CN114267464A - Pressurized water reactor core refueling long-period fuel management method and application - Google Patents
Pressurized water reactor core refueling long-period fuel management method and application Download PDFInfo
- Publication number
- CN114267464A CN114267464A CN202111583867.0A CN202111583867A CN114267464A CN 114267464 A CN114267464 A CN 114267464A CN 202111583867 A CN202111583867 A CN 202111583867A CN 114267464 A CN114267464 A CN 114267464A
- Authority
- CN
- China
- Prior art keywords
- fuel
- refueling
- core
- assemblies
- reactor core
- 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.)
- Pending
Links
- 239000000446 fuel Substances 0.000 title claims abstract description 160
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 34
- 238000007726 management method Methods 0.000 title claims abstract description 31
- 230000000712 assembly Effects 0.000 claims abstract description 66
- 238000000429 assembly Methods 0.000 claims abstract description 66
- 238000000034 method Methods 0.000 claims description 15
- CMIHHWBVHJVIGI-UHFFFAOYSA-N gadolinium(III) oxide Inorganic materials [O-2].[O-2].[O-2].[Gd+3].[Gd+3] CMIHHWBVHJVIGI-UHFFFAOYSA-N 0.000 claims description 13
- 239000008188 pellet Substances 0.000 claims description 7
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 claims description 6
- 229910052796 boron Inorganic materials 0.000 claims description 6
- 239000002826 coolant Substances 0.000 claims description 6
- 230000007774 longterm Effects 0.000 claims description 5
- 229910052688 Gadolinium Inorganic materials 0.000 description 6
- UIWYJDYFSGRHKR-UHFFFAOYSA-N gadolinium atom Chemical compound [Gd] UIWYJDYFSGRHKR-UHFFFAOYSA-N 0.000 description 6
- 239000002574 poison Substances 0.000 description 6
- 231100000614 poison Toxicity 0.000 description 3
- 239000007787 solid Substances 0.000 description 3
- 239000000463 material Substances 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000011156 evaluation Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 230000007704 transition Effects 0.000 description 1
Classifications
-
- 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a pressurized water reactor core refueling long-period fuel management method, wherein each refueling of a balance cycle adopts new fuel assemblies with enrichment degree exceeding 5 percent, and the number of the new fuel assemblies per refueling is less than or equal to 1/2 of the number of the reactor core assemblies; the equilibrium cycle was a 24 month refuel period. By adopting the new fuel assembly refueling with the enrichment degree of more than 5 percent and not exceeding 1/2 of the number of reactor core assemblies each time, the fuel economy can be effectively improved, the fuel management method with good fuel economy in a 24-month refueling period is realized, and the wide application of the 24-month refueling mode of pressurized water reactors of various reactor types of large-scale nuclear power plants is realized.
Description
Technical Field
The invention relates to the technical field of reactors of pressurized water reactor nuclear power plants, in particular to a pressurized water reactor core refueling long-period fuel management method and application.
Background
The nuclear pressurized water reactor core fuel management generally refers to determining the fuel enrichment degree, the type of combustible poison, the arrangement of various assemblies and poisons in the core and the like from a first circulation to a balanced circulation core, so that the design result of the pressurized water reactor core meets the nuclear design criterion and the overall requirements of a power plant. The quality of reactor core fuel management directly influences the economy and safety of the nuclear power plant and is the basis of subsequent safety analysis or evaluation.
At present, the mainstream cycle length of the in-service nuclear power plants all around the world is about 18 months, a few nuclear power plants applying a 24-month refueling strategy in the United states are all nuclear power plants with relatively low reactor power started in the last 70 th century, and the linear power density is generally between 145 and 170W/cm. For the core of a pressurized water reactor of a nuclear power plant with million kilowatt power, due to the limitation of high linear power density and enrichment degree, the cost of a 24-month refueling strategy is high, and the fuel economy index of a 24-month refueling mode is not as good as that of 18-month refueling.
