CN112366010A - First circulation loading method for applying FCM fuel to million kilowatt pressurized water reactor - Google Patents
First circulation loading method for applying FCM fuel to million kilowatt pressurized water reactor Download PDFInfo
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- CN112366010A CN112366010A CN202011247341.0A CN202011247341A CN112366010A CN 112366010 A CN112366010 A CN 112366010A CN 202011247341 A CN202011247341 A CN 202011247341A CN 112366010 A CN112366010 A CN 112366010A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/12—Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The invention discloses a first circulation loading method for applying FCM fuel to a million kilowatt pressurized water reactor, which comprises a first circulation reactor core consisting of 157 FCM fuel assemblies235The difference of the U initial enrichment degrees is divided into three regions and loading is carried out by adopting a high-leakage loading mode, wherein the number of fuel assemblies with the initial enrichment degrees of 6.90%, 8.20% and 8.90% is respectively 53, 52 and 52, the fuel assemblies with the highest enrichment degree of 8.90% are loaded on the outermost circle of a reactor core, the fuel assemblies with the enrichment degrees of 6.90% and 8.20% are arranged in a cross-checkerboard type mode in the reactor core, and each fuel assembly of 157 FCM fuel assemblies is respectively provided with 4, 8, 12 or 16 gadolinium-loaded fuel rods. The reactor core first circulation loading method of the invention is realized by pressing the first circulation reactor core fuel235The U enrichment three-division mode is adopted for loading in a high-leakage loading mode, so that the power distribution of the reactor core can be effectively flattened, and the first-cycle reactor core can reach the aim ofThe burnup depth and the cycle length which are relatively close to the reference reactor core meet the economical efficiency of a power plant.
Description
Technical Field
The invention relates to a nuclear reactor core technology, in particular to a first cycle loading method of applying FCM fuel to a million kilowatt pressurized water reactor.
Background
In the nuclear energy development process, the performance of the fuel assembly is always an important basis for the advancement and safety of the reactor, a novel fuel assembly is developed, a novel material is adopted, the melting point of a reactor core is improved, the fuel consumption is increased, the safety coefficient of the reactor core is improved, and the method is a key direction for the research of various nuclear power strong countries in the world. The current commercial pressurized water reactor adopts a technically mature UO2Zirconium alloy fuel, however, in the event of a loss of cooling, the zirconium alloy cladding will undergo a high temperature chemical reaction with water vapour to initiate hydrogen explosions, causing radioactive hazards, and hence the UO2The zirconium alloy fuel form is insufficient in resistance to serious accidents, and thus, higher requirements are placed on safety, reliability and economy of the new generation nuclear power plants and nuclear fuels.
The full Ceramic micro encapsulated Fuel (FCM Fuel) is one of the research directions of accident-resistant Fuel, is an advanced Fuel which disperses TRISO Fuel particles in a SiC matrix, and has good capacity of containing fission products due to the design of a multilayer coating. In addition, the SiC matrix can be used as a protective barrier of TRISO fuel particles, so that the FCM fuel has the advantages of good irradiation stability, excellent thermal conductivity, good thermal shock stability under normal operation conditions, low corrosion rate, low high-temperature oxidation rate and the like, and the performance of the FCM fuel in the aspect of accident resistance is greatly improved.
However, compared with the conventional UO2Compared with ceramic fuel pellets, the fuel loading of the FCM fuel pellets is small, and the direct application of the FCM fuel to a commercial pressurized water reactor can affect the power and the service life of a reactor core and reduce the overall physical performance index of the reactor core; in addition, the FCM fuel adopts SiC as a matrix, has better moderating capability, and can cause the temperature coefficient of a moderator to be positive during the life period of a reactor core, so that the intrinsic safety requirement of the reactor core cannot be met.
Disclosure of Invention
The invention aims to solve the problems in the prior art and provides a first-cycle loading method for applying FCM fuel to a million-kilowatt pressurized water reactor, which is implemented by mixing the first-cycle reactor core fuel235The U enrichment degree is divided into three areas and loaded in a high-leakage loading mode, wherein the highest enrichment degree assembly is placed at the outermost circle of the reactor core, gadolinium-loaded fuel rods are added into the fuel assemblies and serve as burnable poison, the power distribution of the reactor core can be effectively flattened, the first-cycle reactor core can reach the burnup depth and the cycle length which are close to those of the reference reactor core, and the economy of a power plant is met.
