CN115171922B - Loading method for loading low-burnup fuel assemblies into pressurized water reactor initial reactor core - Google Patents
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- CN115171922B CN115171922B CN202210874038.6A CN202210874038A CN115171922B CN 115171922 B CN115171922 B CN 115171922B CN 202210874038 A CN202210874038 A CN 202210874038A CN 115171922 B CN115171922 B CN 115171922B
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- 239000000446 fuel Substances 0.000 title claims abstract description 156
- 238000011068 loading method Methods 0.000 title claims abstract description 54
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 23
- 230000000712 assembly Effects 0.000 title claims description 69
- 238000000429 assembly Methods 0.000 title claims description 69
- 125000004122 cyclic group Chemical group 0.000 claims abstract description 8
- 239000002915 spent fuel radioactive waste Substances 0.000 claims abstract description 8
- 238000000034 method Methods 0.000 claims abstract description 4
- 229910052688 Gadolinium Inorganic materials 0.000 claims description 23
- UIWYJDYFSGRHKR-UHFFFAOYSA-N gadolinium atom Chemical compound [Gd] UIWYJDYFSGRHKR-UHFFFAOYSA-N 0.000 claims description 23
- 239000002574 poison Substances 0.000 claims description 17
- 231100000614 poison Toxicity 0.000 claims description 17
- 230000007704 transition Effects 0.000 claims description 17
- 239000008188 pellet Substances 0.000 claims description 11
- 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 9
- 239000007787 solid Substances 0.000 claims description 9
- 239000002699 waste material Substances 0.000 abstract description 5
- 230000009286 beneficial effect Effects 0.000 description 3
- 230000007613 environmental effect Effects 0.000 description 3
- 230000004992 fission Effects 0.000 description 3
- 230000002269 spontaneous effect Effects 0.000 description 3
- 238000011156 evaluation Methods 0.000 description 2
- 230000001186 cumulative effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000007599 discharging 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
- 230000009257 reactivity Effects 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
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
- G21C3/30—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
- G21C3/3262—Enrichment distribution in zones
-
- 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
- G21C3/334—Assembling, maintenance or repair of the bundles
-
- 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
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Dispersion Chemistry (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention relates to the technical field of pressurized water reactor core fuel, in particular to a loading method for loading a low-burnup fuel assembly into an initial reactor core of a pressurized water reactor, which adopts the following technical scheme: the method comprises a first cyclic loading step, wherein the first cyclic loading step comprises the following steps: simultaneously loading a new fuel assembly and a low-fuel-consumption fuel assembly, wherein the low-fuel-consumption fuel assembly is spent fuel; wherein the low burnup fuel assembly is used to increase the source strength of the neutron source of the core in the subcritical state. According to the invention, the new fuel component and the low-burnup fuel component are simultaneously filled, the low-burnup fuel component is spent fuel, so that the purchase of the new fuel component can be reduced, the low-burnup fuel has higher neutron intensity, the source intensity of a neutron source of a reactor core in a subcritical state can be increased through the low-burnup fuel component, the use of the new component is reduced in a first cycle, the neutron source is canceled, the cost can be saved, the generation of high-radioactivity waste can be reduced, and the environment protection is facilitated.
Description
Technical Field
The invention relates to the technical field of pressurized water reactor core fuels, in particular to a loading method for loading a low-burnup fuel assembly into an initial reactor core of a pressurized water reactor.
Background
Pressurized water reactor core fuel management, generally refers to determining the degree of fuel enrichment used by the core, the type of burnable poison, the arrangement of various components and poisons within the core, etc., from the first cycle to the equilibrium cycle core (typically the core goes through 5 or 6 fuel cycles to reach equilibrium), so that the design results of the reactor core meet the nuclear design criteria and overall power plant requirements. The advantages and disadvantages of the core fuel management directly affect the economy and the safety of the nuclear power plant, and are the basis for subsequent safety analysis or evaluation.
The first cycle of the nuclear power plant generally uses new fuel assemblies entirely, and the reactor core power is flattened through the cross placement of fuel assemblies with different enrichment degrees; at the same time, the number of neutrons generated by spontaneous fission of the new fuel assembly is limited and insufficient to provide a neutron count meeting regulatory requirements for startup to reach a threshold. During startup, the source intensity of the reactor core in the subcritical state needs to be increased through a primary neutron source, so that the reactor core reaches the initial critical state under the condition of being capable of being monitored. Thus, the first cycle of a conventional pressurized water reactor nuclear power plant requires the procurement of new fuel assemblies and additional neutron sources for the full core, which is costly.