Disclosure of Invention
The invention aims to solve the technical problems that the existing method for managing the fuel of the pressurized water reactor core in the long period of refueling has high cost and low economy, so that the long period refueling mode cannot be widely applied to the pressurized water reactor core of a large-scale nuclear power plant. The method aims to provide a pressurized water reactor core refueling long-period fuel management method and application, realize 24-month refueling periods of balanced cycle, greatly improve the average batch unloading fuel consumption of each batch of fuel assemblies compared with the current 18-month fuel design of a same-reactor power plant after the reactor core reaches balance, and obviously improve the fuel utilization rate.
The invention is realized by the following technical scheme:
the invention aims to provide a method for managing fuel in a pressurized water reactor core for a long period by refueling, wherein balanced cycle refueling adopts new fuel assemblies with enrichment degree more than 5 percent, and the number of the new fuel assemblies per refueling is less than or equal to 1/2 of the number of the core assemblies; the equilibrium cycle was a 24 month refuel period.
Optionally, the core is cooled and moderated with light water, the coolant containing soluble boron.
Optionally, the core balancing cycle employs extremely low leakage loading.
Optionally, the new fuel assemblies and the fuel assemblies with lower burnup are arranged in the inner area of the reactor core and are arranged in a crossed mode during refueling, and the fuel assemblies with higher burnup are arranged on the outermost circle of the reactor core.
Optionally, the enrichment of the new fuel assembly is one or more.
Alternatively, the enrichment of the new fuel assembly may be 5.45% and/or 5.95%.
Optionally, each of said new fuel assemblies is arranged in a 17 x 17 array with 264 fuel rods, 24 guide tubes and one in-stack instrumentation tube;
the number of gadolinium-carrying fuel rods in the new fuel assembly is 4 or 8 or 12 or 16 or 20 or 24.
Optionally, UO in the new fuel assembly2-Gd2O3The enrichment degree of U-235 in the fuel pellet is 2.5 percent, and Gd2O3Is 10% by weight.
A second object of the present invention is to provide an application of the above fuel management method for long-term fuel management design of pressurized water reactors of various mainstream reactor types.
Compared with the prior art, the invention has the following advantages and beneficial effects:
according to the invention, the new fuel assemblies with enrichment degree exceeding 5% are adopted for refueling in the equilibrium cycle, the number of refueling assemblies does not exceed 1/2 of the number of reactor core assemblies each time, the equilibrium cycle adopts a 24-month refueling cycle, the fuel economy can be effectively improved, the fuel management method with a 24-month refueling cycle with good fuel economy is realized, and the wide application of the 24-month refueling mode aiming at various mainstream reactor type large pressurized water reactor nuclear power plants is realized.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not used as limitations of the present invention.
In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present invention. However, it will be apparent to one of ordinary skill in the art that: it is not necessary to employ these specific details to practice the present invention. In other instances, well-known structures, circuits, materials, or methods have not been described in detail so as not to obscure the present invention.
Throughout the specification, reference to "one embodiment," "an embodiment," "one example," or "an example" means: the particular features, structures, or characteristics described in connection with the embodiment or example are included in at least one embodiment of the invention. Thus, the appearances of the phrases "one embodiment," "an embodiment," "one example" or "an example" in various places throughout this specification are not necessarily all referring to the same embodiment or example. Furthermore, the particular features, structures, or characteristics may be combined in any suitable combination and/or sub-combination in one or more embodiments or examples.
Examples
Because the existing method for managing the fuel of the pressurized water reactor core in the long period of refueling has high cost and low economy, the long period refueling mode cannot be widely applied to the pressurized water reactor core of a large-scale nuclear power plant.
In order to solve the above problems, an embodiment of the present invention provides a method for long-period fuel management of pressurized water reactor core refueling, which adopts the following technical scheme: a pressurized water reactor core refueling long-period fuel management method is characterized in that balanced cycle refueling adopts new fuel assemblies with enrichment degree exceeding 5%, and the number of the new fuel assemblies recharged each time is less than or equal to 1/2 of the number of the reactor core assemblies; the equilibrium cycle was a 24 month refuel period.