The invention is realized by the following technical scheme:
a first-cycle loading method for applying FCM fuel to a million-kilowatt pressurized water reactor comprises a first-cycle reactor core consisting of 157 FCM fuel assemblies235The difference of the U initial enrichment degrees is divided into three regions and loading is carried out by adopting a high-leakage loading mode, wherein the number of fuel assemblies with the initial enrichment degrees of 6.90%, 8.20% and 8.90% is respectively 53, 52 and 52, the fuel assemblies with the highest enrichment degree of 8.90% are loaded on the outermost circle of a reactor core, the fuel assemblies with the enrichment degrees of 6.90% and 8.20% are arranged in a cross-checkerboard type mode in the reactor core, and each fuel assembly of 157 FCM fuel assemblies is respectively provided with 4, 8, 12 or 16 gadolinium-loaded fuel rods.
The gadolinium-loaded fuel rod adopts UO2-Gd2O3The gadolinium-loaded fuel is formed in a form of being uniformly mixed in pelletsA rod.
Fuel pellet235The enrichment degree of U is 2.5 percent and Gd2O3The weight percentage of (B) is 8.0%.
Due to the special form of FCM fuel, it has a higher fuel charge than UO2Less pellet fuel assembly compared to UO2In order to meet the required core power and life of the core, the FCM fuel (UN core) assembly with the above-mentioned TRISO particle parameters needs to have a high initial value235U-enrichment, which makes the initial reactivity of the FCM fuel assembly large. The first circulation reactor core loading method adopts three different types235The fuel rods with the U initial enrichment degree are loaded in a high-leakage loading mode, so that the power distribution of the reactor core can be effectively flattened; and to compensate for the excess reactivity of the core at the beginning of its life when the FCM fuel assemblies are loaded and to flatten the radial power distribution of the core, the first cycle core employs UO2With Gd2O3The evenly dispersed gadolinium-loaded fuel rods are used as burnable poison materials, and fuel assemblies respectively containing 4, 8, 12 and 16 gadolinium-loaded fuel rods are reasonably arranged in the reactor core according to the loading requirement of the reactor core, so that the purpose of flattening the power distribution of the reactor core is further achieved.
The FCM fuel assembly takes the form of a 13 x 13 grid with 17 guide tubes and is arranged symmetrically within the assembly, satisfying 1/8 or 1/4 symmetry.
The FCM fuel assembly combustion pellet adopts TRISO particles, the core of the TRISO particles adopts high-uranium density fuel UN, the diameter of the core is 800 mu m, the volume fraction of fuel balls is 50%, and the cladding material is SiC.
The radius of the loose PyC layer of the TRISO particles is 450 mu m, the radius of the IPyC layer is 485 mu m, the radius of the SiC layer is 520 mu m, and the radius of the OPyC layer is 540 mu m.
The pitch in the FCM fuel assembly was 1.260cm, the fuel segment height was 365.8cm, and the fuel pellet diameter was 1.154 cm.
The arrangement of the guide pipe and the control rod group can ensure that the shutdown allowance of the reactor core meets the requirement of safety criteria, and for the FCM fuel assembly of the fuel rod carrying the gadolinium burnable poison, the under-moderation requirement of the fuel assembly is realized, and the inherent safety of the assembly is ensured.
In the FCM fuel assembly with the enrichment degree of 8.90%, 4 gadolinium-carrying fuel rods are arranged in the fuel assembly positioned at the outermost ring edge of the reactor core, 16 gadolinium-carrying fuel rods are arranged in the fuel assembly with the enrichment degree of 8.20% on a cross line in the reactor core, and 8 gadolinium-carrying fuel rods and 12 gadolinium-carrying fuel rods are arranged in the rest fuel assemblies in a cross mode.
8 gadolinium-loaded fuel rods are all arranged in the fuel assembly with the enrichment degree of 6.90%.
The remaining fuel assemblies with an enrichment of 8.20% had 12 gadolinium-loaded fuel rods arranged therein.
Through the placing mode of rationally arranging the burnable poison fuel rod in the reactor core, the requirement of flattening reactor core power distribution and realizing reactivity control can be effectively realized.
