JP5752349B2 - Boiling water reactor core - Google Patents

Description

  The present invention relates to a core of a boiling water reactor.

  In nuclear reactors, neutrons are absorbed by fissionable materials, causing fission, and neutrons released along with the energy continue to produce energy by a chain reaction. The state in which this chain reaction is in equilibrium is called criticality, and the reactor operated at a constant power continues to maintain this state. In addition, the state in which the chain reaction increases is called supercritical, and the state in which the chain reaction decreases is called subcritical.

  Since a nuclear reactor must be operated without refueling for a predetermined period of time, for example, about one year, more nuclear fissionable material is loaded in the core than is necessary for maintaining criticality. Therefore, in the period up to the middle of the predetermined operation period, the nuclear reactor becomes supercritical without the control material.

  This excess reactivity is referred to as excess reactivity, and it is important to appropriately control the excess reactivity throughout the operation period. As a technique for controlling the excess reactivity throughout the operation period, a technique in which a flammable poison is mixed into the fuel is well known. A flammable poison is a neutron absorber that gradually burns and decreases in the amount of material throughout the operation period. Gadolinia, which is used in combination with nuclear fuel materials, is known.

  The infinite multiplication factor of the fuel assembly containing the combustible poison increases once with combustion and then decreases. Generally, if the number of fuel rods containing a flammable poison increases, the infinite multiplication factor at the initial stage of combustion decreases. Further, if the concentration of the flammable poison is increased, the time when the flammable poison is burned out can be delayed, so that the maximum value of the infinite multiplication factor can be suppressed. For this reason, the excess reactivity can be appropriately controlled by the combination of the mixing concentration of the flammable poison and the number of fuel rods mixed with it.

  In the initial loading core, a part of the loaded fuel assembly is taken out after the operation of the first cycle is completed and replaced with a new replacement fuel assembly. The fuel assembly taken out in the first cycle has a lower burnup and generates less energy than other fuel assemblies. For this reason, the fuel economy increases as the number of fuel assemblies taken out in the first cycle decreases.

  However, if the core average enrichment is simply increased in order to improve fuel economy, thermal characteristics such as the minimum critical power ratio and the maximum linear power density deteriorate, and the safety of the reactor may be impaired. Therefore, in order to make effective use of fissile material, an initially loaded core using a plurality of fuel assemblies having different uranium enrichments in accordance with the period of stay in the reactor is known.

  For example, Patent Document 1 discloses an initial loading core in which unit loading units composed of four fuel assemblies in two rows and two columns are regularly arranged. This unit loading unit is composed of one low-enriched fuel and three highly-enriched fuels, and is arranged so that the low-enriched fuel 4 included in the four unit loaded units forms a control cell adjacent to each other. Further, the gadolinia-containing fuel rods are unevenly distributed so that many gadolinia-containing fuel rods are located on the side of the high-concentration fuel included in the unit loading unit facing the low-concentration fuel. By arranging such fuel rods, deterioration of thermal characteristics due to the spectrum mismatch effect is suppressed.

  At the beginning of the reactor operating cycle, more fissile material is loaded into the core than is necessary to maintain criticality. For this reason, in the initial stage of the operation cycle, the critical state is maintained by inserting control rods into the core. The control rods are pulled out as time passes during the operation cycle, and at the end of the operation cycle, all the control rods are completely pulled out.

Japanese Patent No. 3186546

  In the core of a boiling water reactor, water, which is cooling water, is heated by heat generated by fission, and boils at a certain height in the axial direction. For this reason, the void ratio in the coolant is almost 0 in the lower part of the core, whereas it is about 70% in the upper part of the core. As a result, there is less neutron deceleration in the upper part of the core than in the lower part, and the heat output tends to be larger in the lower part of the core. That is, the axial distribution of the thermal output of the boiling water reactor tends to be a bottom peak.

  In order to flatten the radial power distribution of the core of the nuclear reactor, the control rod inserted into the core during operation is mainly used in the central region of the core. In comparison, the number of control rods inserted in the outer peripheral region of the core is reduced.

  Generally, control rods used during power operation are partially inserted, and fission in the lower core is suppressed, while fission in the upper core is not suppressed much. As a result, in the central region of the core where many control rods are inserted, the tendency of the axial distribution of heat output to become a bottom peak is suppressed.

  On the other hand, in the outer peripheral area of the core, the number of inserted control rods is smaller than that in the central area, and because it is far from the inserted control rods, the axial distribution of heat output is lower than that in the central area. The tendency to become is large. For this reason, in the outer peripheral region of the core, the linear output density tends to be high although the average fuel assembly output is not high due to neutron leakage.