Disclosure of Invention
Aiming at the technical problems that the prior pressurized water reactor nuclear power plant uses new fuel assemblies and needs to use a neutron source once in the first cycle, the invention provides a loading method for loading the low-burnup fuel assemblies in the initial reactor core of the pressurized water reactor, and the low-burnup fuel assemblies are used as the neutron source in the first cycle, so that the use amount of the new fuel assemblies is reduced, the cost is saved, the generation of high-radioactivity wastes can be reduced, and the environment protection is facilitated.
The invention is realized by the following technical scheme:
The loading method for loading the low-burnup fuel assemblies in the initial reactor core of the pressurized water reactor comprises a first cyclic loading step, wherein the first cyclic loading step comprises the following steps:
Simultaneously loading a new fuel assembly and a low-fuel-consumption fuel assembly, wherein the low-fuel-consumption fuel assembly is a spent fuel assembly;
Wherein the low burnup fuel assembly is used to increase the source strength of the neutron source of the core in the subcritical state.
In the prior art, the first cycle of the nuclear power plant uses all new fuel assemblies, and the reactor core power is flattened through the placement of fuel assemblies with different enrichment degrees; the number of neutrons generated by spontaneous fission of the new fuel assembly is limited, and is insufficient to provide neutron counts meeting the supervision requirements for starting up, so that the source intensity of the reactor core in the subcritical state needs to be increased by a primary neutron source during starting up, and the reactor core reaches the initial critical under the condition of being capable of being monitored.
In the invention, in the first cycle, the new fuel component and the low-burnup fuel component are simultaneously loaded, wherein the low-burnup fuel component is spent fuel, so that purchase of the new fuel component can be reduced, the low-burnup fuel has higher neutron intensity, and the source intensity of a neutron source of the reactor core in a subcritical state can be increased through the low-burnup fuel component, so that the reactor core can be normally started without adopting the neutron source additionally.
In summary, compared with the prior art, the loading method for loading the low-fuel-consumption fuel assemblies in the pressurized water reactor initial reactor core can reduce the consumption of the first-cycle new fuel assemblies, does not need to additionally arrange a neutron source, can save cost, can reduce the generation of high-radioactivity wastes, and is beneficial to environmental protection.
In an alternative embodiment, the new fuel assembly is loaded in three zones.
In an alternative embodiment, the U-235 enrichment of the new fuel assembly is 1.8%, 2.4% and 3.1%, respectively.
In an alternative embodiment, the first cycle core adopts a burnable poison as an integrated gadolinium solid burnable poison, wherein gadolinium in the integrated gadolinium solid burnable poison exists in the form of UO2-Gd2O3, and the integrated gadolinium solid burnable poison are uniformly mixed together to form gadolinium-carrying fuel pellets, and the gadolinium-carrying fuel pellets form independent gadolinium-carrying fuel rods.
In an alternative embodiment, the gadolinium-loaded fuel pellet has a mass percent of Gd2O3 of 8%.
In an alternative embodiment, the burnable poison is disposed in the new fuel assembly at an enrichment of 2.4%, 3.1% in the first cycle.
In an alternative embodiment, the number of gadolinium-loaded fuel rods in each set of new fuel assemblies is one of 4, 8, 12 or 16.
In an alternative embodiment, the first cycle is loaded in a partial low leakage mode, the transition and balancing cycles are loaded in an extremely low leakage mode, and each refueling of the transition and balancing cycles is loaded with 72 sets of new fuel assemblies;
Wherein:
The partial low leakage mode is that a low-burnup fuel assembly and a new fuel assembly are simultaneously arranged on the outermost ring of the reactor core;
The extremely low leakage mode is that new fuel assemblies are all arranged on the inner ring of the reactor core and are arranged at intervals in a crossing way with the burnt assemblies, and the outermost ring of the reactor core is arranged by all the burnt assemblies with deeper burning;
the cycle length of the transition cycle and the balance cycle reactor core reaches the design requirement of 18 month long cycle refueling.
In an alternative embodiment, the fresh fuel charge for the transition and balance cycles is enriched by 4.45% and/or 4.95%.
In an alternative embodiment, the enrichment of U235 in gadolinium-loaded fuel pellets in the first, transition and equilibrium cycles is lower than the enrichment of U235 in the assembly.