The invention has the following beneficial effects:
1. the invention relates to a first-cycle loading method for applying FCM fuel to a million-kilowatt pressurized water reactor, which is characterized in that the first-cycle reactor core fuel is loaded according to the weight235The U enrichment three-division area is loaded in a high-leakage loading mode, wherein the highest enrichment assembly is placed at the outermost circle of the reactor core, and gadolinium-loaded fuel rods are added into the fuel assemblies to serve as burnable poisons, so that the power distribution of the reactor core can be effectively flattened;
2. the invention relates to a first circulation loading method of applying FCM fuel to a million kilowatt pressurized water reactor, which is characterized in that the arrangement of a guide pipe and a control rod group realizes the demand of under-moderation of a fuel assembly and ensures the inherent safety of the assembly;
3. the first-cycle loading method of applying the FCM fuel to the million-kilowatt pressurized water reactor realizes the safety requirement that the temperature coefficient of the reactor core moderator is negative, and the first-cycle reactor core reaches the burnup depth and the cycle length which are closer to those of the reference reactor core, thereby ensuring the safety of a power plant and meeting the economic requirement of the power plant.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a schematic view of one form of a 13X 13 grid form FCM fuel assembly of the present invention;
FIG. 2 is a schematic view of one arrangement of control bundles in a 13X 13 grid-type FCM fuel assembly of the present invention.
FIG. 3 is a schematic view of an arrangement of gadolinium-loaded fuel rods in a 13X 13 lattice form FCM fuel assembly of the present invention;
FIG. 4 is a schematic illustration of the loading of the first cycle of the FCM core of the present invention.
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 accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Example 1
As shown in figure 1, the FCM fuel assembly of the first-cycle core of the invention adopts a mode of embedding TRISO fuel particles into a SiC matrix, wherein the core of the TRISO particles adopts high-uranium-density fuel UN, the parameters of the TRISO particles of the UN core are shown in a table 1, the volume fraction of fuel spheres is 50%, and the cladding material is SiC.
TABLE 1 structural size, Density and composition of TRISO particles from inside to outside
| Structural parameters | Size (mum) | Density (g/cm)3) | Composition (I) |
| Core diameter of UN | 800 | 14.316 (95% porosity) | U, N atomic ratio 1:1 |
| Radius of loose PyC layer | 450 | 1.1 | C |
| Radius of IPyC layer | 485 | 1.9 | C |
| Radius of SiC layer | 520 | 3.18 | The atomic ratio of Si to C is 1:1 |
| Radius of OPyC layer | 540 | 1.9 | C |
| Total diameter | 1080 | — | — |
Example 2
Based on example 1, the UO of the invention in the form of a standard AFA3G 17X 17 grid2-a Zr alloy fuel assembly as a reference object, and the arrangement of the guide tubes in the FCM fuel assembly in a 13 × 13 grid form is designed to satisfy the following conditions:
1) the guide tubes are symmetrically arranged in the assembly, and the 1/8 or 1/4 symmetry is met;
2) the guide tube is considered to be positioned appropriately close to the center of the assembly to ensure that the assembly has a low power crest factor.
The FCM fuel assembly in the 13 x 13 grid format has 17 guide tubes in the assembly as shown in fig. 1, and the control bundles in the assembly as shown in fig. 2, while meeting the design criteria for the guide tube placement within the assembly and maintaining control rod worth comparable to the reference assembly, as described in detail below:
coordinate positions of 12 gray rods in the gray control rod group are (05, 03), (09, 03), (03, 05), (05, 05), (09, 05), (11, 05), (03, 09), (05, 09), (09, 09), (11, 09), (05, 11), (09, 11), and coordinate positions of 4 black rods are (07, 05), (05, 07), (09, 07), (07, 09);
the coordinate positions of the 16 black rods in the black control rod group are (05, 03), (09, 03), (03, 05), (05, 05), (09, 05), (11, 05), (03, 09), (05, 09), (09, 09), (11, 09), (05, 11), (09, 11), (07, 05), (05, 07), (09, 07), (07, 09).
The component parameters of the FCM fuel assembly are shown in table 2.
