Patent Number: 
Section: claims

1. A boiling water reactor, comprising:a reactor pressure vessel;a core disposed in said reactor pressure vessel and loaded with a plurality of fuel assemblies including transuranic nuclides; anda coolant supplying apparatus which supplies a coolant to said core,wherein a ratio of Pu-239 in all of said transuranic nuclides included in said fuel assembly, which is loaded in said core, with a burnup of 0 is 3% or more but 45% or less; andin said fuel assembly having a channel box and a plurality of fuel rods disposed in said channel box, a transverse cross section of a fuel pellet in said fuel rod occupies 30% or more but 55% or less of a transverse cross section of a unit fuel rod lattice in said channel box, the transverse cross section of the unit fuel rod lattice in said channel box including a transverse cross section of said fuel rod and a transverse cross section of a portion of a moderator surrounding said fuel rod in said channel box. 2. The boiling water reactor according to claim 1,wherein said ratio of Pu-239 in all of said transuranic nuclides is 40% or more but 45% or less. 3. The boiling water reactor according to claim 1,wherein said ratio of Pu-239 in all of said transuranic nuclides is 3% or more but less than 40%. 4. The boiling water reactor according to claim 1,wherein said core is a parfait core being disposed axially an upper blanket zone, an upper fissile zone, an internal blanket zone, a lower fissile zone, and a lower blanket zone in turn from a top thereof. 5. The boiling water reactor according to claim 1,wherein said core is a one fissile zone core being disposed axially an upper blanket zone, a fissile zone, and a lower blanket zone in turn from a top thereof. 6. The boiling water reactor according to claim 1, wherein said ratio of Pu-239 in all of said transuranic nuclides included in said fuel assembly with said burnup of 0 is 3% or more but 15% or less. 7. The boiling water reactor according to claim 1, wherein said channel box is a hexagonal channel box and the transverse cross section of the unit fuel rod lattice which includes the portion of the moderator surrounding said fuel rod in said hexagonal channel box is a hexagonal transverse cross section. 8. The boiling water reactor according to claim 7, wherein the hexagonal transverse cross section of the unit fuel rod lattice includes the transverse cross section of a substantially circular cross section of said fuel rod and a surrounding region of the moderator surrounding said fuel rod in a hexagonal shape in cross section. 9. A boiling water reactor, comprising:a reactor pressure vessel;a core disposed in said reactor pressure vessel and loaded with a plurality of fuel assemblies including transuranic nuclides; anda coolant supplying apparatus which supplies a coolant to said core,wherein a ratio of Pu-239 in all Pu elements included in said fuel assembly, which is loaded in said core, with a burnup of 0 is 3% or more but 50% or less, and a ratio of Pu-240 in said all Pu elements is 35% or more but 45% or less; andin said fuel assembly having a channel box and a plurality of fuel rods disposed in said channel box, a transverse cross section of a fuel pellet in said fuel rod occupies 30% or more but 55% or less of a transverse cross section of a unit fuel rod lattice in said channel box, the transverse cross section of the unit fuel rod lattice in said channel box including a transverse cross section of said fuel rod and a transverse cross section of a portion of a moderator surrounding said fuel rod in said channel box. 10. The boiling water reactor according to claim 9,wherein said ratio of Pu-239 in all of said transuranic nuclides is 40% or more but 45% or less. 11. The boiling water reactor according to claim 9,wherein said ratio of Pu-239 in all of said transuranic nuclides is 3% or more but less than 40%. 12. The boiling water reactor according to claim 9,wherein said core is a parfait core being disposed axially an upper blanket zone, an upper fissile zone, an internal blanket zone, a lower fissile zone, and a lower blanket zone in turn from a top thereof. 13. The boiling water reactor according to claim 9,wherein said core is a one fissile zone core being disposed axially an upper blanket zone, a fissile zone, and a lower blanket zone in turn from a top thereof. 14. The boiling water reactor according to claim 9, wherein said ratio of Pu-239 in all of said transuranic nuclides included in said fuel assembly with said burnup of 0 is 3% or more but 15% or less. 15. The boiling water reactor according to claim 9, wherein said channel box is a hexagonal channel box and the transverse cross section of the unit fuel rod lattice which includes the portion of the moderator surrounding said fuel rod in said hexagonal channel box is a hexagonal transverse cross section. 