of Power operation, shutdown more than about 30 days.The present invention proposes
Fuel assembly and small-sized presurized water reactor, there is stronger reactive control ability and higher reactor core transfer capability, thus obtain
The longer refulling cycle, significantly improve neutron economy and safety, cycling service, it is ensured that heap in-core232During Th absorbs
Son produces233Pa, it is possible to fully decay production233U, reduces235The wear rate of U, makes reactor core length of the cycle prolong further
Long.In sum, using the small-sized presurized water reactor of thorium base fuel tight lattice fuel assembly, the refulling cycle can significantly extend, from
And significantly improve its economy.
To sum up, the invention has the beneficial effects as follows:
1, compared with conventional fuel assembly and corresponding small-sized presurized water reactor thereof, owing to the fuel core body of the present invention uses thorium base fuel,
Take full advantage of232The neutronics characteristic of Th, it is achieved that lower initial reactivity, the mildest reactivity changes with burnup
Curve, thus there is higher reactive control ability.
2, small-sized presurized water reactor involved in the present invention uses periodical duty, it is ensured that heap in-core232Th absorbs neutron
Produce233Pa, it is possible to fully decay production233U, reduces235The wear rate of U, makes reactor core length of the cycle extend further.
3, the present invention uses large scale fuel rod, tight lattice to arrange and thorium base fuel, makes reactor core neutron energy spectrum the hardest
Changing, conversion capability is substantially improved.
4, compared with conventional fuel assembly and corresponding small-sized presurized water reactor thereof, the present invention can significantly improve fuel just loading amount,
With meet long circulating core loading for235The requirement of U just loading amount.
Accompanying drawing explanation
Fig. 1 is square tight lattice thorium base fuel component diagram;
Fig. 2 is square small-sized presurized water reactor schematic diagram;
Fig. 3 is hexagon tight lattice thorium base fuel component diagram;
Fig. 4 is hexagon small-sized presurized water reactor schematic diagram.
Labelling and the title of corresponding parts in accompanying drawing:
1-fuel rod, 2-guide pipe, 3-square shaped module box, 4-square shaped module, 5-hexagonal assembly.
Detailed description of the invention
Below in conjunction with embodiment and accompanying drawing, detailed description further is made in invention, but embodiments of the present invention are not
It is limited to this.
Embodiment 1:
As it is shown in figure 1, a kind of thorium base fuel assembly, contain 232 shell thickness be 0.5mm, external diameter be the fuel rod of 9.1mm
1,57 external diameter is the guide pipe 2 of 9.1mm, and fuel rod 1, guide pipe 2 are spaced, and the spacing of consecutive fuel rod 1 is 1.0mm,
Consecutive fuel rod 1, the spacing of guide pipe 2 are 1.0mm, and fuel assembly opposite side distance is 172.7mm, mix in fuel pellet235U
Abundance is the UO of 20%2Fuel, UO2Fuel and ThO2The ratio of fuel is 1:1,235U percentage composition is 8.8%,232Th content is
43.9%, fuel rod 1, guide pipe 2 are evenly distributed according to square grid, constitute square fuel assembly 4, are with outward square
Assembly housing 3.
As in figure 2 it is shown, a kind of small-sized presurized water reactor, the square fuel assembly 4 shown in Fig. 1 is used to construct as shown in Figure 2
Reactor core, arranges 57 box fuel assemblies altogether, and fuel assembly centre-to-centre spacing is 174mm, and equivalent diameter is 1482mm, and active region height is
1600mm, small-sized presurized water reactor uses control rod to control reactor core excess reactivity and loss compensates, and reactor uses periodically fortune
Row mode.
In the case of reactor core thermal power rating is 250MW, fuel rod mean linear power density density is 11.8kW/m, the average merit of body
Rate density is 90.5MW/m3, using cycling service pattern, interval Shutdown time is 30 days, and the phase in burnup longevity can reach 1500
Equivalent full power day, the refulling cycle is about 7 years.
Embodiment 2:
The present embodiment is based on embodiment 1, as it is shown in figure 1, a kind of thorium base fuel assembly, containing 232 shell thickness is
0.5mm, external diameter are the guide pipe 2 that 1,57 external diameters of fuel rod are 9.0mm of 9.0 mm, and fuel rod 1, guide pipe 2 are spaced,
The spacing of consecutive fuel rod 1 is 1.0mm, and consecutive fuel rod 1, the spacing of guide pipe 2 are 1.0mm, and fuel assembly opposite side distance is
172.7mm, mixes in fuel pellet239Pu abundance is the PuO of 18%2Fuel, PuO2Fuel and ThO2The ratio of fuel is 1:1
, 239Pu percentage total content is 8.8%,232Th content is 43.9%, and fuel rod 1, guide pipe 2 are evenly distributed according to square grid,
Constitute square fuel assembly 4, be with outward square shaped module box 3.