  Therefore, an object of the present invention is to suppress a tendency that the axial distribution of heat output becomes a bottom peak in the outer peripheral region of the core.

In order to achieve the above-described object, the present invention is directed to a boiling water reactor core in which a fuel assembly is loaded in a substantially cylindrical space, and the fuel assembly including the first fuel assembly is loaded. And a fuel assembly including a second fuel assembly in which a ratio of an infinite multiplication factor below a predetermined height to an infinite multiplication factor above the predetermined height is smaller than the first fuel assembly. An outer peripheral region radially outside the central region in which a body is arranged, and the first condition is a fissile material above the predetermined height of the amount of fissile material below the predetermined height The ratio of the amount of combustible poisons below the predetermined height to the amount of combustible poisons above the predetermined height is the first condition. Be larger than the fuel assembly, the third condition The ratio of the thickness of the channel box below the predetermined height to the thickness of the channel box above the predetermined height is larger than that of the first fuel assembly, and the fourth condition is greater than the predetermined height. When the ratio of the lower water to heavy metal weight ratio to the upper water to heavy metal weight ratio above the predetermined height is smaller than the first fuel assembly, the second fuel assembly is The second fuel assembly in the outer peripheral region to satisfy at least one of the first condition, the second condition, the third condition, and the fourth condition and suppress a bottom peak in the outer peripheral region. of is larger than the percentage ratio number of repeating said first fuel assembly body number for the body number of the first fuel assembly body speed of the second fuel assembly in the central region, the The fuel assembly includes a highly enriched fuel assembly group and a low enriched fuel assembly group having a smaller amount of fissile material than the highly enriched fuel assembly group, and the first fuel assembly and the second fuel assembly. All belong to the highly enriched fuel assembly group .
The present invention also provides a core region of a boiling water reactor in which a fuel assembly is loaded in a substantially cylindrical space, a central region in which the fuel assembly including the first fuel assembly is loaded, The fuel assembly including a second fuel assembly in which a ratio of an infinite multiplication factor below a predetermined height to an infinite multiplication factor above the predetermined height is smaller than the first fuel assembly is arranged and the fuel assembly is arranged An outer peripheral region radially outward from the central region, and the first condition is that the ratio of the amount of fissile material below the predetermined height to the amount of fissile material above the predetermined height is the first condition. The ratio of the amount of combustible poison below the predetermined height to the amount of combustible poison above the predetermined height is larger than that of the first fuel assembly. The third condition is more than the predetermined height The ratio of the thickness of the channel box to the thickness of the channel box above the predetermined height is larger than that of the first fuel assembly, and the fourth condition is that water to heavy metal below the predetermined height When the ratio of the weight ratio to the weight ratio of water to heavy metal above the predetermined height is smaller than that of the first fuel assembly, the second fuel assembly has the first condition, In order to satisfy at least one of the second condition, the third condition, and the fourth condition, and to suppress the bottom peak in the outer peripheral region, the number of the second fuel assemblies in the outer peripheral region is the first number. The ratio of the number of fuel assemblies to the number of bodies is larger than the ratio of the number of bodies of the second fuel assemblies in the central region to the number of bodies of the first fuel assemblies, and the fuel assemblies are highly concentrated. And a low enriched fuel assembly group having a smaller amount of fissile material than the highly enriched fuel assembly group, both of the first fuel assembly and the second fuel assembly being the low enriched fuel assembly. It belongs to an aggregate group.

  According to the present invention, it is possible to suppress the tendency that the axial distribution of heat output becomes a bottom peak in the outer peripheral region of the core.

FIG. 2 is a ¼ cross-sectional view showing the arrangement of fuel assemblies in the first embodiment of the core of the boiling water reactor according to the present invention. It is a cross section (horizontal cross section) figure in 1st Embodiment of the core of the boiling water reactor which concerns on this invention. 1 is a cross-sectional view of a fuel assembly used in a first embodiment of a core of a boiling water reactor according to the present invention. 1 is a cross-sectional view showing a fuel rod arrangement of a highly enriched high gadolinia fuel assembly used in a first embodiment of a core of a boiling water reactor according to the present invention. It is a cross-sectional view showing the fuel rod arrangement of the highly enriched low gadolinia fuel assembly used in the first embodiment of the core of the boiling water reactor according to the present invention. It is a cross-sectional view showing the fuel rod arrangement of the highly concentrated power distribution adjusting fuel used in the first embodiment of the core of the boiling water reactor according to the present invention. It is a cross-sectional view showing the fuel rod arrangement of the low-enriched fuel used in the first embodiment of the core of the boiling water reactor according to the present invention. It is a cross-sectional view showing the fuel rod arrangement of the fuel for adjusting the low concentrated power distribution used in the first embodiment of the core of the boiling water reactor according to the present invention. It is a cross-sectional view showing the fuel rod arrangement of the low-enriched fuel assembly used in the second embodiment of the core of the boiling water reactor according to the present invention.