16. The boiling water reactor according to claim 15, wherein the hexagonal transverse cross section of the unit fuel rod lattice includes the transverse cross section of a substantially circular cross section of said fuel rod and a surrounding region of the moderator surrounding said fuel rod in a hexagonal shape in cross section. 17. A boiling water reactor comprising:a reactor pressure vessel;a core disposed in said reactor pressure vessel and loaded with a plurality of fuel assemblies including transuranic nuclides;a coolant supplying apparatus which supplies a coolant within said reactor pressure vessel to said core by pressurizing said coolant; anda coolant flow rate control apparatus which adjusts a flow rate of the coolant supplied to said core by controlling said coolant supplying apparatus, and said coolant flow rate control apparatus setting a coolant flow rate in an operation cycle to a set coolant flow rate which is determined based on a ratio of Pu-239 in transuranic nuclides included in said fuel assembly with a burnup of 0, which is loaded in said core before an operation starts in said operation cycle, so that ratios of a plurality of isotopes of transuranic nuclides present in said core upon the completion of said operation in said operation cycle are substantially the same as ratios of said plurality of isotopes in a state in which said operation in said operation cycle can be started;wherein said ratio of Pu-239 in all of said transuranic nuclides included in said fuel assembly with a burnup of 0 is 3% or more but 45% or less; andwherein in said fuel assembly having a channel box and a plurality of fuel rods disposed in said channel box, a transverse cross section of a fuel pellet in said fuel rod occupies 30% or more but 55% or less of a transverse cross section of a unit fuel rod lattice in said channel box, the transverse cross section of the unit fuel rod lattice in said channel box including a transverse cross section of said fuel rod and a transverse cross section of a portion of a moderator surrounding said fuel rod in said channel box. 18. The boiling water reactor according to claim 17,wherein said ratio of Pu-239 in all of said transuranic nuclides is 40% or more but 45% or less. 19. The boiling water reactor according to claim 17,wherein said ratio of Pu-239 in all of said transuranic nuclides is 3% or more but less than 40%. 20. The boiling water reactor according to claim 17,wherein said ratio of Pu-239 in all of said transuranic nuclides included in said fuel assembly with said burnup of 0 is 3% or more but 15% or less. 21. The boiling water reactor according to claim 20,wherein said core is a parfait core being disposed axially an upper blanket zone, an upper fissile zone, an internal blanket zone, a lower fissile zone, and a lower blanket zone in turn from a top thereof. 22. The boiling water reactor according to claim 20,wherein the state in which said ratios of said plurality of isotopes of transuranic nuclides present in said core upon the completion of said operation in said operation cycle are substantially the same as ratios of said plurality of isotopes in a state in which said operation in said operation cycle can be started, is a state in which ratios of a plurality of isotopes of transuranic nuclides present in said fuel assembly taken out of said core are substantially the same as ratios of said plurality of isotopes present in said fuel assembly with a burnup of 0, which is to be loaded in said core. 23. The boiling water reactor according to claim 17,wherein said core is a parfait core being disposed axially an upper blanket zone, an upper fissile zone, an internal blanket zone, a lower fissile zone, and a lower blanket zone in turn from a top thereof. 24. The boiling water reactor according to claim 17,wherein said core is a one fissile zone core being disposed axially an upper blanket zone, a fissile zone, and a lower blanket zone in turn from a top thereof. 25. The boiling water reactor according to claim 17, further comprising:a plurality of control rods; anda control rod drive control apparatus which controls an operation of said control rods based on a measured reactor power. 26. The boiling water reactor according to claim 17, wherein said channel box is a hexagonal channel box and the transverse cross section of the unit fuel rod lattice which includes the portion of the moderator surrounding said fuel rod in said hexagonal channel box is a hexagonal transverse cross section. 27. The boiling water reactor according to claim 26, wherein the hexagonal transverse cross section of the unit fuel rod lattice includes the transverse cross section of a substantially circular cross section of said fuel rod and a surrounding region of the moderator surrounding said fuel rod in a hexagonal shape in cross section. 