As in figure 2 it is shown, a kind of small-sized presurized water reactor, the square fuel assembly 4 shown in Fig. 1 is used to construct as shown in Figure 2
Reactor core, arranges 57 box fuel assemblies altogether, and fuel assembly centre-to-centre spacing is 174mm, and equivalent diameter is 1482mm, and active region height is
1600mm, small-sized presurized water reactor uses control rod to control reactor core excess reactivity and loss compensates, and reactor uses periodically fortune
Row mode.
In the case of reactor core thermal power rating is 250MW, fuel rod mean linear power density density is 11.8kW/m, the average merit of body
Rate density is 90.5MW/m3, uses cycling service pattern, and interval Shutdown time is 30 days, and the phase in burnup longevity can reach 1500
Equivalent full power day, the refulling cycle is about 7 years.
Embodiment 3:
As it is shown on figure 3, a kind of thorium base fuel assembly, contain 270 shell thickness be 0.5mm, external diameter be the fuel rod of 9.1mm
1,61 external diameter is the guide pipe 2 of 9.1mm, and fuel rod 1, guide pipe 2 are spaced, and the spacing of consecutive fuel rod 1 is 1.0mm,
Consecutive fuel rod 1, the spacing of guide pipe 2 are 1.0mm, and fuel assembly opposite side distance is 186mm, mix 235U rich in fuel pellet
Degree is the UO of 20%2Fuel, UO2Fuel and ThO2The ratio of fuel is 1:1,235U percentage composition is 8.8%,232Th content is
43.9%, fuel rod 1, guide pipe 2 are evenly distributed according to triangular lattice, constitute regular hexagon fuel assembly 5, are with outward positive six
Dihedral assembly housing.
As shown in Figure 4, a kind of small-sized presurized water reactor, use the positive regular hexagon fuel assembly 5 shown in Fig. 3 to construct such as Fig. 4 institute
The reactor core shown, arranges 55 box fuel assemblies altogether, and fuel assembly centre-to-centre spacing is 188mm, and equivalent diameter is 1464mm, and active region is high
Degree is 1600mm, and small-sized presurized water reactor uses control rod to control reactor core excess reactivity and loss compensates, and reactor uses the cycle
Property operational mode.
In the case of reactor core thermal power rating is 250MW, fuel rod mean linear power density density is 10.5kW/m, the average merit of body
Rate density is 92.8MW/m3, using cycling service pattern, interval Shutdown time is 30 days, and the phase in burnup longevity can reach 1600
Equivalent full power day, the refulling cycle is about 7.5 years.
Embodiment 4:
The present embodiment is based on embodiment 3, as it is shown on figure 3, a kind of thorium base fuel assembly, containing 270 shell thickness is
0.5mm, external diameter are the guide pipe 2 that 1,61 external diameters of fuel rod are 9.0 mm of 9.0mm, and fuel rod 1, guide pipe 2 are spaced,
The spacing of consecutive fuel rod 1 is 1.0mm, and consecutive fuel rod 1, the spacing of guide pipe 2 are 1.0mm, and fuel assembly opposite side distance is
186mm, mixes in fuel pellet239Pu abundance is the PuO of 18%2Fuel, PuO2Fuel and ThO2The ratio of fuel is 1:1,239Pu percentage total content is 8.8%,232Th content is 43.9%, and fuel rod 1, guide pipe 2 are evenly distributed according to triangular lattice, structure
Become regular hexagon fuel assembly 5, be with outward regular hexagon assembly housing.
As shown in Figure 4, a kind of small-sized presurized water reactor, use the positive regular hexagon fuel assembly 5 shown in Fig. 3 to construct such as Fig. 4 institute
The reactor core shown, arranges 55 box fuel assemblies altogether, and fuel assembly centre-to-centre spacing is 188mm, and equivalent diameter is 1464mm, and active region is high
Degree is 1600mm, and small-sized presurized water reactor uses control rod to control reactor core excess reactivity and loss compensates, and reactor uses the cycle
Property operational mode.