  Embodiments of the core of a boiling water reactor according to the present invention will be described with reference to the drawings. In addition, the same code | symbol is attached | subjected to the same or similar structure, and the overlapping description is abbreviate | omitted.

[First Embodiment]
FIG. 2 is a transverse cross-sectional view (horizontal cross-sectional view) in the first embodiment of the core of the boiling water nuclear reactor according to the present invention. FIG. 3 is a cross-sectional view of the fuel assembly used in the present embodiment. FIG. 2 is a diagram showing the upper left quarter of the cross section of the core, and the remaining portion is rotationally symmetric with respect to the illustrated portion with the central axis in the vertical direction of the core as the symmetry axis. Note that the entire core does not need to be rotationally symmetric, and may be mirror-symmetrical or a core without symmetry.

  The boiling water reactor has a region 10 in which spaces 22 in which square-tubular fuel assemblies 26 are arranged are arranged in a square lattice pattern. The region 10 is formed in a substantially cylindrical shape as a whole, and the axis of the fuel assembly 26 is directed in the same direction as the axis of the cylinder. Fuel assemblies 26 are arranged in these spaces 22 to form a core.

  The space 22 in which the fuel assembly 26 is arranged is slightly larger than the fuel assembly 26, and the control rod 21 can be inserted between the four adjacent fuel assemblies 26. A space 22 in which a fuel assembly 26 that is not adjacent to the control rod 21 is also present in a part of the region 10 on the outer side in the radial direction.

  In the core of the present embodiment, 872 fuel assemblies 26 are loaded, and 205 control rods 21 are arranged.

  The fuel assembly 26 includes cylindrical fuel rods 24 arranged in a square lattice in 9 rows and 9 columns, and a rectangular tube-shaped water channel 25 arranged in the center of the array of fuel rods 24. Yes. The water channel 25 occupies an area of nine fuel rods 24 in 3 rows and 3 columns. The fuel rod 24 and the water channel 25 are held by tie plates (not shown) provided at both ends in the axial direction and spacers (not shown) provided at several locations in the axial direction. The outer periphery of the fuel assembly 26 is surrounded by a rectangular tubular channel box 23.

  Inside the fuel rod 24, a fissile material such as uranium 235 is stored as a pellet baked into a cylindrical shape together with uranium 238, for example. The enrichment of uranium 235 in each fuel rod 24 is different for each fuel rod 24, and the amount of fissile material contained in each fuel rod 24 is also different for each fuel rod 24. In addition, you may provide the area | region where enrichment differs in the axial direction of the fuel rod 24. FIG.

  FIG. 1 is a ¼ cross-sectional view showing the arrangement of fuel assemblies in the present embodiment. Reference numerals 1 to 5 each indicate the type of the fuel assembly 26, and the same reference numerals indicate fuel assemblies having the same arrangement of the fuel rods 24.

  This core 11 is an initial loading core, and five kinds of fuel assemblies 1, 2, 3, 4, and 5 are loaded. These are a highly enriched high gadolinia fuel assembly 1, a highly enriched low gadolinia fuel assembly 2, a highly enriched output distribution adjusting fuel assembly 3, a low enriched fuel assembly 4, and a low enriched output distribution adjusting fuel assembly 5. is there.

  The core 11 is divided into three regions: a central region 71, an outer peripheral region 72, and an outermost peripheral region 73 from the center in the radial direction to the outer side. The outermost peripheral area 73 is an area of about two layers from the outermost outer periphery of the core 11. The inner peripheral region 72 is a region outside the core radius of about 0.6 from the core center and inside the outermost peripheral region 73.

  The highly enriched low gadolinia fuel assembly 2 is arranged in the outermost peripheral region 73 of the first or second layer from the outermost periphery of the core 11 toward the radially inner side. In the outer peripheral region 72, there are about one to three layers from the outermost peripheral region 73 toward the inside in the radial direction of the core 11, and the high enriched power distribution adjusting fuel assembly 3 and the low enriched power distribution adjusting fuel assembly 5. Is arranged.

  Control cells 74 and 75 are formed in the central region 71 and the outer peripheral region 72. The control cells 74 and 75 are a set (cell) of fuel assemblies in which the four fuel assemblies surrounding a certain control rod 21 are all the low enriched fuel assemblies 4 and 5. The control rod 21 located in the control cells 74 and 75 is mainly used for the control by the control rod 21 of the core during operation. In particular, 13 control cells 74 indicated by white squares are used in the central region 71 of the core 11 during most of the operation cycle. In these control cells 74, the low enriched fuel assemblies 4 are arranged.