28. A core of a boiling water reactor, having a plurality of fuel assemblies including a plurality of isotopes of transuranic nuclides,wherein a ratio of Pu-239 in all of said transuranic nuclides included in said fuel assembly loaded in said core with a burnup of 0, is 3% or more but 45% or less;wherein said fuel assembly has a channel box and a plurality of fuel rods disposed in said channel box; andwherein a transverse cross section of a fuel pellet in said fuel rod occupies 30% or more but 55% or less of a transverse cross section of a unit fuel rod lattice in said channel box, the transverse cross section of the unit fuel rod lattice in said channel box including a transverse cross section of said fuel rod and a transverse cross section of a portion of a moderator surrounding said fuel rod in said channel box. 29. The core of a boiling water reactor according to claim 28,wherein said ratio of Pu-239 in all of said transuranic nuclides is 40% or more but 45% or less. 30. The core of a boiling water reactor according to claim 28,wherein said ratio of Pu-239 in all of said transuranic nuclides is 3% or more but less than 40%. 31. The core of a boiling water reactor according to claims 28,wherein an upper blanket zone, an upper fissile zone, an internal blanket zone, a lower fissile zone, and a lower blanket zone are axially disposed in turn from a top thereof. 32. The core of a boiling water reactor according to claim 28,wherein an upper blanket zone, a fissile zone, and a lower blanket zone are axially disposed in turn from a top thereof. 33. The core of a boiling water reactor according to claim 28,wherein said ratio of Pu-239 in all of said transuranic nuclides included in said fuel assembly with a burnup of 0 is 3% or more but 15% or less. 34. The core of a boiling water reactor according to claim 33,wherein said core is a parfait core disposing axially an upper blanket zone, an upper fissile zone, an internal blanket zone, a lower fissile zone, and a lower blanket zone in turn from a top thereof. 35. The core of a boiling water reactor according to claim 28, wherein said channel box is a hexagonal channel box and the transverse cross section of the unit fuel rod lattice which includes the portion of the moderator surrounding said fuel rod in said hexagonal channel box is a hexagonal transverse cross section. 36. The core of a boiling water reactor according to claim 35, wherein the hexagonal transverse cross section of the unit fuel rod lattice includes the transverse cross section of a substantially circular cross section of said fuel rod and a surrounding region of the moderator surrounding said fuel rod in a hexagonal shape in cross section. 37. A core of a boiling water reactor having a plurality of fuel assemblies including a plurality of isotopes of transuranic nuclides,wherein a ratio of Pu-239 in all Pu elements included in said fuel assembly loaded in said core with a burnup of 0 is 3% or more but 50% or less, and a ratio of Pu-240 in said all Pu elements is 35% or more but 45% or less;wherein said fuel assembly has a channel box and a plurality of fuel rods disposed in said channel box; andwherein a transverse cross section of a fuel pellet in said fuel rod occupies 30% or more but 55% or less of a transverse cross section of a unit fuel rod lattice in said channel box, the transverse cross section of the unit fuel rod lattice in said channel box including a transverse cross section of said fuel rod and a transverse cross section of a portion of a moderator surrounding said fuel rod in said channel box. 38. The core of a boiling water reactor according to claim 37,wherein an upper blanket zone, an upper fissile zone, an internal blanket zone, a lower fissile zone, and a lower blanket zone are axially disposed in turn from a top thereof. 39. The core of a boiling water reactor according to claim 38,wherein an upper blanket zone, a fissile zone, and a lower blanket zone are axially disposed in turn from a top thereof. 40. The core of a boiling water reactor according to claim 38,wherein said ratio of Pu-239 in all of said transuranic nuclides included in said fuel assembly with a burnup of 0 is 3% or more but 15% or less. 41. The core of a boiling water reactor according to claim 40,wherein said core is a parfait core disposing axially an upper blanket zone, an upper fissile zone, an internal blanket zone, a lower fissile zone, and a lower blanket zone in turn from a top thereof. 42. The boiling water reactor according to claim 37, wherein said ratio of Pu-239 in all of said transuranic nuclides is 40% or more but 45% or less. 43. The core of a boiling water reactor according to claim 37, wherein said channel box is a hexagonal channel box and the transverse cross section of the unit fuel rod lattice which includes the portion of the moderator surrounding said fuel rod in said hexagonal channel box is a hexagonal transverse cross section. 44. The core of a boiling water reactor according to claim 43, wherein the hexagonal transverse cross section of the unit fuel rod lattice includes the transverse cross section of a substantially circular cross section of said fuel rod and a surrounding region of the moderator surrounding said fuel rod in a hexagonal shape in cross section. 