The invention has the following advantages and beneficial effects:
1. according to the loading method for loading the low-burnup fuel assemblies in the pressurized water reactor initial reactor core, the new fuel assemblies and the low-burnup fuel assemblies are simultaneously loaded in the first cycle, the low-burnup fuel assemblies are spent fuel, so that purchase of the new fuel assemblies can be reduced, the low-burnup fuel has higher neutron intensity, the source intensity of a neutron source of the reactor core in a subcritical state can be increased through the low-burnup fuel assemblies, the use of the new assemblies in the first cycle is reduced, the primary neutron source is eliminated, the cost can be saved, the generation of high-radioactivity waste can be reduced, and the environmental protection is facilitated.
2. According to the loading method for loading the low-fuel-consumption fuel assemblies in the pressurized water reactor initial reactor core, the new fuel assemblies are loaded in the same mode as the balance cycle in the transition cycle, and the transition from the first cycle to the balance cycle can be fast carried out.
3. According to the loading method for loading the low-fuel-consumption fuel assemblies in the pressurized water reactor initial reactor core, which is provided by the invention, the transition cycle and the balance cycle are loaded in the extremely low leakage mode, so that the design requirement of a 18-month refueling period can be met.
Drawings
The accompanying drawings, which are included to provide a further understanding of embodiments of the application and are incorporated in and constitute a part of this specification, illustrate embodiments of the application and together with the description serve to explain the principles of the application.
In the drawings:
FIG. 1 is a loading schematic of a first cycle core of the present invention;
FIG. 2 is a loading schematic of a second circulating core of the present invention;
FIG. 3 is a loading schematic of a third circulating core of the present invention;
FIG. 4 is a loading schematic of a fourth cycle and balance cycle core of the present invention.
Wherein:
The blank boxes in FIG. 1 represent 1.8% enrichment new assemblies, with the colored boxes extending from light to dark in color for 2.4% enrichment new assemblies, 3.1% enrichment new assemblies, low burn fuel assemblies;
the numbers in the graph of fig. 4 refer to the number of gadolinium-loaded fuel rods in the new fuel assemblies, with the underlined representing 4.95% enrichment assemblies and the remaining 4.45% enrichment assemblies, the light shading being the reusable fuel assembly burned for one cycle, and the dark shading being the reusable fuel assembly burned for two cycles.
In the drawing, the abscissa is arranged from a to R in order from right to left, and the ordinate is arranged from 1 to 15 in order from top to bottom.
Detailed Description
For the purpose of making apparent the objects, technical solutions and advantages of the present invention, the present invention will be further described in detail with reference to the following examples and the accompanying drawings, wherein the exemplary embodiments of the present invention and the descriptions thereof are for illustrating the present invention only and are not to be construed as limiting the present invention.
It should be appreciated that existing pressurized water reactor nuclear power plants are more in core specification, and in this embodiment are directed to a million kilowatt level nuclear power plant reactor core that is comprised of 177 groups of AFA3G fuel assemblies.
And the fuel management of a complete nuclear power plant core should be based on established objectives and given core parameter constraints or guidelines to overall determine the core loading pattern for a series of core fuel cycles from the first cycle to the balance cycle and to perform the relevant neutron physics calculations.
Example 1
With reference to fig. 1, this embodiment provides a loading method for loading a low-burnup fuel assembly into an initial reactor core of a pressurized water reactor, including a first cyclic loading step, where the first cyclic loading step is as follows: simultaneously loading a new fuel assembly and a low-fuel-consumption fuel assembly, wherein the low-fuel-consumption fuel assembly is a spent fuel assembly; wherein the low burnup fuel assembly is used to increase the source strength of the neutron source of the core in the subcritical state.
Specifically, in this example, the specific content covers: the method comprises the steps of selecting a low-fuel consumption fuel assembly adopted by a first cycle, determining the enrichment degree of different fuels of a new fuel assembly, determining the enrichment degree of the new fuel assembly of a subsequent cycle, selecting the type of solid burnable poison of each cycle, arranging and optimizing a reactor core fuel assembly and the solid burnable poison, and carrying out preliminary safety evaluation.
More specifically, the new fuel assemblies are loaded in three zones in the first cycle, i.e., the first cycle core loading employs 3 different U-235 enrichment fuel assemblies. The U-235 enrichment of the new fuel assemblies in this example was 1.8%, 2.4% and 3.1%, respectively, with the 1.8%, 2.4% and 3.1% enrichment of the fuel assemblies in the order 16, 40 and 80 groups, with 41 groups of low burn fuel assemblies being charged.