In the case of reactor core thermal power rating is 250MW, fuel rod mean linear power density density is 10.5kW/m, the average merit of body
Rate density is 92.8MW/m3, using cycling service pattern, interval Shutdown time is 30 days, and the phase in burnup longevity can reach 1600
Equivalent full power day, the refulling cycle is about 7.5 years.
As it has been described above, the present invention can preferably be realized.
Claims (8)
1. a thorium base fuel assembly, including some fuel rods (1), guide pipe (2), it is characterised in that described fuel rod (1)
Fuel core body is thorium base fuel core body.
A kind of thorium base fuel assembly the most according to claim 1, it is characterised in that described thorium base fuel core body is with titanium dioxide
Thorium is matrix, mixes in thorium anhydride matrix235U abundance is the UO of 20%2Fuel or239Pu abundance is the PuO of 18%2Fuel.
A kind of thorium base fuel assembly the most according to claim 1, it is characterised in that the external diameter of described guide pipe (2) and combustion
The external diameter of charge bar (1) is identical.
A kind of thorium base fuel assembly the most according to claim 1, it is characterised in that adjacent guide pipe (2), fuel rod (1)
Between and adjacent 2 fuel rods (1) between spacing be 1.0mm.
A kind of thorium base fuel assembly the most according to claim 1, it is characterised in that described fuel rod (1), guide pipe (2)
Evenly distributed according to square grid, constitute square fuel assembly (4), be with outward square shaped module box (3).
A kind of thorium base fuel assembly the most according to claim 1, it is characterised in that described fuel rod (1), guide pipe (2)
Evenly distributed according to triangular lattice, constitute regular hexagon fuel assembly (5), be with outward regular hexagon assembly housing.
7. the small-sized presurized water reactor being made up of thorium base fuel assembly described in any one of claim 1-6, it is characterised in that include
Some square fuel assemblies (4) or regular hexagon fuel assembly (5).
The small-sized presurized water reactor of one the most according to claim 7, it is characterised in that small-sized presurized water reactor uses control rod to control heap
Core excess reactivity and loss thereof compensate, and reactor uses cycling service pattern.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201610557308.5A CN106128516B (en) | 2016-07-15 | 2016-07-15 | A kind of thorium base fuel component and small-sized presurized water reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201610557308.5A CN106128516B (en) | 2016-07-15 | 2016-07-15 | A kind of thorium base fuel component and small-sized presurized water reactor |
Publications (2)
Publication Number | Publication Date |
---|---|
CN106128516A true CN106128516A (en) | 2016-11-16 |
CN106128516B CN106128516B (en) | 2017-12-15 |
Family
ID=57283198
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN201610557308.5A Active CN106128516B (en) | 2016-07-15 | 2016-07-15 | A kind of thorium base fuel component and small-sized presurized water reactor |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN106128516B (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN110111913A (en) * | 2018-09-13 | 2019-08-09 | 中国核动力研究设计院 | The test reactor core and method of hexagon thimble tube fuel reactor core neutron fluence rate measurement |
CN111063460A (en) * | 2019-12-13 | 2020-04-24 | 南华大学 | Method for prolonging core life of pressurized water reactor |
CN114242272A (en) * | 2021-12-17 | 2022-03-25 | 中国核动力研究设计院 | Non-refueling reactor core for small nuclear power supply |
Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3859165A (en) * | 1970-07-29 | 1975-01-07 | Atomic Energy Commission | Epithermal to intermediate spectrum pressurized heavy water breeder reactor |
US4493809A (en) * | 1982-03-08 | 1985-01-15 | Ga Technologies Inc. | Uranium thorium hydride nuclear fuel |
CN103165206A (en) * | 2011-12-15 | 2013-06-19 | 中国核动力研究设计院 | Preparation method of thorium-uranium mixed oxide ceramic microspheres |
CN103943161A (en) * | 2013-01-17 | 2014-07-23 | 加拿大原子能有限公司 | Heterogeneous Core Designs And Thorium Based Fuels For Heavy Water Reactors |
CN104446478A (en) * | 2013-09-24 | 2015-03-25 | 中核北方核燃料元件有限公司 | Method for preparing thorium dioxide pellets |