45. A fuel assembly for a boiling water reactor, comprising:a channel box; anda plurality of fuel rods disposed in the channel box, and having nuclear fuel material including a plurality of isotopes of transuranic nuclides,wherein a ratio of Pu-239 in all of said transuranic nuclides included in said nuclear fuel material is 3% or more but 45% or less when a burnup is 0; andwherein a transverse cross section of a fuel pellet in said fuel rod occupies 30% or more but 55% or less of a transverse cross section of a unit fuel rod lattice in said channel box, the transverse cross section of the unit fuel rod lattice in said channel box including a transverse cross section of said fuel rod and a transverse cross section of a portion of a moderator surrounding said fuel rod in said channel box. 46. The fuel assembly according to claim 45,wherein said ratio of Pu-239 in all of said transuranic nuclides is 40% or more but 45% or less when said burnup is 0. 47. The fuel assembly according to claim 45,wherein said ratio of Pu-239 in all of said transuranic nuclides is 3% or more but less than 40% when said burnup is 0. 48. The fuel assembly according to claim 47,wherein when said burnup is 0, said ratio of Pu-239 in all of said transuranic nuclides is 3% or more but 15% or less. 49. The fuel assembly according to claim 45,wherein an upper blanket zone, an upper fissile zone, an internal blanket zone, a lower fissile zone, and a lower blanket zone are axially disposed in an active fuel length in turn from a top thereof. 50. The fuel assembly according to claim 49,wherein when the burnup is 0, each of said blanket zones includes depleted uranium and does not include said transuranic nuclides, and each of said fissile zones includes said nuclear fuel material including said isotopes. 51. The fuel assembly according to claim 45,wherein an upper blanket zone, a fissile zone, and a lower blanket zone are axially disposed in an active fuel length in turn from a top thereof. 52. The fuel assembly according to claim 51,wherein when the burnup is 0, each of said blanket zones includes depleted uranium and does not include said transuranic nuclides, and each of said fissile zones includes said nuclear fuel material including said isotopes. 53. The fuel assembly according to claim 45,wherein ratios of said plurality of isotopes of said transuranic nuclides included in said nuclear fuel material when said fuel assembly is taken out of a core are substantially the same as ratios of said plurality of isotopes included in said nuclear fuel material when said fuel assembly is loaded in said core and has a burnup of 0. 54. The fuel assembly according to claim 45, wherein said channel box is a hexagonal channel box and the transverse cross section of the unit fuel rod lattice which includes the portion of the moderator surrounding said fuel rod in said hexagonal channel box is a hexagonal transverse cross section. 55. The fuel assembly according to claim 54, wherein the hexagonal transverse cross section of the unit fuel rod lattice includes the transverse cross section of a substantially circular cross section of said fuel rod and a surrounding region of the moderator surrounding said fuel rod in a hexagonal shape in cross section. 56. A fuel assembly for a boiling water reactor, comprising:a channel box; anda plurality of fuel rods disposed in the channel box, and having nuclear fuel material including a plurality of isotopes of transuranic nuclides;wherein a ratio of Pu-239 in all Pu elements included in said nuclear fuel material is 3% or more but 50% or less when a burnup is 0;wherein a ratio of Pu-240 in said all Pu elements is 35% or more but 45% or less when said burnup is 0; andwherein a transverse cross section of a fuel pellet in said fuel rod occupies 30% or more but 55% or less of a transverse cross section of a unit fuel rod lattice in said channel box, the transverse cross section of the unit fuel rod lattice in said channel box including a transverse cross section of said fuel rod and a transverse cross section of a portion of a moderator surrounding said fuel rod in said channel box. 57. The fuel assembly according to claim 56,wherein an upper blanket zone, an upper fissile zone, an internal blanket zone, a lower fissile zone, and a lower blanket zone are axially disposed in an active fuel length in turn from a top thereof. 58. The fuel assembly according to claim 57,wherein when the burnup is 0, each of said blanket zones includes depleted uranium and does not include said transuranic nuclides, and each of said fissile zones includes said nuclear fuel material including said isotopes. 59. The fuel assembly according to claim 56,wherein an upper blanket zone, a fissile zone, and a lower blanket zone are axially disposed in an active fuel length in turn from a top thereof. 60. The fuel assembly according to claim 59,wherein when the burnup is 0, each of said blanket zones includes depleted uranium and does not include said transuranic nuclides, and each of said fissile zones includes said nuclear fuel material including said isotopes. 