  In the central region 71, the highly enriched and high gadolinia fuel assembly 1 is disposed at a position facing the control cells 74 and 75. Highly enriched low gadolinia fuel assemblies 2 are loaded in most of the positions diagonal to the control cells 74 and 75. The fuel assembly 3 for highly concentrated output distribution adjustment is disposed at a part of the central region 71 that is diagonal to the control cell.

  FIG. 4 is a cross-sectional view showing the fuel rod arrangement of the highly enriched high gadolinia fuel assembly used in the present embodiment. FIG. 5 is a cross-sectional view showing the fuel rod arrangement of the highly enriched low gadolinia fuel assembly used in the present embodiment. FIG. 6 is a cross-sectional view showing the fuel rod arrangement of the highly concentrated output distribution adjusting fuel used in the present embodiment. FIG. 7 is a cross-sectional view showing the fuel rod arrangement of the low-enriched fuel used in the present embodiment. FIG. 8 is a cross-sectional view showing the fuel rod arrangement of the low enriched output distribution adjusting fuel used in this embodiment.

  4 to 8, the positions indicated by 1 to 5 indicate that uranium fuel rods are arranged, and the positions indicated by G1 and G2 indicate that gadolinia-containing fuel rods are arranged. W indicates the position of the water channel or water rod.

  The highly enriched high gadolinia fuel assembly 1, the highly enriched low gadolinia fuel assembly 2, and the highly enriched power distribution adjusting fuel assembly 3 are arranged in a rectangular tube at a position that occupies the middle 3 rows and 3 columns of the 9 rows and 9 columns square lattice. Shaped water channels are arranged. The low enriched fuel assembly 4 and the low enriched output distribution adjusting fuel assembly 5 are provided with two cylindrical water rods in the center of a 9 × 9 square lattice and occupy seven lattice positions. . Thus, a plurality of types of fuel assemblies having different internal shapes may be used for one core 11.

  The uranium fuel rod is a fuel rod 24 that does not contain a flammable poison such as gadolinia. Uranium fuel rods arranged at different numbers have different uranium 235 enrichments. As the uranium fuel rods are arranged at positions where the numbers in the same fuel assembly are larger, the enrichment of uranium is lower. That is, the enrichment of the fuel rod indicated by 1 is the highest, and the enrichment of the uranium fuel rod at the position indicated by 4 is the lowest. The enrichment of the uranium fuel rod indicated by 1 is, for example, 4.9 wt%. Further, the fuel rod arranged at the position indicated by 1 'has a low uranium enrichment at the lower part in the axial direction. The fuel rod arranged at the position indicated by 2 'has a low enrichment of uranium at the upper part in the axial direction.

  Further, as the fissile material, plutonium, thorium, or a combination thereof may be used instead of uranium. In this case, fissile material concentration is taken into account instead of uranium enrichment.

  The fuel rod containing gadolinia is a fuel rod 24 containing a combustible poison such as gadolinia together with a fissile material. The fuel rod containing gadolinia arranged at the position indicated by G1 is a full length gadolinia containing fuel rod containing a combustible poison throughout the effective fuel portion. The fuel rod with gadolinia arranged at the position indicated by G2 contains a flammable poison at the lower part of the effective fuel part, for example, from the lower end to about 1/3 of the effective fuel length, and at the upper part, the flammable poison. This is a fuel rod containing part-length gadolinia that does not contain.

  Even a fuel rod containing gadolinia may be provided with a blanket region loaded with natural uranium pellets at a length of about 1/24 or 2/24 of the effective fuel length at the upper and lower ends of the effective fuel portion. In addition to gadolinia, erbia, boron, and combinations thereof can be used as the flammable poison. The amount of the flammable poison in the fuel assembly can be changed by the number and volume of fuel rods containing the flammable poison, the concentration of the flammable poison, or a combination thereof.