Due to the low burnup fuel assembly, the first cycle is not entirely new fuel assembly, and a partial low leak loading mode may be employed. While low burnup assemblies refer to assemblies that have been irradiated at the core for 1-2 cycles, the cumulative burnup is far different from the limit (e.g., 52000 MWd/tU), but the long cycle burnup is long, and the re-burnup cycle is overrun and cannot continue to be used. Typical low burnup fuel assemblies have burnup less than 40000MWd/tU, with specific burnup values determined based on the type of core loaded and the loading mode.
In order to control the residual reactivity of the initial reactor core, the first cycle adopts an integrated gadolinium burnable poison in the form of UO2-Gd2O3 which is uniformly mixed in the pellets to form gadolinium-loaded fuel rods. Gadolinium-loaded fuel rods are arranged in assemblies with enrichment of 2.4% and 3.1%, and 4 gadolinium-loaded fuel rods, 8 gadolinium-loaded fuel rods, 12 gadolinium-loaded fuel rods or 16 gadolinium-loaded fuel rods are arranged in the new fuel assemblies. And the U-235 enrichment degree in the UO2-Gd2O3 fuel pellet is respectively 1.2% and 1.8% in two enrichment degree components of 2.4% and 3.1%.
In addition, the burnable poison Gd2O3 in the present example was 8% by weight.
Wherein, the first cycle core loading can meet the safety rule requirement, and the main calculation result is shown in table 1.
TABLE 1
In the prior art, the first cycle of the nuclear power plant uses all new fuel assemblies, and the reactor core power is flattened through the placement of the fuel assemblies with different enrichment degrees; the number of neutrons generated by spontaneous fission of the new fuel assembly is limited, and is insufficient to provide neutron counts meeting the supervision requirements for starting up, so that the source intensity of the reactor core in the subcritical state needs to be increased by a primary neutron source during starting up, and the reactor core reaches the initial critical under the condition of being capable of being monitored.
In the invention, in the first cycle, the new fuel component and the low-burnup fuel component are simultaneously loaded, and the low-burnup fuel component is spent fuel, so that the purchase of the new fuel component can be reduced, and the low-burnup fuel has higher neutron intensity, and the source intensity of a neutron source of the reactor core in a subcritical state can be increased through the low-burnup fuel component, so that the reactor core can be normally started without adopting the neutron source additionally.
To sum up, the present embodiment first cycles 41 sets of low burnup fuel assemblies while eliminating the primary neutron source, i.e., burnup the low burnup fuel assemblies for multiple cycles are disposed in the first cycle core with the new fuel assemblies. Not only can save cost, but also can reduce the generation of high-radioactivity waste, and is beneficial to environmental protection.
Example 2
Referring to fig. 2,3 and 4, the present embodiment provides a loading method for loading a low-fuel-consumption fuel assembly in an initial core of a pressurized water reactor, wherein based on the steps and principles described in embodiment 1, a first cycle is loaded in a partial low-leakage mode, a transition cycle and a balance cycle are loaded in an extremely low-leakage mode, and each refueling of the transition cycle and the balance cycle is loaded with 72 sets of new fuel assemblies.
Wherein:
the partial low leakage mode is that the new fuel assembly and the low burnup assembly are alternately arranged, and a part of the low burnup fuel assembly is arranged on the outermost ring of the reactor core, namely the partial low leakage mode is that the low burnup fuel assembly and the new fuel assembly are simultaneously arranged on the outermost ring of the reactor core.
The extremely low leakage mode is that new fuel components are arranged on the inner ring of the reactor core and are alternately arranged with burnt components, and the new components with deeper burnt components are arranged on the outermost ring of the reactor core; that is, the very low leakage mode is that new fuel assemblies are all arranged on the inner ring of the reactor core and are arranged at intervals crossing the burnt assemblies, and the outermost ring of the reactor core is all the burnt assemblies with deeper burning.
Specifically, from the second cycle to the equilibrium cycle, the fuel enrichment used for the fresh feed is the same. In this example, the transition cycle (the cycle from the start of the second cycle to the preceding the balancing cycle is collectively referred to as the transition cycle) employs both 4.45% and 4.95% enrichment of the new fuel, that is, the transition cycle and balancing cycle charge of the new fuel is enriched to 4.45% and/or 4.95%. Fig. 2 to 4 show specific schematic diagrams of the core loading fuel assemblies from the second cycle to the balance cycle, namely 72 new fuel assemblies added each time are placed inside the core, the old assemblies of the excessive burnup cycles are placed on the outermost ring of the core, and the old and new assemblies of the inner ring of the core are matched and combined with each other, or the burnt assemblies are arranged in a cross manner according to different burnup depths.