For a pressurized water reactor core, the fuel economy can be effectively improved by adopting the refueling of new fuel assemblies with the enrichment degree of more than 5%, the number of refueling assemblies does not exceed 1/2 of the number of components of the reactor core each time, the balanced circulation adopts a 24-month refueling period, the fuel management method of the 24-month refueling period with good fuel economy is realized, and the wide application of the 24-month refueling mode aiming at a large-scale nuclear power plant is realized.
Further, the core is cooled and moderated with light water, and the coolant contains soluble boron.
Furthermore, the transition circulation and the balance circulation of the reactor core adopt an extremely low leakage loading mode.
Further, when the fuel is replaced, the new fuel assemblies and the fuel assemblies with low fuel consumption are arranged in the inner area of the reactor core in a crossed mode, and the fuel assemblies with high fuel consumption are arranged on the outermost circle of the reactor core.
Further, the enrichment of the new fuel assembly is one or more.
Further, the enrichment of the new fuel assembly is varied, preferably the enrichment of the new fuel assembly is 5.45% and/or 5.95%.
Further, each of the new fuel assemblies was arranged in a 17 x 17 array with 264 fuel rods, 24 guide tubes and an in-stack instrumentation tube.
Further, the number of gadolinium-carrying fuel rods in the new fuel assembly is 4 or 8 or 12 or 16 or 20 or 24.
Further, the new fuelUO in a material assembly2-Gd2O3The enrichment degree of U-235 in the fuel pellet is 2.5 percent, and Gd2O3Is 10% by weight.
According to the long-period fuel management method for pressurized water reactor core refueling, the new fuel assemblies with the enrichment degree larger than 5% are adopted during refueling, the refueling assemblies do not exceed 1/2 of the full-reactor assemblies, and the loading mode of the reactor core, the enrichment degree of the new fuel assemblies, the arrangement mode of fuel rods in the new fuel assemblies and the UO in the new fuel assemblies are reasonably designed2-Gd2O3The enrichment degree of the fuel pellet and the weight of the poison are applied to a large pressurized water reactor nuclear power plant, the limitations of high online power density and the enrichment degree of a pressurized water reactor core of the large pressurized water reactor nuclear power plant are overcome, and the cost of a 24-month refueling period is reduced; the average batch unloading fuel consumption of each batch of fuel assemblies is greatly improved compared with the current 18-month fuel design of the same-pile power plant, the fuel utilization rate is obviously improved, and the availability of the power plant is obviously increased.
Example 1
This example is for a one million kilowatt nuclear power plant reactor core consisting of 157 fuel assemblies. The core is cooled and moderated with light water, and the coolant contains soluble boron.
The scheme loads 72 new fuel assemblies with the enrichment degree of 5.95% per cycle and arranges the new fuel assemblies inside a core. Old fuel assemblies which burn for a plurality of cycles are placed on the outermost circle of the reactor core, and old fuel assemblies which burn for a plurality of cycles are placed on the inner circle of the reactor core, and old fuel assemblies which burn for a plurality of cycles are placed in a crossed mode with new fuel assemblies to form an extremely-low leakage loading mode.
Each new fuel assembly was arranged in a 17 x 17 array with 264 fuel rods, 24 guide tubes and an in-stack instrumentation tube. Gadolinium and UO are used as solid burnable poison2-Gd2O3The enrichment degree of U-235 in the fuel pellet is 2.5 percent, and Gd2O3Is 10% by weight. Typical numbers of gadolinium-loaded fuel rods in the new fuel assembly are 4, 8, 12, 16, 20 or 24.