  The highly enriched high gadolinia fuel assembly 1 uses 14 gadolinia-containing fuel rods, two of which are partial-length gadolinia-containing fuel rods. The highly enriched low gadolinia fuel assembly 2 uses twelve gadolinia containing fuel rods, one of which is a gadolinia containing fuel rod. On the other hand, the fuel assembly 3 for adjusting the highly concentrated output distribution uses 14 gadolinia-containing fuel rods, of which 4 are partial-length fuel rods. That is, the highly concentrated output distribution adjusting fuel assembly 3 has more gadolinia-containing fuel rods in the lower axial region than the highly enriched high gadolinia fuel assembly 1 or the highly enriched low gadolinia fuel assembly 2. Therefore, in the initial stage of the lifetime when gadolinium burns out, the highly concentrated output distribution adjusting fuel assembly 3 is lower in the axial direction than the highly enriched high gadolinia fuel assembly 1 or the highly enriched low gadolinia fuel assembly 2. The ratio of the infinite multiplication factor with respect to the upper part in the axial direction is small. The infinite multiplication factor is the ratio of generation and extinction of neutrons when a section of the fuel assembly is arranged infinitely in the section direction. That is, the highly enriched output distribution adjusting fuel assembly 3 is a fuel assembly in which the axial power distribution tends to become a top peak compared to the highly enriched high gadolinia fuel assembly 1 or the highly enriched low gadolinia fuel assembly 2. is there.

  The fuel assembly 5 for adjusting the low enrichment output distribution uses eight fuel rods 2 'having low axial enrichment in the vicinity of the corner portion, but the fuel rod having low enrichment in the axially lower portion in the inner peripheral region. Thirty 1's are used. Therefore, the low enriched output distribution adjusting fuel assembly 5 has a smaller ratio of the infinite multiplication factor to the axially upper portion in the lower axial direction than the low enriched fuel assembly 4. That is, the low enriched power distribution adjusting fuel assembly 5 is a fuel assembly in which the axial power distribution is likely to have a top peak compared to the low enriched fuel assembly 4.

  Thus, in the present embodiment, the ratio of the amount of fissile material below the predetermined height to the amount of fissile material above the predetermined height is small, or the combustible below the predetermined height. Because the ratio of the amount of toxic poison to the amount of flammable poison above the predetermined height is large, the ratio of the infinite multiplication factor below the predetermined height to the infinite multiplication factor above the predetermined height is A fuel assembly 26 smaller than the fuel assembly 26 mainly loaded in the peripheral region 71 is formed. Further, by increasing the thickness of the channel box 23 below the predetermined height, the ratio of the infinite multiplication factor below the predetermined height to the infinite multiplication factor above the predetermined height is set in the inner peripheral region 71. You may form the fuel assembly 26 smaller than the fuel assembly 26 mainly loaded. Alternatively, the weight ratio of the water to heavy metal below the predetermined height is reduced by changing the shape of the water channel 25, and the infinite increase above the predetermined height of the infinite multiplication factor below the predetermined height. You may form the fuel assembly 26 whose ratio with respect to a magnification is smaller than the fuel assembly 26 mainly loaded by the inner peripheral area | region 71. FIG.

  The predetermined height, that is, the boundary between the lower portion in the axial direction and the upper portion in the axial direction for comparing the infinite multiplication factor is, for example, about a third of the effective fuel length from the lower end of the core. This is because, in a boiling water reactor, the void ratio generally increases from a position about 1/3 of the effective fuel length from the lower end of the core, so the bottom peak of the axial power distribution is high. This is because it tends to appear below.

  In the core 11 using these fuel assemblies, the critical state is maintained by inserting the control rod 21 in the initial stage of the operation cycle. At this time, as the control rod 21 inserted into the core during operation, a rod mainly located in the central region of the core is used in order to flatten the radial power distribution of the reactor core. In the present embodiment, the control rod 21 of the control cell 74 in the central region 71 is inserted. In comparison, the number of control rods inserted in the outer peripheral region 72 of the core is reduced. For this reason, in the outer peripheral region 72 of the core, the axial power distribution tends to be a bottom peak.

  However, in the present embodiment, the high enriched power distribution adjusting fuel assembly 3 is loaded in the outer peripheral region 72 of the core instead of the highly enriched high gadolinia fuel assembly 1 or the highly enriched low gadolinia fuel assembly 2. Yes. Further, in the outer peripheral region 72 of the core, the low enriched power distribution adjusting fuel assembly 5 is loaded instead of the low enriched fuel assembly 4.

  The highly concentrated output distribution adjusting fuel assembly 3 is loaded with many fuel rods containing part-length gadolinia containing a flammable poison only in the lower part. For this reason, by arranging the highly concentrated output distribution adjusting fuel assembly 3 in the outer peripheral region 72, the axial output distribution can be made uniform. Further, by arranging the low concentrated output distribution adjusting fuel assembly 5 in which the enrichment at the upper part in the axial direction is increased in the outer peripheral region 75, the axial output distribution can be made uniform. That is, the axial output distribution in the outer peripheral region 72 can be suppressed from becoming an excessively bottom peak.