From the second cycle, the solid burnable poison also used gadolinium, with a U-235 enrichment of 2.5% and a Gd2O3 weight percentage of 8% in the UO2-Gd2O3 fuel pellet. Accordingly, a typical number of gadolinium-loaded fuel rods in the new fuel assembly is 12, or 16, or 20.
In addition, the U235 enrichment in gadolinium-loaded fuel pellets in the initial, transitional and equilibrium cycles is lower than the U235 enrichment of the assembly in which it is located.
For the loading method of the pressurized water reactor initial reactor core loaded with the low-burnup fuel assemblies provided by the implementation, the main calculation results are shown in table 2:
TABLE 2
As can be seen from Table 2, by adopting the loading method for loading the low-burnup fuel assemblies in the pressurized water reactor initial reactor core, the design from the first cycle year of refueling to the balance cycle reaching 18 months of long-period refueling is adopted, wherein the cycle length of the balance cycle is 496 equivalent full power days, the reactor core power distribution is simultaneously considered, the cycle length of the subsequent cycle reactor core is increased, and the utilization rate of nuclear fuel and the running economy of a power plant are improved. The maximum nuclear enthalpy rise factor is lower than 1.63, meets the requirement of a safety limit, and the average burnup of the maximum discharging assembly is lower than 52000MWd/tU, and meets the requirement of the burnup safety limit.
The foregoing description of the embodiments has been provided for the purpose of illustrating the general principles of the invention, and is not meant to limit the scope of the invention, but to limit the invention to the particular embodiments, and any modifications, equivalents, improvements, etc. that fall within the spirit and principles of the invention are intended to be included within the scope of the invention.
Claims (3)
1. The loading method for loading the low-burnup fuel assemblies in the initial reactor core of the pressurized water reactor comprises a first cyclic loading step, and is characterized in that the first cyclic loading step comprises the following steps:
Simultaneously loading a new fuel assembly and a low-fuel-consumption fuel assembly, wherein the low-fuel-consumption fuel assembly is a spent fuel assembly;
the low-burnup fuel assembly is used for increasing the source intensity of a neutron source of the reactor core in a subcritical state, the new fuel assembly is loaded in three areas, and the U-235 enrichment degree of the new fuel assembly is 1.8%, 2.4% and 3.1% respectively;
The first circulation reactor core adopts a combustible poison as an integrated gadolinium solid combustible poison, wherein the existing form of gadolinium in the integrated gadolinium solid combustible poison is UO2-Gd2O3, and the integrated gadolinium solid combustible poison are uniformly mixed together to form gadolinium-carrying fuel pellets, and form independent gadolinium-carrying fuel rods, wherein the mass percent of Gd2O3 in the gadolinium-carrying fuel pellets is 8%, and the number of the gadolinium-carrying fuel rods in each new fuel assembly is one of 4, 8, 12 or 16;
In the first cycle, the burnable poison is arranged in a new fuel assembly with enrichment degree of 2.4 percent and 3.1 percent, the first cycle is loaded in a partial low leakage mode, the transition cycle and the balance cycle are loaded in an extremely low leakage mode, and 72 groups of new fuel assemblies are loaded in each refueling of the transition cycle and the balance cycle;
The partial low leakage mode is that the low-burnup fuel assemblies and the new fuel assemblies are simultaneously arranged on the outermost ring of the reactor core, and the extremely low leakage mode is that the new fuel assemblies are all arranged on the inner ring of the reactor core and are alternately arranged with the burnup assemblies, and the outermost ring of the reactor core is the assembly with deeper burnup.
2. The method of loading a pressurized water reactor initial core loaded low burnup fuel assembly of claim 1, wherein the fresh fuel enrichment of the transition cycle and the balance cycle loading is 4.45% and/or 4.95%.
3. The method of loading a pressurized water reactor initial core loaded low burnup fuel assembly of claim 1, wherein the enrichment of U235 in the gadolinium-loaded fuel pellets in the initial cycle, the transition cycle, and the equilibrium cycle is lower than the enrichment of U235 in the assembly.
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