Table 213 x 13 FCM Fuel component parameters in grid form (Cold)
| |
13×13 |
| Center distance, cm, of fuel assembly | 21.504 |
| Grid pitch, cm | 1.260 |
| Fuel section height, cm, of fuel assembly | 365.8 |
| Diameter of fuel pellet, cm | 1.154 |
| Outer cladding diameter, cm, of fuel pellets | 1.360 |
| Cladding thickness of fuel pellets, cm | 0.100 |
| Outside diameter, cm, of the guide tube | 1.603 |
| Thickness of guide tube, cm | 0.062 |
| Radius of absorber (cold state), cm | 0.654 |
| Inner diameter (cold state) of the cladding in cm | 1.308 |
| Outer diameter (cold state) of the cladding in cm | 1.410 |
| Density of fuel pellets, g/cm3 | 14.316 |
Example 3
The method for loading the first circulation reactor core of the pressurized water reactor adopts 157 example 2The 13 x 13 grid pattern of FCM fuel assemblies described in (1) constitutes the primary cycle core, and 157 FCM fuel assemblies have three different types235U initial enrichment, where the number of fuel assemblies at 6.90%, 8.20% and 8.90% enrichment was 53, 52 and 52, respectively. As shown in fig. 4, fuel assemblies with the highest enrichment of 8.90% are loaded on the outermost ring of the reactor core, fuel assemblies with the enrichments of 6.90% and 8.20% are arranged in a cross-checkerboard type arrangement in the reactor core, wherein 4, 8, 12 or 16 gadolinium-carrying fuel rods are respectively arranged in the fuel assemblies, 4 gadolinium-carrying fuel rods are arranged in the fuel assemblies at the edge of the outermost ring of the reactor core, 16 gadolinium-carrying fuel rods are arranged in the fuel assemblies with the enrichment of 8.20% on a cross line in the reactor core, 8 or 12 gadolinium-carrying fuel rods in the remaining fuel assemblies are arranged in a cross-checkerboard type arrangement, and 8 gadolinium-carrying fuel rods are all arranged in the fuel assemblies with the enrichment of 6.90%.
The invention adopts the high leakage loading mode to have different pairs235The FCM fuel assemblies with the U enrichment degree are loaded in a partitioned mode, meanwhile, the number of gadolinium-loaded fuel rods in the FCM fuel assemblies at different positions in the reactor core is reasonably arranged, and the power distribution of the reactor core is effectively flattened.
The arrangement of 4, 8, 12 and 16 gadolinium-loaded fuel rods in a 13 x 13 lattice form FCM fuel assembly is shown in fig. 3 and is described in detail below:
the coordinate positions of 4 gadolinium-loaded fuel rods in the FCM fuel assembly containing 4 gadolinium-loaded fuel rods are (03, 03), (11, 03), (03, 11) and (11, 11);
the coordinate positions of 8 gadolinium-loaded fuel rods in the FCM fuel assembly containing 8 gadolinium-loaded fuel rods are (06, 04), (08, 04), (04, 06), (10, 06), (04, 08), (10, 08), (06, 10), (08, 10);
the coordinate positions of 12 gadolinium-loaded fuel rods in the FCM fuel assembly containing 12 gadolinium-loaded fuel rods are (03, 03), (11, 03), (03, 11), (11, 11), (06, 04), (08, 04), (04, 06), (10, 06), (04, 08), (10, 08), (06, 10), (08, 10);
the coordinate positions of 16 gadolinium-loaded fuel rods in an FCM fuel assembly containing 16 gadolinium-loaded fuel rods are (03, 03), (11, 03), (03, 11), (11, 11), (06, 04), (08, 04), (04, 06), (10, 06), (04, 08), (10, 08), (06, 10), (08, 10), (06, 06), (08, 06), (06, 08), (08, 08).
The loaded first-cycle reactor core of the embodiment can meet the requirement of safety criteria, the Mode-G Mode operation is adopted, the thermal power of the reactor is 2895MW, and the main calculation results are shown in Table 3.
TABLE 3 FCM core first cycle calculation results
| Calculating parameters | Calculation results |
| Cycle length (EFPD) | 293 |
| Maximum module burn-up in cycle (MWd/tU) | 45508 |
| Boron concentration (ppm) (BOL, HFP, ARO) | 1048 |
| Moderator temperature coefficient (BOL, HZP, ARO, pcm/. degree.C.) | -0.088 |
| Core trip margin (EOL, pcm) | 4180 |
As can be seen from Table 3, when the core of the present invention is used in a commercial pressurized water reactor power plant, both the burnup depth and the cycle length can be achieved and referencedCore (UO in AFA3G 17 × 17 grid form2The reactor core composed of Zr alloy fuel assemblies) is relatively close, the safety requirement that the temperature coefficient of the reactor core moderator is negative is realized, the safety requirement of a power plant is ensured, and the economic requirement of the power plant is met.