  In the outermost peripheral region 73 of the core 11, the heat output per fuel assembly is smaller than that in the inner region. Therefore, in the outermost peripheral area 73, the void ratio is smaller than that in the inner area, and the axial output distribution is less likely to have a bottom peak. For this reason, if the high-concentration output distribution adjustment fuel assembly 3 or the low-concentration output distribution adjustment fuel assembly 5 is loaded in the outermost peripheral region 73 to suppress the tendency that the axial output distribution becomes the bottom peak, Combustion in the area is difficult to proceed.

  However, in the case of the initial loading core, the fuel assembly loaded in the outermost peripheral region 73 of the core 11 is often moved to a region inside the core in the subsequent operation cycle. For this reason, in the initial loading core, the fuel composition 3 for high enriched power distribution adjustment or the fuel assembly 5 for low enriched power distribution adjustment is loaded in the outermost peripheral region 73 to suppress the tendency that the axial power distribution becomes the bottom peak. Then, in these fuel assemblies, the axial output distribution is more likely to have a bottom peak in the subsequent operation cycle. Therefore, in the present embodiment, the highly concentrated output distribution adjusting fuel assembly 3 or the low concentrated output distribution adjusting fuel assembly 5 is not loaded in the outermost peripheral region 73.

  Even in the central region 71, the axial output distribution has a slightly bottom peak in the control cell 75 where the control rod 21 is hardly inserted during operation and in the vicinity thereof. Therefore, the maximum linear power density can be suppressed by loading the highly concentrated output distribution adjusting fuel assembly 3 or the low concentrated output distribution adjusting fuel assembly 5 at such a position. As described above, the highly concentrated output distribution adjusting fuel assembly 3 and the low concentrated output distribution adjusting fuel assembly 5 may be loaded in the central region 71. However, as the number of loaded bodies increases, the axial direction in the central region 71 increases. The output distribution approaches the top peak. Therefore, the number of high-concentration output distribution adjustment fuel assemblies 3 and low-concentration output distribution adjustment fuel assemblies 5 loaded in the central region 71 corresponds to the total number of high-enrichment fuel assemblies or low-enrichment fuel assemblies, respectively. The proportion should be less than or equal to the proportion loaded in the outer peripheral region 72.

  In the outer peripheral region 72, the heat output per fuel assembly tends to be low due to neutron leakage from the core system. Further, the minimum limit output ratio greatly depends on the aggregate output. For this reason, in the outer peripheral region 72, although the linear output density is high due to the bottom peak in the axial direction output distribution, the minimum limit output ratio tends to increase (become easier). Therefore, when the axial output distribution is flattened, the heat output per fuel assembly can be increased accordingly.

  In the present embodiment, the highly concentrated output distribution adjusting fuel assembly 3 has fewer full-length gadolinia containing fuel rods than the highly enriched high gadolinia fuel assembly 1 and the highly enriched low gadolinia fuel assembly 2. Yes. That is, the highly concentrated output distribution adjusting fuel assembly 3 increases the heat output per fuel assembly while being disposed in the outer peripheral region 72. Further, by loading the low enriched output distribution adjusting fuel assembly 5 having a higher assembly average enrichment than the low enriched fuel assembly 4 to the outer peripheral region 72, the heat output per fuel assembly in the outer peripheral region 72 is obtained. Is increasing. For this reason, the heat output per fuel assembly disposed in the central region 71 is relatively small. As a result, it is possible to improve the characteristics of the central region 71 where the minimum limit output ratio tends to be small. Note that the heat output per fuel assembly may be increased by reducing the average thickness in the axial direction of the channel box 23 or increasing the weight ratio of water to heavy metal.

  Further, the highly concentrated fuel facing the control cells 74 and 75 loaded with the low enriched fuel assemblies 4 and 5 tends to be deteriorated in thermal characteristics due to the spectrum mismatch effect. Therefore, in the present embodiment, many gadolinia-containing fuel rods are arranged on the side of the highly enriched and highly gadolinia fuel assembly 1 facing the low enriched fuel, that is, on the counter-control rod side. This alleviates the deterioration of thermal characteristics. In addition, since the spectrum mismatch effect is not large at positions diagonal to the control cells 74 and 75, the arrangement of the gadolinia-containing fuel rods of the highly enriched low gadolinia fuel assembly 2 is distributed almost uniformly.

  The low enriched power distribution adjusting fuel assembly 5 improves the thermal characteristics of the central region by increasing the thermal output per fuel assembly in the outer peripheral region 72, but the low enriched fuel assembly 4 Compared to, the furnace shutdown margin is likely to deteriorate. Therefore, in the present embodiment, measures are taken to improve the reactor shutdown margin in the low concentrated power distribution adjusting fuel assembly 5.