Table 1 below is a comparison of the fuel management protocol for a balance cycle of a 100 kilowatt unit 157 core over 18 months, 24 month refueling periods. Therefore, the reactor core fuel management method can realize 24-month long-period refueling design of the balance cycle, the cycle length of the balance cycle is longer than 649 equivalent full power days, and the availability of a power plant is more than 93%; the fuel assembly batch unloading fuel consumption is improved by over 12Gwd/tU compared with the highest batch unloading fuel consumption of 18-month fuel exchange with the reactor core, and the average fuel consumption of the maximum unloading assembly is lower than 62 Gwd/tU.
TABLE 1100 Ten thousand kilowatt unit 157 reactor core different refueling period fuel management scheme comparison
Example 2
This example is for a sixty-thousand kilowatt nuclear power plant reactor core consisting of 121 fuel assemblies. The core is cooled and moderated with light water, and the coolant contains soluble boron.
The scheme loads 56 new fuel assemblies with the enrichment degree of 5.45% per cycle and arranges the new fuel assemblies inside a core. The outermost circle of the core is placed with old fuel assemblies that burn through multiple cycles. Old fuel assemblies which are burnt and have low burn-up and are arranged in the inner ring of the reactor core in a crossing way with new fuel assemblies to form an extremely low leakage loading mode.
Each new fuel assembly was arranged in a 17 x 17 array with 264 fuel rods, 24 guide tubes and an in-stack instrumentation tube. Gadolinium and UO are used as solid burnable poison2-Gd2O3The enrichment degree of U-235 in the fuel pellet is 2.5 percent, and Gd2O3Is 10% by weight. Typical numbers of gadolinium-loaded fuel rods in the new fuel assembly are 4, 8, 12, 16, 20 or 24.
Table 2 below is a fuel management schedule comparison of 18 month, 24 month refueling cycles for a core of 121 fuel assemblies in a 60 ten-thousand kilowatt fleet. As can be seen from Table 2, the reactor core fuel management method of the embodiment can realize 24-month long-period refueling design, the cycle length of the equilibrium cycle is 692 equivalent full power days, and the availability of the power plant is more than 93%; the fuel assembly batch unloading fuel consumption is about 52Gwd/tU, is improved by about 5Gwd/tU compared with the highest batch unloading fuel consumption of 18-month fuel exchange with the reactor core, and the average fuel consumption of the maximum unloading assembly is lower than 58 Gwd/tU.
Comparison of fuel management schemes for different refueling periods of reactor core of 260 ten thousand kilowatt unit 121
Example 3
This embodiment is directed to a core of a million kilowatt nuclear power plant reactor consisting of 177 fuel assemblies. The core is cooled and moderated with light water, and the coolant contains soluble boron.
According to the scheme, 80 new fuel assemblies are loaded in each cycle, wherein the new fuel assemblies comprise two enrichment degrees which are respectively 5.45% and 5.95%, the number of the new fuel assemblies with the enrichment degree of 5.45% is 4, the number of the new fuel assemblies with the enrichment degree of 5.95% is 76, and the new fuel assemblies are arranged in a reactor core. The outermost circle of the core is placed with old fuel assemblies that burn through multiple cycles. Old fuel assemblies which are burnt and have low burn-up and are arranged in the inner ring of the reactor core in a crossing way with new fuel assemblies to form an extremely low leakage loading mode.
Each new fuel assembly was arranged in a 17 x 17 array with 264 fuel rods, 24 guide tubes and an in-stack instrumentation tube. Gadolinium and UO are used as solid burnable poison2-Gd2O3The enrichment degree of U-235 in the fuel pellet is 2.5 percent, and Gd2O3Is 10% by weight. Typical numbers of gadolinium-loaded fuel rods in the new fuel assembly are 4, 8, 12, 16, 20 or 24.