61. The fuel assembly according to claim 59,wherein ratios of said plurality of isotopes of said transuranic nuclides being included in said nuclear fuel material when said fuel assembly is taken out of a core are substantially the same as ratios of said plurality of isotopes being included in said nuclear fuel material when said fuel assembly is loaded in said core and has a burnup of 0. 62. The fuel assembly according to claim 56, wherein said ratio of Pu-239 in all of said transuranic nuclides is 40% or more but 45% or less. 63. The fuel assembly according to claim 56, wherein said ratio of Pu-239 in all of said transuranic nuclides is 3% or more but less than 40%. 64. The fuel assembly according to claim 56, wherein said ratio of Pu-239 in all of said transuranic nuclides included in said fuel assembly with said burnup of 0 is 3% or more but 15% or less. 65. The fuel assembly according to claim 56, wherein said channel box is a hexagonal channel box and the transverse cross section of the unit fuel rod lattice which includes the portion of the moderator surrounding said fuel rod in said hexagonal channel box is a hexagonal transverse cross section. 66. The fuel assembly according to claim 65, wherein the hexagonal transverse cross section of the unit fuel rod lattice includes the transverse cross section of a substantially circular cross section of said fuel rod and a surrounding region of a moderator surrounding said fuel rod in a hexagonal shape in cross section. 67. A boiling water reactor comprising:a reactor pressure vessel;a core disposed in said reactor pressure vessel and loaded with a plurality of fuel assemblies including transuranic nuclides; anda coolant supplying apparatus which supplies a coolant to said core by pressurizing said coolant; anda coolant flow rate control apparatus which adjusts a flow rate of the coolant supplied to said core by controlling said coolant supplying apparatus, and said coolant flow rate control apparatus sets a coolant flow rate in an operation cycle to a set coolant flow rate which is determined based on a ratio of Pu-239 in transuranic nuclides included in said fuel assembly with a burnup of 0, which is loaded in said core before an operation starts in said operation cycle, so that ratios of a plurality of isotopes of transuranic nuclides present in said core upon the completion of said operation in said operation cycle are substantially the same as ratios of said plurality of isotopes in a state in which said operation in said operation cycle can be started;wherein a ratio of Pu-239 in all Pu elements included in said fuel assembly, which is loaded in said core, with a burnup of 0 is 3% or more but 50% or less;wherein a ratio of Pu-240 in said all Pu elements is 35% or more but 45% or less;wherein said fuel assembly has a channel box and a plurality of fuel rods disposed in said channel box; andwherein a transverse cross section of a fuel pellet in said fuel rod occupies 30% or more but 55% or less of a transverse cross section of a unit fuel rod lattice in said channel box, the transverse cross section of the unit fuel rod lattice in said channel box including a transverse cross section of said fuel rod and a transverse cross section of a portion of a moderator surrounding said fuel rod in said channel box. 68. The boiling water reactor according to claim 67,wherein said ratio of Pu-239 in all of said transuranic nuclides is 40% or more but 45% or less. 69. The boiling water reactor according to claim 67,wherein said ratio of Pu-239 in all of said transuranic nuclides is 3% or more but less than 40%. 70. The boiling water reactor according to claim 67, wherein said core is a parfait core being disposed axially an upper blanket zone, an upper fissile zone, an internal blanket zone, a lower fissile zone, and a lower blanket zone in turn from a top thereof. 71. The boiling water reactor according to claim 67, wherein said core is a one fissile zone core being disposed axially an upper blanket zone, a fissile zone, and a lower blanket zone in turn from a top thereof. 72. The boiling water reactor according to claim 67,wherein said ratio of Pu-239 in all of said transuranic nuclides included in said fuel assembly with said burnup of 0 is 3% or more but 15% or less. 73. The boiling water reactor according to claim 67, wherein said channel box is a hexagonal channel box and the transverse cross section of the unit fuel rod lattice which includes the portion of the moderator surrounding said fuel rod in said hexagonal channel box is a hexagonal transverse cross section. 74. The boiling water reactor according to claim 73, wherein the hexagonal transverse cross section of the unit fuel rod lattice includes the transverse cross section of a substantially circular cross section of said fuel rod and a surrounding region of a moderator surrounding said fuel rod in a hexagonal shape in cross section.