  The measure for improving the reactor shutdown margin applied to the low enriched power distribution adjusting fuel assembly 5 is, for example, reducing the enrichment of the fuel rods near the corner of the low enriched power distribution adjusting fuel assembly 5. It is. Alternatively, a fuel rod having a lower enrichment in the upper axial direction where the output is higher at low temperatures may be used. The furnace stop margin is greatly influenced by the corners facing more water and the fuel rods in the vicinity thereof. Therefore, for example, such a fuel rod may be used at the position indicated by 2 'in FIG.

  By providing a region using uranium with low enrichment only above the effective fuel effective portion for improving the reactor shutdown margin, the reactor shutdown margin can be increased without significantly reducing the average enrichment of the fuel assembly. Can improve. In addition, fuel rods with reduced overall enrichment of the fuel effective part are used only at the corners and the vicinity that are most effective for improving the furnace shutdown margin, for example, thereby suppressing a decrease in the average enrichment of the fuel assembly. it can.

  In this way, the furnace shutdown margin can be improved while the assembly average enrichment of the low enriched power distribution adjusting fuel assembly 5 is higher than that of the low enriched fuel assembly 4. Similarly, in the highly concentrated power distribution adjusting fuel 3, the furnace stop margin can be improved by lowering the enrichment in the vicinity of the corner or the enrichment in the upper part in the axial direction.

  The axial power distribution at the time of cold temperature, that is, when the furnace is stopped has a peak at a height of about 20/24 from the lower end of the core. For this reason, the region having a length about 1/3 of the effective fuel length from the upper end of the effective fuel portion has a great influence on the furnace stop margin. Therefore, in order to improve the furnace stop margin, the enrichment of the region having a length of about 1/3 of the effective fuel length from the upper end of the effective fuel portion may be reduced.

[Second Embodiment]
FIG. 9 is a cross-sectional view showing the fuel rod arrangement of the low-enriched fuel assembly used in the second embodiment of the core of the boiling water reactor according to the present invention.

  In FIG. 9, the fuel rods arranged at the positions indicated by 2 ′ and 3 ′ have low uranium enrichment at the upper part in the axial direction. In the present embodiment, the low-enriched fuel assembly 4 is different from the first embodiment. In the low enriched fuel assembly of the present embodiment, the enrichment of the fuel rods arranged in the vicinity of the corner portion closest to the axial center of the control rod is lowered, and the enrichment of the upper region is lowered.

  When the bottom peak is suppressed by using a fuel assembly having a small ratio of the infinite multiplication factor with respect to the axial upper portion in the axial lower portion as in the first embodiment or the present embodiment, that is, the axial output distribution is made uniform. In this case, the axial output distribution may reach a top peak in the area around the control rod inserted during operation. This tendency is remarkable when the control rod is pulled out relatively shallowly. In a cell operated with a control rod inserted for a certain period, the thermal characteristics may deteriorate due to the control rod history effect when the control rod is pulled out.

  However, in the present embodiment, the enrichment is lowered particularly in the vicinity of the corner fuel rod on the side where the control rod is inserted, and the enrichment of the upper region where plutonium is likely to be accumulated when the control rod is inserted is lowered. The deterioration of the thermal characteristics can be alleviated. Thereby, it can suppress that the axial direction power distribution of a core center area | region becomes an extreme top peak. Further, the upper enrichment of the highly enriched high gadolinia fuel assembly 1 (see FIG. 4) and the highly enriched low gadolinia fuel assembly 2 (see FIG. 5) may be similarly reduced.

[Other embodiments]
The above-described embodiments are merely examples, and the present invention is not limited to these. For example, although the initial loading core has been described here as an example, the present invention can also be applied to a replacement core. When applied to a replacement core, the fuel may be arranged so as to have the same relationship as that of the above-mentioned initial loading core based on the infinite multiplication factor of each cross section of the fuel assembly at the beginning of the operation cycle. Moreover, it can also implement combining the characteristic of each embodiment.

DESCRIPTION OF SYMBOLS 1 ... High enrichment high gadolinia fuel assembly, 2 ... High enrichment low gadolinia fuel assembly, 3 ... High enrichment output distribution adjustment fuel assembly, 4 ... Low enrichment fuel assembly, 5 ... Low enrichment output distribution adjustment fuel assembly 11 ... core, 21 ... control rod, 23 ... channel box, 24 ... fuel rod, 25 ... water channel, 26 ... fuel assembly, 71 ... central region, 72 ... outer peripheral region, 73 ... outermost peripheral region, 74 ... Control cell, 75 ... control cell, 22 ... space, 10 ... area

Claims (6)