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 (10)
1. The first circulation loading method of applying FCM fuel to million kilowatt pressurized water reactors comprises a first circulation reactor core consisting of 157 FCM fuel assemblies, and is characterized in that the fuel assemblies of the first circulation reactor core are arranged according to the weight235The difference of the U initial enrichment degrees is divided into three regions and loading is carried out by adopting a high-leakage loading mode, wherein the number of fuel assemblies with the initial enrichment degrees of 6.90%, 8.20% and 8.90% is respectively 53, 52 and 52, the fuel assemblies with the highest enrichment degree of 8.90% are loaded on the outermost circle of a reactor core, the fuel assemblies with the enrichment degrees of 6.90% and 8.20% are arranged in a cross-checkerboard type mode in the reactor core, and each fuel assembly of 157 FCM fuel assemblies is respectively provided with 4, 8, 12 or 16 gadolinium-loaded fuel rods.
2. The method of claim 1, wherein the FCM fuel assembly is in the form of a 13 x 13 grid, and the number of the guide tubes is 17 and the guide tubes are symmetrically arranged in the assembly, so as to satisfy the one-eighth symmetrical arrangement or the one-quarter rotational symmetrical arrangement.
3. The method of claim 1, wherein the FCM fuel assembly with the enrichment degree of 8.90% is provided with 4 gadolinium-carrying fuel rods in the fuel assembly at the outermost periphery of the core, 16 gadolinium-carrying fuel rods are arranged in the fuel assembly with the enrichment degree of 8.20% on a crisscross line in the core, and the rest fuel assemblies are provided with 8 and 12 gadolinium-carrying fuel rods in a crisscross manner.
4. The method of claim 3, wherein the fuel assemblies with 6.90% enrichment are all provided with 8 gadolinium-loaded fuel rods.
5. The method of claim 3, wherein 12 gadolinium-loaded fuel rods are arranged in the fuel assembly with the remaining enrichment of 8.20%.
6. The method of claim 1, wherein the first cycle loading of the fuel FCM in a million kilowatt pressurized water reactor is carried out by using UO as gadolinium-carrying fuel rod2-Gd2O3The gadolinium-loaded fuel rod is formed in a form of being uniformly mixed in the pellets.
7. The method for loading a million kilowatt pressurized water reactor with FCM fuel as claimed in claim 6, wherein the fuel pellets are loaded in the first cycle235The enrichment degree of U is 2.5 percent and Gd2O3The weight percentage of (B) is 8.0%.
8. The method for loading the FCM fuel in the first cycle of a million kilowatt pressurized water reactor according to claim 1, wherein the FCM fuel assembly combustion pellets are TRISO particles, the cores of the TRISO particles are high-uranium-density fuel UN, the diameter of the cores is 800 microns, the volume fraction of fuel balls is 50%, and the cladding material is SiC.
9. The method of claim 8, wherein the radius of the loose PyC layer of the TRISO particles is 450 μm, the radius of the IPyC layer is 485 μm, the radius of the SiC layer is 520 μm, and the radius of the OPyC layer is 540 μm.
10. The method of claim 2, wherein the FCM fuel assembly has a grid pitch of 1.260cm, a fuel segment height of 365.8cm, and a fuel pellet diameter of 1.154 cm.
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114420315A (en) * | 2021-11-18 | 2022-04-29 | 中国核动力研究设计院 | Method for obtaining safety margin |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105139899A (en) * | 2015-07-09 | 2015-12-09 | 中国核动力研究设计院 | Core loading method of pressurized water reactor nuclear power plant first cycle |
| CN107910078A (en) * | 2017-12-08 | 2018-04-13 | 中国核动力研究设计院 | 18 months of a kind of pressurized water reactor core are reloaded the management method of multi-cycle fuel |
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2020
- 2020-11-10 CN CN202011247341.0A patent/CN112366010A/en not_active Withdrawn
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105139899A (en) * | 2015-07-09 | 2015-12-09 | 中国核动力研究设计院 | Core loading method of pressurized water reactor nuclear power plant first cycle |
| CN107910078A (en) * | 2017-12-08 | 2018-04-13 | 中国核动力研究设计院 | 18 months of a kind of pressurized water reactor core are reloaded the management method of multi-cycle fuel |
Non-Patent Citations (1)
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| 秦雪等: "基于FCM燃料的商业压水堆中子学分析", 《核技术》 * |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN114420315A (en) * | 2021-11-18 | 2022-04-29 | 中国核动力研究设计院 | Method for obtaining safety margin |
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