-
2016
- 2016-07-15 CN CN201610557308.5A patent/CN106128516B/en active Active
Patent Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3859165A (en) * | 1970-07-29 | 1975-01-07 | Atomic Energy Commission | Epithermal to intermediate spectrum pressurized heavy water breeder reactor |
US4493809A (en) * | 1982-03-08 | 1985-01-15 | Ga Technologies Inc. | Uranium thorium hydride nuclear fuel |
CN103165206A (en) * | 2011-12-15 | 2013-06-19 | 中国核动力研究设计院 | Preparation method of thorium-uranium mixed oxide ceramic microspheres |
CN103943161A (en) * | 2013-01-17 | 2014-07-23 | 加拿大原子能有限公司 | Heterogeneous Core Designs And Thorium Based Fuels For Heavy Water Reactors |
CN104446478A (en) * | 2013-09-24 | 2015-03-25 | 中核北方核燃料元件有限公司 | Method for preparing thorium dioxide pellets |
Non-Patent Citations (1)
Title |
---|
郑洪涛 等: ""紧凑型压水堆钍-铀燃料长寿期堆芯物理特性研究"", 《核动力工程》 * |
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN110111913A (en) * | 2018-09-13 | 2019-08-09 | 中国核动力研究设计院 | The test reactor core and method of hexagon thimble tube fuel reactor core neutron fluence rate measurement |
CN110111913B (en) * | 2018-09-13 | 2022-02-11 | 中国核动力研究设计院 | Test reactor core and method for measuring neutron fluence rate of hexagonal sleeve type fuel reactor core |
CN111063460A (en) * | 2019-12-13 | 2020-04-24 | 南华大学 | Method for prolonging core life of pressurized water reactor |
CN114242272A (en) * | 2021-12-17 | 2022-03-25 | 中国核动力研究设计院 | Non-refueling reactor core for small nuclear power supply |
CN114242272B (en) * | 2021-12-17 | 2024-01-30 | 中国核动力研究设计院 | Small-sized nuclear power supply is with not reloading reactor core |
Also Published As
Publication number | Publication date |
---|---|
CN106128516B (en) | 2017-12-15 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US4285769A (en) | Control cell nuclear reactor core | |
US5677938A (en) | Method for fueling and operating a nuclear reactor core | |
US20100054389A1 (en) | Mixed oxide fuel assembly | |
CN106128516A (en) | A kind of thorium base fuel assembly and small-sized presurized water reactor | |
CN103366836B (en) | Fuel ball, method for making and nuclear reactor | |
CN110867261B (en) | Multi-type pellet mixed loading metal cooling reactor and management method | |
KR100935560B1 (en) | Fuel bundle for pressurized-water reactor and method of designing fuel bundle | |
CN101206930B (en) | Method for cycle using multi-stack combined nuclear fuel | |
CN110853774B (en) | Zirconium hydride moderated metal cooling reactor miniaturization design method and reactor | |
ZA200503518B (en) | Use of isotopically enriched nitride in actinide fuel in nuclear reactors. | |
Hibi et al. | Conceptual designing of reduced-moderation water reactor with heavy water coolant | |
CN111710444B (en) | Reactor core loading method of annular fuel heat supply reactor | |
US20100166133A1 (en) | Use of isotopically enriched nitrogen in actinide fuel in nuclear reactors | |
CN103366835A (en) | Nuclear fuel pellet and manufacturing method thereof, and nuclear reactor | |
Fareha et al. | Design Study of 600 MWt Long Life Modular Gas Cooled Fast Reactors | |
CN112366010A (en) | First circulation loading method for applying FCM fuel to million kilowatt pressurized water reactor | |
Subkhi et al. | Netronic design of small long-life PWR using thorium cycle | |
CN113793702B (en) | Intrinsic safety integrated small-sized villaumite cooling high-temperature reactor core | |
US20240047088A1 (en) | High energy nuclear fuel, fuel assembly, and refueling method | |
Trianti et al. | Preliminary design study of small long life boiling water reactor (BWR) with tight lattice thorium nitride fuel | |
Li et al. | Conceptual core design of HAPPY200 reactor | |
Leer et al. | Fast modular reactor nuclear design parameters of fuel cycle and power distributions | |
Wang et al. | Pre-conceptual core design of a LBE-cooled fast reactor (BLESS) | |
Zou et al. | China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen, Guangdong, China zoutingting@ cgnpc. com. cn | |
Yeoh et al. | Pre-Conceptual Core Design of a Micro-LBE-Cooled Fast Reactor |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
C06 | Publication | ||
PB01 | Publication | ||
C10 | Entry into substantive examination | ||
SE01 | Entry into force of request for substantive examination | ||
GR01 | Patent grant | ||
GR01 | Patent grant |