The following table 3 is a fuel management protocol comparison for an 18 month, 24 month refueling cycle for a core of 177 fuel assemblies in a 100 kilowatt unit. As can be seen from table 3, the reactor core fuel management method of the present embodiment can realize a long-period refueling design of 24 months, the cycle length of the equilibrium cycle is 665 equivalent full power days, and the availability of the power plant reaches more than 93%; the fuel assembly batch unloading fuel consumption is about 58Gwd/tU, the fuel assembly batch unloading fuel consumption is improved by about 10Gwd/tU compared with the highest batch unloading fuel consumption of 18-month fuel exchange with the reactor core, and the average fuel consumption of the maximum unloading assembly is lower than 62 Gwd/tU.
Comparison of fuel management schemes of different refueling periods of reactor core of 3100 ten thousand kilowatt unit 177
Wherein, the availability of the power plant in each table is converted according to the cycle length/(cycle length + overhaul time).
It can be seen from the above embodiments that the fuel management method provided by the present invention greatly improves the utilization of nuclear fuel and the operating economy of a power plant.
Methods, procedures, equipment and the like not mentioned in the present patent application are all methods known in the art and are not described in detail herein.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (9)
1. A pressurized water reactor core refueling long-period fuel management method is characterized in that balanced cycle refueling adopts new fuel assemblies with enrichment degree exceeding 5%, and the number of the new fuel assemblies recharged each time is less than or equal to 1/2 of the number of the core assemblies; the equilibrium cycle was a 24 month refuel period.
2. The method of claim 1, wherein the core is cooled and moderated with light water, and the coolant contains soluble boron.
3. The method of claim 1, wherein the core is loaded in a very low leakage mode during the balance cycle.
4. The method of claim 3, wherein the new fuel assemblies and the less-burned fuel assemblies are arranged in the inner region of the core and arranged in a crossing manner during refueling, and the more-burned fuel assemblies are arranged at the outermost periphery of the core.
5. The method of claim 1, wherein the enrichment of the new fuel assemblies is one or more of the enrichment of the new fuel assemblies.
6. The PWR core refueling long-term fuel management method of claim 5, wherein the enrichment of the new fuel assemblies may be 5.45% and/or 5.95%.
7. The pressurized water reactor core refueling long-cycle fuel management method as claimed in claim 1, wherein each of said new fuel assemblies is arranged in a 17 x 17 array with 264 fuel rods, 24 guide tubes and an in-core instrumentation tube;
the number of gadolinium-carrying fuel rods in the new fuel assembly is 4 or 8 or 12 or 16 or 20 or 24.
8. The PWR core refueling long-term fuel management method of claim 1, wherein the UO in the new fuel assembly2-Gd2O3The enrichment degree of U-235 in the fuel pellet is 2.5 percent, and Gd2O3Is 10% by weight.
9. The use of the method of claim 1 for long-term refueling pressurized water reactor core fuel management, wherein the method is used for long-term fuel management design of pressurized water reactors of various mainstream reactor types.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111583867.0A CN114267464A (en) | 2021-12-22 | 2021-12-22 | Pressurized water reactor core refueling long-period fuel management method and application |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111583867.0A CN114267464A (en) | 2021-12-22 | 2021-12-22 | Pressurized water reactor core refueling long-period fuel management method and application |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN114267464A true CN114267464A (en) | 2022-04-01 |
Family
ID=80829706
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202111583867.0A Pending CN114267464A (en) | 2021-12-22 | 2021-12-22 | Pressurized water reactor core refueling long-period fuel management method and application |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN114267464A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115274163A (en) * | 2022-08-05 | 2022-11-01 | 中国核动力研究设计院 | Method for managing fuel assemblies of reactor core of pressurized water reactor nuclear power plant |