In the core of a boiling water reactor in which a fuel assembly is loaded in a substantially cylindrical space,
A central region loaded with the fuel assembly including a first fuel assembly;
The fuel assembly including a second fuel assembly in which a ratio of an infinite multiplication factor below a predetermined height to an infinite multiplication factor above the predetermined height is smaller than the first fuel assembly is arranged and the fuel assembly is arranged An outer peripheral region radially outward from the central region;
Have
The first condition is that a ratio of the amount of fissile material below the predetermined height to the amount of fissile material above the predetermined height is smaller than that of the first fuel assembly,
The ratio of the amount of combustible poison below the predetermined height to the amount of combustible poison above the predetermined height is greater than the first fuel assembly, the second condition
The third condition is that the ratio of the thickness of the channel box below the predetermined height to the thickness of the channel box above the predetermined height is larger than that of the first fuel assembly,
The fourth condition is that the ratio of the weight ratio of water to heavy metal below the predetermined height to the weight ratio of water to heavy metal above the predetermined height is smaller than that of the first fuel assembly.
The second fuel assembly satisfies at least one of the first condition, the second condition, the third condition, and the fourth condition,
To suppress the bottom peak in the outer peripheral region, the body of the second fuel assemblies ratio body speed of the second fuel assemblies of the body number of the first fuel assembly in the peripheral area in the central region Greater than the ratio of the number of the first fuel assemblies to the number of bodies ,
The fuel assembly is
A highly enriched fuel assembly group and a low enriched fuel assembly group having a smaller amount of fissile material than the highly enriched fuel assembly group,
The first fuel assembly and the second fuel assembly both belong to the highly enriched fuel assembly group.
A boiling water reactor core characterized by that. In the core of a boiling water reactor in which a fuel assembly is loaded in a substantially cylindrical space,
A central region loaded with the fuel assembly including a first fuel assembly;
The fuel assembly including a second fuel assembly in which a ratio of an infinite multiplication factor below a predetermined height to an infinite multiplication factor above the predetermined height is smaller than the first fuel assembly is arranged and the fuel assembly is arranged An outer peripheral region radially outward from the central region;
Have
The first condition is that a ratio of the amount of fissile material below the predetermined height to the amount of fissile material above the predetermined height is smaller than that of the first fuel assembly,
The ratio of the amount of combustible poison below the predetermined height to the amount of combustible poison above the predetermined height is greater than the first fuel assembly, the second condition
The third condition is that the ratio of the thickness of the channel box below the predetermined height to the thickness of the channel box above the predetermined height is larger than that of the first fuel assembly,
The fourth condition is that the ratio of the weight ratio of water to heavy metal below the predetermined height to the weight ratio of water to heavy metal above the predetermined height is smaller than that of the first fuel assembly.
The second fuel assembly satisfies at least one of the first condition, the second condition, the third condition, and the fourth condition,
In order to suppress the bottom peak in the outer peripheral region, the ratio of the number of the second fuel assemblies in the outer peripheral region to the number of the first fuel assemblies in the outer region is the body of the second fuel assembly in the central region. Greater than the ratio of the number of the first fuel assemblies to the number of bodies,
The fuel assembly is
A highly enriched fuel assembly group and a low enriched fuel assembly group having a smaller amount of fissile material than the highly enriched fuel assembly group,
The first fuel assembly and the second fuel assembly both belong to the low enriched fuel assembly group.
Boiling Agamizu reactor core of you, wherein a. The said 2nd fuel assembly is equipped with the fuel rod in which the upper area | region where the fissile material density | concentration is small compared with the average of the whole fuel effective part was formed, The Claim 1 or Claim 2 characterized by the above-mentioned. Boiling water reactor core. The fifth condition is that the amount of fissile material in the entire fuel assembly is larger than that of the first fuel assembly,
The sixth condition is that the amount of flammable poisons of the entire fuel assembly is smaller than that of the first fuel assembly,
The seventh condition is that the average axial thickness of the channel box is smaller than that of the first fuel assembly,
The eighth condition is that the weight ratio of water to heavy metal is larger than that of the first fuel assembly,
The second fuel assembly satisfies at least one of the fifth condition, the sixth condition, the seventh condition, and the eighth condition. The core of the boiling water reactor according to any one of claims 3 to 4. A ratio of a fissionable material amount of a fuel rod disposed at a corner portion closest to the control rod of the second fuel assembly and a position adjacent to the corner portion to a fissionable material amount of the entire fuel assembly; and 2. At least one of the ratio of the amount of fission material in the region of a predetermined length from the upper end of the fuel effective portion of the fuel assembly to the amount of fissile material in the entire fuel assembly is smaller than that of the first fuel assembly. The core of a boiling water reactor according to any one of claims 1 to 4, wherein the core is a boiling water reactor. The core of a boiling water reactor according to any one of claims 1 to 5, wherein the core is an initial load .

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