| CN115376712A (en) * | 2022-08-03 | 2022-11-22 | 上海核工程研究设计院有限公司 | Fuel management method and reactor core of long-period balanced cycle of passive nuclear power plant |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107093478A (en) * | 2017-03-30 | 2017-08-25 | 中国核电工程有限公司 | A kind of pressurized water reactor core balanced recycle material-changing method of 24 months |
-
2021
- 2021-12-22 CN CN202111583867.0A patent/CN114267464A/en active Pending
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107093478A (en) * | 2017-03-30 | 2017-08-25 | 中国核电工程有限公司 | A kind of pressurized water reactor core balanced recycle material-changing method of 24 months |
Non-Patent Citations (2)
| Title |
|---|
| LUIS GARCIA-DELGADO ET AL.: ""An economically optimum PWR reload core for a 36-month cycle"", 《ANNALS OF NUCLEAR ENERGY》, 30 September 1999 (1999-09-30), pages 659 - 677 * |
| 位金锋;许星星;付学峰;蔡德昌;: "177堆芯24个月换料可行性研究", 强激光与粒子束, no. 01 * |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115376712A (en) * | 2022-08-03 | 2022-11-22 | 上海核工程研究设计院有限公司 | Fuel management method and reactor core of long-period balanced cycle of passive nuclear power plant |
| CN115274163A (en) * | 2022-08-05 | 2022-11-01 | 中国核动力研究设计院 | Method for managing fuel assemblies of reactor core of pressurized water reactor nuclear power plant |
| CN115274163B (en) * | 2022-08-05 | 2024-02-13 | 中国核动力研究设计院 | Fuel assembly management method for reactor core of pressurized water reactor nuclear power plant |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US7961836B2 (en) | Use of boron or enriched boron 10 in UO2 | |
| CN114267464A (en) | Pressurized water reactor core refueling long-period fuel management method and application | |
| JP2004507711A (en) | Improved nuclear fuel assemblies | |
| CN109036603B (en) | Long-circulation refueling and loading method for reactor core of ultra-large pressurized water reactor | |
| CN105139900B (en) | A kind of 24 months reload core stowages of employing erbium burnable poison | |
| US11056246B2 (en) | Heterogeneous core designs and thorium based fuels for heavy water reactors | |
| US20180240557A1 (en) | Nuclear fuel bundle containing thorium and nuclear reactor comprising same | |
| CN112420223A (en) | Long-circulation refueling loading method for pressurized water reactor core based on gadolinium enrichment | |
| CN107863165B (en) | Method for loading 18-month refueling multi-cycle fuel of pressurized water reactor core | |
| CN103366836B (en) | Fuel ball, method for making and nuclear reactor | |
| CN110867261B (en) | Multi-type pellet mixed loading metal cooling reactor and management method | |
| US20090268861A1 (en) | Plutonium/Zirconium Hydride/Thorium Fuel Matrix | |
| CN114242283A (en) | Fuel loading method for 24-month refueling period of pressurized water reactor core | |
| JP2018510361A (en) | Nuclear fuel containing neutron absorber mixture | |
| CN112259269A (en) | Loading method for 18-month cycle length of reactor core of million-kilowatt pressurized water reactor nuclear power plant | |
| Lapanporo et al. | Parametric Study of Thorium Fuel Utilization on Small Modular Pressurized Water Reactors (PWR) | |
| CN107910078B (en) | Management method for 18-month refueling multi-cycle fuel of pressurized water reactor core | |
| Trianti et al. | Design study of thorium cycle based long life modular boiling water reactors | |
| Fox et al. | Reactivity-initiated accidents in two pressurized water reactor high burnup core designs | |
| US20070064862A1 (en) | Pressurized water nuclear reactor fuel assembly including rods having two different contents of gadolinium | |
| Cudrnak et al. | Optimization of fuel assembly with gadolinium for LWRS | |
| Gagarinskiy | Development of fuel cycles with new fuel with 8.9 mm external diameter for VVER-440: Preliminary assessment of operating efficiency | |
| Petrovic et al. | Fuel management approach in IRIS reactor | |
| CN115547519A (en) | Reactor core of lead-bismuth cooling reactor adopting spontaneous moderated fuel | |
| Aoyama et al. | Study of advanced LWR cores for effective use of plutonium |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination |